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Sample records for evaluation preliminary site

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-09-30

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.
Preliminary safety evaluation, based on initial site investigation data. Planning document

International Nuclear Information System (INIS)

Hedin, Allan

2002-12-01

This report is a planning document for the preliminary safety evaluations (PSE) to be carried out at the end of the initial stage of SKBs ongoing site investigations for a deep repository for spent nuclear fuel. The main purposes of the evaluations are to determine whether earlier judgements of the suitability of the candidate area for a deep repository with respect to long-term safety holds up in the light of borehole data and to provide feed-back to continued site investigations and site specific repository design. The preliminary safety evaluations will be carried out by a safety assessment group, based on a site model, being part of a site description, provided by a site modelling group and a repository layout within that model suggested by a repository engineering group. The site model contains the geometric features of the site as well as properties of the host rock. Several alternative interpretations of the site data will likely be suggested. Also the biosphere is included in the site model. A first task for the PSE will be to compare the rock properties described in the site model to previously established criteria for a suitable host rock. This report gives an example of such a comparison. In order to provide more detailed feedback, a number of thermal, hydrological, mechanical and chemical analyses of the site will also be included in the evaluation. The selection of analyses is derived from the set of geosphere and biosphere analyses preliminarily planned for the comprehensive safety assessment named SR-SITE, which will be based on a complete site investigation. The selection is dictated primarily by the expected feedback to continued site investigations and by the availability of data after the PSE. The repository engineering group will consider several safety related factors in suggesting a repository layout: Thermal calculations will be made to determine a minimum distance between canisters avoiding canister surface temperatures above 100 deg C
Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul

2013-04-30

The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.
Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

2013-09-30

This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.
Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

International Nuclear Information System (INIS)

Boardman, C.R.; Knutson, C.F.

1978-01-01

Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced
Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

Energy Technology Data Exchange (ETDEWEB)

Boardman, C.R.; Knutson, C.F.

1978-02-15

Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced.
Preliminary evaluation of the seismic hazard at Cernavoda NPP site

International Nuclear Information System (INIS)

Mingiuc, C.; Serban, V.; Androne, M.

2001-01-01

The probabilistic seismic hazard analysis (PSHA) is a methodology by which one evaluates the probability of exceeding different parameters of the ground motions (the maximum ground acceleration - PGA and the ground response spectrum - SA) as effect of the seismic action, on a given site at a future time moment. Due to the large uncertainties in the geological, geophysical, seismological input data, as well as, in the models utilised, various interpretation schemes are applied in the PSHA analyses. This interpretation schemes lead to opinion discrepancies among specialists which finally lead to disagreements in estimating the values of the seismic design for a given site. In order to re-evaluate the methodology and to improve the PSHA result stability, U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) and Electric Power Research Institute (EPRI) sponsored a project for defining methodological guides of performing PSHA analyses. The project was implemented by a panel of 7 experts, the Senior Seismic Hazard Analysis Committee - SSHAC. This paper presents a preliminary evaluation of the seismic hazard for the Cernavoda NPP site by application of the methodology mentioned, by taking into account the possible sources which could affect the site (the Vrancea focus, Galati - Tulcea fault, Sabla - Dulovo fault and local earthquakes)
Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-09-30

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an
Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-10-01

This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site
Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

2006-03-15

The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the
Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

International Nuclear Information System (INIS)

Andersson, Johan

2006-03-01

The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the
Preliminary Site Suitability Evaluation

International Nuclear Information System (INIS)

J. L. King

2001-01-01

Commercial electric power generation, nuclear weapons production, the operation of naval reactors, and research and development activities produce spent nuclear fuel and high-level radioactive waste. Spent nuclear fuel and high-level radioactive waste have been accumulating at commercial reactor sites and storage facilities across the country since 1957. Spent nuclear fuel and high-level radioactive waste have been accumulating at sites now managed by U.S. Department of Energy (DOE) since the mid-1940s. The DOE has the statutory obligation to dispose of these wastes. The U.S. has studied methods for the safe storage and disposal of radioactive waste for more than 40 years. Many organizations and government agencies have participated in these studies. In the 1950s, the U.S. Atomic Energy Commission requested the National Academy of Sciences to evaluate options for land disposal of radioactive waste. The U.S. Atomic Energy Commission and its successor agencies, the Energy Research and Development Administration and the DOE, continued to analyze radioactive waste management options throughout the 1960s and 1970s. In 1979, an Interagency Review Group that included representatives of 14 federal government entities provided findings and recommendations to the President. After analyzing a range of options, disposal in a geologic repository emerged as the preferred long-term environmental solution. This consensus is reflected in the Nuclear Waste Policy Act of 1982 (NWPA). The NWPA and related statutes established the framework for addressing the issues of radioactive waste disposal and designated the roles and responsibilities of the federal government and the owners and generators of the waste
Preliminary safety evaluation for the Simpevarp subarea. Based on data and site descriptions after the initial site investigation stage

International Nuclear Information System (INIS)

2005-04-01

The main objectives of this Preliminary safety evaluation (PSE) of the Simpevarp subarea are: to determine, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in the report SKB-TR--00-12. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that even considering remaining uncertainties, the Simpevarp subarea meets all safety requirements and most of the safety preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Simpevarp subarea. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Still, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry within the Simpevarp subarea would allow for a more specified layout, although the sensitivity analysis shows that the space needed is rather robust with respect to uncertainties in the zones. There is substantial uncertainty in the discrete fracture network (DFN) model
Preliminary evaluation of techniques for transforming regional climate model output to the potential repository site in support of Yucca Mountain future climate synthesis

International Nuclear Information System (INIS)

Church, H.W.; Zak, B.D.; Behl, Y.K.

1995-06-01

The report describes a preliminary evaluation of models for transforming regional climate model output from a regional to a local scale for the Yucca Mountain area. Evaluation and analysis of both empirical and numerical modeling are discussed which is aimed at providing site-specific, climate-based information for use by interfacing activities. Two semiempirical approaches are recommended for further analysis
Assessing the representativeness of wind data for wind turbine site evaluation

Science.gov (United States)

Renne, D. S.; Corotis, R. B.

1982-01-01

Once potential wind turbine sites (either for single installations or clusters) are identified through siting procedures, actual evaluation of the sites must commence. This evaluation is needed to obtain estimates of wind turbine performance and to identify hazards to the machine from the turbulence component of the atmosphere. These estimates allow for more detailed project planning and for preliminary financing arrangements to be secured. The site evaluation process can occur in two stages: (1) utilizing existing nearby data, and (2) establishing and monitoring an onsite measurement program. Since step (2) requires a period of at least 1 yr or more from the time a potential site has been identified, step (1) is often an essential stage in the preliminary evaluation process. Both the methods that have been developed and the unknowns that still exist in assessing the representativeness of available data to a nearby wind turbine site are discussed. How the assessment of the representativeness of available data can be used to develop a more effective onsite meteorological measurement program is also discussed.
Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

International Nuclear Information System (INIS)

Andersson, Johan

2005-08-01

The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to provide
Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

2005-08-01

The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to
Preliminary environmental site assessments in New York City

International Nuclear Information System (INIS)

Lundy, P.; Gasson, D.R.; Longendyke, S.T.

1991-01-01

Preliminary Environmental Site Assessments are often performed prior to real estate transactions or refinancing. These assessments are typically performed for real estate buyers, sellers and lending institutions. Undertaking a Preliminary Environmental Site Assessment in New York City can often be quite complex and time-consuming. This is due, in part, to the age and density of buildings in the city as well as the myriad of regulatory agencies with jurisdiction over environmental issues. This paper will discuss how environmental assessments are performed with a special emphasis on building in New York City. In includes hazardous wastes management for Radon, PCB's and asbestos
Preliminary investigation on determination of radionuclide distribution in field tracing test site

International Nuclear Information System (INIS)

Tanaka, Tadao; Mukai, Masayuki; Takebe, Shinichi; Guo Zede; Li Shushen; Kamiyama, Hideo.

1993-12-01

Field tracing tests for radionuclide migration have been conducted by using 3 H, 60 Co, 85 Sr and 134 Cs, in the natural unsaturated loess zone at field test site of China Institute for Radiation Protection. It is necessary to obtain confidable distribution data of the radionuclides in the test site, in order to evaluate exactly the migration behavior of the radionuclides in situ. An available method to determine the distribution was proposed on the basis of preliminary discussing results on sampling method of soils from the test site and analytical method of radioactivity in the soils. (author)
Preliminary Evaluation of Method to Monitor Landfills Resilience against Methane Emission

Science.gov (United States)

Chusna, Noor Amalia; Maryono, Maryono

2018-02-01

Methane emission from landfill sites contribute to global warming and un-proper methane treatment can pose an explosion hazard. Stakeholder and government in the cities in Indonesia been found significant difficulties to monitor the resilience of landfill from methane emission. Moreover, the management of methane gas has always been a challenging issue for long waste management service and operations. Landfills are a significant contributor to anthropogenic methane emissions. This study conducted preliminary evaluation of method to manage methane gas emission by assessing LandGem and IPCC method. From the preliminary evaluation, this study found that the IPCC method is based on the availability of current and historical country specific data regarding the waste disposed of in landfills while from the LandGEM method is an automated tool for estimating emission rates for total landfill gas this method account total gas of methane, carbon dioxide and other. The method can be used either with specific data to estimate emissions in the site or default parameters if no site-specific data are available. Both of method could be utilize to monitor the methane emission from landfill site in cities of Central Java.

Geoscientific evaluation factors and criteria for siting and site evaluation. Progress report

International Nuclear Information System (INIS)

Stroem, A.; Ericsson, Lars O.; Svemar, C.; Almen, K.E.; Andersson, Johan

1999-03-01

thereby involved. Requirements and preferences regarding the deep repository, and thereby the rock, are primarily formulated with respect to function and not directly for individual parameter values. In a similar manner the evaluation factors have been arranged per geoscientific discipline. A geoscientific parameter that can be measured or estimated in site investigations is considered to be a suitable evaluation factor if one of the following conditions is fulfilled: a direct requirement or an essential preference has been formulated for the parameter, or a the parameter is expected to have a great influence on the result of one or more important function analyses. Based on a preliminary list of possible evaluation factors, the level of knowledge that can or should be reached after the feasibility study, site investigation and detailed characterization have been completed is also discussed. It is not reasonable to designate a geoscientific parameter as an evaluation factor if the parameter cannot be measured or estimated with sufficient accuracy. Criteria for site evaluation will also be determined in the future work. When it comes to repository performance, criteria consist of indicative values or value ranges of outcomes of performance assessments. The criteria can be changed during the course of the siting work as the information available on the sites changes. But requirements and preferences remain the same. Even though the overall evaluation of the suitability of the sites is determined within the framework of an integrated safety assessment and an integrated construction analysis, the specified criteria should provide good guidance regarding the results of such an integrated assessment/analysis
Geoscientific evaluation factors and criteria for siting and site evaluation. Progress report

Energy Technology Data Exchange (ETDEWEB)

Stroem, A.; Ericsson, Lars O.; Svemar, C. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Almen, K.E. [KEA GEO-konsult AB (Sweden); Andersson, Johan [Golder Grundteknik KB (Sweden)

1999-03-01

thereby involved. Requirements and preferences regarding the deep repository, and thereby the rock, are primarily formulated with respect to function and not directly for individual parameter values. In a similar manner the evaluation factors have been arranged per geoscientific discipline. A geoscientific parameter that can be measured or estimated in site investigations is considered to be a suitable evaluation factor if one of the following conditions is fulfilled: a direct requirement or an essential preference has been formulated for the parameter, or a the parameter is expected to have a great influence on the result of one or more important function analyses. Based on a preliminary list of possible evaluation factors, the level of knowledge that can or should be reached after the feasibility study, site investigation and detailed characterization have been completed is also discussed. It is not reasonable to designate a geoscientific parameter as an evaluation factor if the parameter cannot be measured or estimated with sufficient accuracy. Criteria for site evaluation will also be determined in the future work. When it comes to repository performance, criteria consist of indicative values or value ranges of outcomes of performance assessments. The criteria can be changed during the course of the siting work as the information available on the sites changes. But requirements and preferences remain the same. Even though the overall evaluation of the suitability of the sites is determined within the framework of an integrated safety assessment and an integrated construction analysis, the specified criteria should provide good guidance regarding the results of such an integrated assessment/analysis 14 refs, figs, tabs
Preliminary site design for the SP-100 ground engineering test

International Nuclear Information System (INIS)

Cox, C.M.; Miller, W.C.; Mahaffey, M.K.

1986-04-01

In November, 1985, Hanford was selected by the Department of Energy (DOE) as the preferred site for a full-scale test of the integrated nuclear subsystem for SP-100. The Hanford Engineering Development Laboratory, operated by Westinghouse Hanford Company, was assigned as the lead contractor for the Test Site. The nuclear subsystem, which includes the reactor and its primary heat transport system, will be provided by the System Developer, another contractor to be selected by DOE in late FY-1986. In addition to reactor operations, test site responsibilities include preparation of the facility plus design, procurement and installation of a vacuum chamber to house the reactor, a secondary heat transport system to dispose of the reactor heat, a facility control system, and postirradiation examination. At the conclusion of the test program, waste disposal and facility decommissioning are required. The test site must also prepare appropriate environmental and safety evaluations. This paper summarizes the preliminary design requirements, the status of design, and plans to achieve full power operation of the test reactor in September, 1990
DOE responses to the State of New Mexico's comments on ''summary of the results of the evaluation of the WIPP site and preliminary design validation program'' (WIPP-DOE-161)

International Nuclear Information System (INIS)

1983-06-01

During the 60-day period provided for comments on the ''Summary of the Results of the Evaluation of the WIPP Site and Preliminary Design Validation Program'' (WIPP-DOE-161), written submittals and hearing testimony from about 133 individuals, 7 citizens groups and 6 state agencies were received by the Department of Energy (DOE). Approximately 25% of the public comment submittals were positive statements supporting the WIPP, with the remaining 75% reflecting concern with one or more aspects of the project. A portion of the state's comment package (submitted by the Governor of New Mexico) contained concerns relevant to WIPP which were unrelated to site suitability. Supportive comments formed the majority of the submittals from the New Mexico Environmental Evaluation Group (EEG) which ''...is charged with the responsibility of evaluating the suitability of the site for carrying out the mission of WIPP by analyzing all the reports and other information which form the background to the DOE evaluation of the site''
OSU TOMF Program Site Selection and Preliminary Concept Design Report

Energy Technology Data Exchange (ETDEWEB)

Spadling, Steve [Oklahoma State Univ., Stillwater, OK (United States)

2012-05-10

The purpose of this report is to confirm the programmatic requirements for the new facilities, identify the most appropriate project site, and develop preliminary site and building concepts that successfully address the overall project goals and site issues. These new facilities will be designed to accommodate the staff, drivers and maintenance requirements for the future mixed fleet of passenger vehicles, Transit Style Buses and School Buses.
Preliminary site requirements and considerations for a monitored retrievable storage facility

International Nuclear Information System (INIS)

1991-08-01

This report presents preliminary requirements and considerations for siting monitored retrievable storage (MRS) facility. It purpose is to provide guidance for assessing the technical suitability of potential sites for the facility. It has been reviewed by the NRC staff, which stated that this document is suitable for ''guidance in making preliminary determinations concerning MRS site suitability.'' The MRS facility will be licensed by the US Nuclear Regulatory Commission. It will receive spent fuel from commercial nuclear power plants and provide a limited amount of storage for this spent fuel. When a geologic repository starts operations, the MRS facility will also stage spent-fuel shipments to the repository. By law, storage at the MRS facility is to be temporary, with permanent disposal provided in a geologic repository to be developed by the DOE
Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site

International Nuclear Information System (INIS)

Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H.; Price, L.L.

1997-09-01

This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd 3 (4,580 m 3 ) of glass gems prior to disposal. This report documents Sandia National Laboratories' preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment
New Reactor Siting in Finland, Hanhikivi Site in Pyhaejoki - STUK preliminary safety assessment

International Nuclear Information System (INIS)

Nevalainen, Janne

2013-01-01

STUK has performed a preliminary assessment of the Decision-in-Principle on the Fennovoima application. A variety of factors must be considered in the selection of a site, including effects of the site on the plant design and the effects of the plant on the site environment. These include external hazards, both natural and human-induced. Since this is a new site, an extensive siting process is followed, that can include an EIA. A site survey is performed to identify candidate sites, after investigating a large region and rejecting unsuitable sites. The remaining sites are then screened and compared on the basis of safety and other considerations to select one or more preferred sites. Natural hazards include geology, seismology, hydrology and meteorology. Offshore ice will be a particular hazard for this plant, since the site is on average only 1.5 m above sea level. The design basis earthquake corresponds to a return frequency of 100,000 years, with 50 % confidence. The existing sites in southern Finland used a design peak ground acceleration of 0.1 g with the ground response spectrum maximum at 10 Hz. The candidate sites in northern Finland will require a peak ground acceleration of 0.2 g with the ground response spectrum maximum at 25 Hz
Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

International Nuclear Information System (INIS)

Lim, Doo Hyun; Hatanaka, Koichiro; Ishii, Eiichi

2010-01-01

JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information
Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

Energy Technology Data Exchange (ETDEWEB)

Lim, Doo Hyun [NE Union Hill Road, Suite 200, WA 98052 (United States); Hatanaka, Koichiro; Ishii, Eiichi [Japan Atomic Energy Agency, Hokkaido (Japan)

2010-10-15

JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information
Geoscientific long-term prognosis. Preliminary safety analysis for the site Gorleben

International Nuclear Information System (INIS)

Mrugalla, Sabine

2011-07-01

The preliminary safety analysis of the site Gorleben includes the following chapters: (1) Introduction; (2) Aim and content of the geoscientific long-term prognosis for the site Gorleben; (3) Boundary conditions at the site Gorleben: climate; geomorphology; overlying rocks and adjoining rocks; hydrogeology; salt deposit Gorleben. (4) Probable future geological developments at the site Gorleben: supraregional developments with effects on the site Gorleben; glacial period developments; developments of the geomorphology, overlying and adjoining rocks; future developments of the hydrological systems at the site Gorleben; future saliniferous specific developments of the salt deposit Gorleben. (5) Commentary on the unlikely or excludable developments of the site Gorleben.
Preliminary site characterization at Beishan northwest China-A potential site for China's high-level radioactive waste repository

International Nuclear Information System (INIS)

Wang Ju; Su Rui; Xue Weiming; Zheng Hualing

2004-01-01

Chinese nuclear power plants,radioactive waste and radioactive waste disposal are introduced. Beishan region (Gansu province,Northwest China)for high-level radioactive waste repository and preliminary site characterization are also introduced. (Zhang chao)
Evaluation of the radionuclide tracer test conducted at the project Gnome Underground Nuclear Test Site, New Mexico

International Nuclear Information System (INIS)

Pohll, G.; Pohlmann, K.

1996-08-01

A radionuclide tracer test was conducted in 1963 by the U.S. Geological Survey at the Project Gnome underground nuclear test site, approximately 40 km southeast of Carlsbad, New Mexico. The tracer study was carried out under the auspices of the U.S. Atomic Energy Commission (AEC) to study the transport behavior of radionuclides in fractured rock aquifers. The Culebra Dolomite was chosen for the test because it was considered to be a reasonable analogue of the fractured carbonate aquifer at the Nevada Test Site (NTS), the principal location of U.S. underground nuclear tests. Project Gnome was one of a small number of underground nuclear tests conducted by the AEC at sites distant from the NTS. The Gnome device was detonated on December 10, 1961 in an evaporate unit at a depth of 360 m below ground surface. Recently, the U.S. Department of Energy (DOE) implemented an environmental restoration program to characterize, remediate, and close these offsite nuclear test areas. An early step in this process is performance of a preliminary risk analysis of the hazard posed by each site. The Desert Research Institute has performed preliminary hydrologic risk evaluations for the groundwater transport pathway at Gnome. That evaluation included the radioactive tracer test as a possible source because the test introduced radionuclides directly into the Culebra Dolomite, which is the only aquifer at the site. This report presents a preliminary evaluation of the radionuclide tracer test as a source for radionuclide migration in the Culebra Dolomite. The results of this study will assist in planning site characterization activities and refining estimates of the radionuclide source for comprehensive models of groundwater transport st the Gnome site
Environmental Survey preliminary report, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1987-08-01

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Hanford Site, conducted August 18 through September 5, 1986. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Hanford Site. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Hanford Site, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by a DOE National Laboratory or a support contractor. When completed, the results will be incorporated into the Environmental Survey Interim Report for the Hanford Site. The Interim Report will reflect the final determinations of the Hanford Site Survey. 44 refs., 88 figs., 74 tabs
Environmental Survey preliminary report, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

1987-08-01

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Hanford Site, conducted August 18 through September 5, 1986. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Hanford Site. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Hanford Site, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by a DOE National Laboratory or a support contractor. When completed, the results will be incorporated into the Environmental Survey Interim Report for the Hanford Site. The Interim Report will reflect the final determinations of the Hanford Site Survey. 44 refs., 88 figs., 74 tabs.
Site evaluation for the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Hill, L.R.

1979-01-01

Preliminary site selection activities for the WIPP are complete now; these consisted primarily of national and regional studies over the past fifteen years, and resulted in selection of the WIPP study area for geological characterization. The work of geological characterization should be considered to have begun with the drilling of ERDA 9 at the center of the WIPP study area and the initiation of seismic reflection work on the site. That geological characterization, which is primarily oriented to provide specific data concerning the present geology of the site, was virtually complete in December, 1978, when the Geological Characterization Report was submitted to the Department of Energy; much basic information has been gathered indicating no major technical problems with the site as it is now understood. Studies of long-term processes which might affect a repository or have an effect on safety analyses will now be the major geotechnical activity for the WIPP site evaluation team, some of these activities are already underway. These studies will deal with the age of significant features and the rates and processes which produce those features. The information so gained will be useful in increasing the confidence in evaluation of the safety of a repository
Preliminary safety analysis of the Gorleben site

International Nuclear Information System (INIS)

Bracke, G.; Fischer-Appelt, K.

2014-01-01

The safety requirements governing the final disposal of heat-generating radioactive waste in Germany were implemented by the Federal Ministry of Environment, Natural Conservation and Nuclear Safety (BMU) in 2010. The Ministry considers as a fundamental objective the protection of man and the environment against the hazards of radioactive waste. Unreasonable burdens and obligation for future generations shall be avoided. The main safety principles are concentration and inclusion of radioactive and other pollutants in a containment-providing rock zone. Any release of radioactive nuclides may increase the risk for men and the environment only negligibly compared to natural radiation exposure. No intervention or maintenance work shall be necessary in the post-closure phase. Retrieval/recovery of the waste shall be possible up to 500 years after closure. The Gorleben salt dome has been discussed since the 1970's as a possible repository site for heat-generating radioactive waste in Germany. The objective of the project preliminary safety analysis of the Gorleben site (VSG) was to assess if repository concepts at the Gorleben site or other sites with a comparable geology could comply with these requirements based on currently available knowledge (Fischer-Appelt, 2013; Bracke, 2013). In addition to this it was assessed if methodological approaches can be used for a future site selection procedure and which technological and conceptual considerations can be transferred to other geological situations. The objective included the compilation and review of the available exploration data of the Gorleben site and on disposal in salt rock, the development of repository designs, and the identification of the needs for future R and D work and further site investigations. (authors)
Hydrogeochemical evaluation. Preliminary site description Laxemar subarea - version 1.2

International Nuclear Information System (INIS)

Laaksoharju, Marcus

2006-04-01

Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 for Laxemar subarea which represents the third evaluation of the available Simpevarp area groundwater analytical data collected up to November, 2004. Model version 1.2 focusses on improving the methodology and tools used for evaluating the hydrochemistry combined with a sensitivity and uncertainty analysis of the available data. The major goal has been to consolidate groundwater geochemical understanding and the models used at the site. The complex groundwater evolution and patterns at Simpevarp are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1,000 m depending on local topography. Close to the Baltic Sea coastline where topographical variation is small, groundwater flow penetration to depth will subsequently be less marked. In contrast, the Laxemar subarea is characterised by higher topography resulting in a much more dynamic groundwater circulation which appears to extend to 1,000 m depth in the vicinity of borehole KLX02. The marked differences in the groundwater flow regimes between the Laxemar and Simpevarp are reflected in the groundwater chemistry where four major hydrochemical
Hydrogeochemical evaluation. Preliminary site description Laxemar subarea - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Laaksoharju, Marcus (ed.) [Geopoint AB, Stockholm (Sweden)

2006-04-15

Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 for Laxemar subarea which represents the third evaluation of the available Simpevarp area groundwater analytical data collected up to November, 2004. Model version 1.2 focusses on improving the methodology and tools used for evaluating the hydrochemistry combined with a sensitivity and uncertainty analysis of the available data. The major goal has been to consolidate groundwater geochemical understanding and the models used at the site. The complex groundwater evolution and patterns at Simpevarp are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1,000 m depending on local topography. Close to the Baltic Sea coastline where topographical variation is small, groundwater flow penetration to depth will subsequently be less marked. In contrast, the Laxemar subarea is characterised by higher topography resulting in a much more dynamic groundwater circulation which appears to extend to 1,000 m depth in the vicinity of borehole KLX02. The marked differences in the groundwater flow regimes between the Laxemar and Simpevarp are reflected in the groundwater chemistry where four major
Preliminary site characterization radiological monitoring plan for the Nevada Nuclear Waste Storage Investigations Project, Yucca Mountain Site

International Nuclear Information System (INIS)

1987-03-01

The activities described in this plan occur in the early phases of site characterization. This document presents the Preliminary Site Characterization Radiological Monitoring Plan (PSCRMP) for collecting and evaluating data in support of the NNWSI Project. The PSCRMP defines and identifies control procedures for the monitoring activities. The PSCRMP activity will utilize integrating radon monitoring devices, a continuous radon monitor, and a particulate air sampler. These instruments will be used to establish the baseline radioactivity and/or radioactivity released due to early site characterization activities. The sections that follow provide a general project description, the specifics of the monitoring program, and the practices that will be employed to ensure the validity of the collected data by integrating quality assurance into all activities. Section 2 of this document describes the regulatory base of this document. Section 3 describes the site characterization activities which may lead to release of radioactivity. Section 4 provides a description of the potential sources of radioactivity that site characterization could generate. Section 5 summarizes the sampling and monitoring methodology, which will be used to monitor the potential sources of radioactivity. The network of sampling and monitoring equipment is described in Section 6, and Section 7 summarizes the systems operation activities. The data reporting activities are described in Section 8. Finally, a description of the Quality Assurance (QA) and Quality Control (QC) activities is provided in Section 9. Appendix A contains a summary of the procedures to be used in this program, and Appendix B contains technical specification on equipment and services. 20 refs., 11 figs., 2 tabs

Hydrogeochemical evaluation. Preliminary site description Forsmark area - version 1.2

International Nuclear Information System (INIS)

Laaksoharju, Marcus

2005-03-01

Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Forsmark and Laxemar-Simpevarp, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Forsmark groundwater analytical data collected up to June, 2004. The Hydrochemical Analytical Group (HAG) had access to data where a total of 1,131 water samples had been collected from the surface and sub-surface environment; 252 samples were collected from drilled boreholes. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1 km. Most of the waters sampled (66%) lacked crucial analytical information that restricted the evaluation. Model version 1.2 focuses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1,000 m depth. The complex groundwater evolution and patterns at Forsmark are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/ transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Forsmark are considered local and extend down to depths of around 600 m depending on hydraulic conditions. Close to the Baltic Sea coastline where topographical variation is even less, groundwater flow penetration to depth will subsequently be less marked and such areas will tend to be characterised by groundwater
Hydrogeochemical evaluation. Preliminary site description Forsmark area - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Laaksoharju, Marcus (ed.) [Geopoint AB, Stockholm (Sweden)

2005-03-15

Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Forsmark and Laxemar-Simpevarp, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Forsmark groundwater analytical data collected up to June, 2004. The Hydrochemical Analytical Group (HAG) had access to data where a total of 1,131 water samples had been collected from the surface and sub-surface environment; 252 samples were collected from drilled boreholes. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1 km. Most of the waters sampled (66%) lacked crucial analytical information that restricted the evaluation. Model version 1.2 focuses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1,000 m depth. The complex groundwater evolution and patterns at Forsmark are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/ transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Forsmark are considered local and extend down to depths of around 600 m depending on hydraulic conditions. Close to the Baltic Sea coastline where topographical variation is even less, groundwater flow penetration to depth will subsequently be less marked and such areas will tend to be characterised by
Site study plan for Deep Hydronest Test Wells, Deaf Smith County Site, Texas: Preliminary draft

International Nuclear Information System (INIS)

1987-05-01

Wells called Deep Hydronest Wells will be installed at six locations at the Deaf Smith County Site to characterize hydraulic parameters in the geologic column between the top of the San Andres Formation and the base of Pennsylvanian System. Three hydronests will be drilled during early stages of site characterization to provide data for performance assessment modeling. Four wells are proposed for each of these 3 nests. Results of drilling, testing, and preliminary modeling will direct drilling and testing activities at the last 3 nests. Two wells are proposed at each of the last 3 nests for a total of 18 wells. The Salt Repository Project (SRP) Networks specify the schedule under which this program will operate. Drilling and hydrologic testing of the first Deep Hydronest will begin early in the Surface Investigation Program. Drilling and testing of the first three Deep Hydronests will require about 18 months. After 12 months of evaluating and analyzing data from the first three hydronests, the remaining three hydronests will be drilled during a 12-month period. The Technical Field Services Contractor is responsible for conducting the field program. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be used to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 36 refs., 20 figs., 6 tabs
Description of the Northwest hazardous waste site data base and preliminary analysis of site characteristics

International Nuclear Information System (INIS)

Woodruff, D.L.; Hartz, K.E.; Triplett, M.B.

1988-08-01

The Northwest Hazardous Waste RD and D Center (the Center) conducts research, development, and demonstration (RD and D) activities for hazardous and radioactive mixed-waste technologies applicable to remediating sites in the states of Idaho, Montana, Oregon, and Washington. To properly set priorities for these RD and D activities and to target development efforts it is necessary to understand the nature of the sites requiring remediation. A data base of hazardous waste site characteristics has been constructed to facilitate this analysis. The data base used data from EPA's Region X Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) and from Preliminary Assessment/Site Investigation (PA/SI) forms for sites in Montana. The Center's data base focuses on two sets of sites--those on the National Priorities List (NPL) and other sites that are denoted as ''active'' CERCLIS sites. Active CERCLIS sites are those sites that are undergoing active investigation and analysis. The data base contains information for each site covering site identification and location, type of industry associated with the site, waste categories present (e.g., heavy metals, pesticides, etc.), methods of disposal (e.g., tanks, drums, land, etc.), waste forms (e.g., liquid, solid, etc.), and hazard targets (e.g., surface water, groundwater, etc.). As part of this analysis, the Northwest region was divided into three geographic subregions to identify differences in disposal site characteristics within the Northwest. 2 refs., 18 figs., 5 tabs
Preliminary site characterization - final report

Energy Technology Data Exchange (ETDEWEB)

Clark, D.; Smith, L.B.

1993-12-01

This report summarizes the ecological unit reconnaissance conducted at the F-Area Burning/Rubble Pit(s) RCRA/CERCLA Unit (F-Area BRP) on August 30 and 31, 1993 as part of the RFI/RI baseline risk assessment for the waste unit The baseline risk assessment will assess the potential endangerment to human health and the environment associated with the unit and will be used to evaluate remediation criteria, if needed. The information presented in this report will be used in subsequent stages of the ecological risk assessment to refine the conceptual site model, assist in the selection of contaminants of concern, identify potential ecological receptors, and evaluate trophic relationships and other exposure pathways. The unit reconnaissance survey was conducted in accordance with Specification No. E-18272, Rev. 1 dated August 5, 1993, and the Draft {open_quotes}Ecological Risk Assessment Program Plan for Evaluation of Waste Sites on the Savannah River Site{close_quotes}. The objectives of the site reconnaissance were to: Assess the general characteristics of on-unit biological communities including mammals, birds, reptiles, amphibians, and any aquatic communities present. Determine the location, extent, and characteristics of on-unit ecological resources, such as forested areas and wetlands, that could serve as important wildlife habitat or provide other ecological functions. Identify any overt effects of contamination on biological communities. The field investigations included mapping and describing all wetland and terrestrial habitats; recording wildlife observations of birds, mammals, and reptiles; and investigating ecological resources in nearby downgradient and downstream areas which could be affected by mobile contaminants or future remedial actions. In preparation for the field investigation, existing unit information including aerial photographs and reports were reviewed to help identify and describe ecological resources at the waste unit.
Superfund TIO videos. Set A. Identifying PRPS. Removal process: Removal site evaluation. Part 2. Audio-Visual

International Nuclear Information System (INIS)

1990-01-01

The videotape is divided into three sections. Section 1 details the liability of Potentially Responsible Parties (PRPs) and describes the four classes of PRPs: current owners and operators, former owners and operators, generators, and transporters (if they selected the site). Section 2 lists the goals of the Potentially Responsible Party (PRP) search and explains how to identify key players during the PRP search. How to plan and conduct the PRP search is also outlined. Section 3 outlines the steps involved in conducting a removal site evaluation. A discussion of when to conduct a removal preliminary assessment, a removal site inspection, and an Engineering Evaluation/Cost Analysis (EE/AC) also is covered
Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

1994-09-01

The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.
Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

1994-09-01

The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria
Preliminary screening analysis of the off-site environment downstream of the US Department of Energy Oak Ridge Reservation

International Nuclear Information System (INIS)

Blaylock, B.G.; Hoffman, F.O.; Frank, M.L.

1990-01-01

Operations and waste disposal activities at the Y-12 Plant, the Oak Ridge National Laboratory (ORNL), and the Oak Ridge Gaseous Diffusion Plant (ORGDP), located on the US Department of Energy (DOE) Oak Ridge Reservation (ORR) in eastern Tennessee, have introduced airborne, liquid, and solid wastes into the surrounding environment. Some of these wastes may affect off-site areas by entering local streams that ultimately drain into the Clinch River. Previously reported concentrations of radionuclides, metals, and organic compounds in water, sediment, and biota of the Clinch River and Watts Bar Reservoir suggest the presence of contaminants of possible concern to the protection of human health and the environment. A preliminary screening was conducted of contaminants in the off-site surface water environments downstream of the DOE ORR. This screening analysis represents part of a scoping phase of the Clinch River Resource Conservation and Recovery Facilities Investigation (CRRFI). The purpose of this preliminary screening analysis is to use existing data on off-site contaminant concentrations to identify and prioritize potential contaminants of concern for further evaluation and investigation. The primary objective of this screening analysis is to ensure that CRRFI sampling and analysis efforts focus on those contaminants that may possibly contribute to human health or environmental risk. 8 refs., 3 figs., 6 tabs
Preliminary evaluation of the Accident Response Mobile Manipulation System for accident site salvage operations

International Nuclear Information System (INIS)

Trujillo, J.M.; Morse, W.D.; Jones, D.P.

1994-01-01

This paper describes and evaluates operational experiences with the Accident Response Mobile Manipulation System (ARMMS) during simulated accident site salvage operations which might involve nuclear weapons. The ARMMS is based upon a teleoperated mobility platform with two Schilling Titan 7F Manipulators
Analysis and evaluation of the Gorleben site characteristics. Report on the working package 2. Preliminary safety analysis Gorleben

International Nuclear Information System (INIS)

Kukla, Peter; Pechnig, Renate; Urai, Janos

2011-10-01

The report on analysis and evaluation of the Gorleben site characteristics covers the following chapters: Site characteristics on the hydrology of the cover rock: hydrology and hydraulic properties, geothermal studies, ground water properties and motion, model calculations. Site characteristics on geology of the cover and adjoining rock: borehole explorations, geologic development, 3D geometry of the salt dome Gorleben, geologic development of the salt structure Gorleben. Site characteristics on the saliniferous formation: geophysical exploration, modeling of the internal structure of the salt dome Gorleben, fluids in the salt dome Gorleben. Geotechnical studies at the site: geothermal studies, hydraulic data on the saliniferous formation, thermal model calculations, geomechanical in-situ measurements, mechanical and transport properties, thermo-mechanical modeling. Summarized evaluation of the site characteristics and further research requirement.
Preliminary risk assessment of Power Plant Plomin site contaminated by radioactive slag and ash

International Nuclear Information System (INIS)

Skanata, D.; Sinka, D.; Lokner, V.; Schaller, A.

1996-01-01

There is a certain number of radioactively contaminated sites in the Republic of Croatia, one of them being known as Power Plant Plomin site, which contains radioactive slag and ash. Due to a relatively high quantity of the deposited material, as well as relatively high population density of the neighbouring area, it is very important to assess the impact of the site on human health and environment. Using RESRAD computer code and PATHRAE method a preliminary assessment of doses and radiation risks for the workers who spend most of their working day at the pile has been performed. PATHRAE method has also been used for the assessment of radiation risks for the neighbouring population. The assessment is preliminary in its character due to the lack of input data. On the basis of assessment results, recommendations are being given comprising measurements to be taken with a view to coming up with the final risk assessment, as well as protective measures which should be undertaken in the meantime. (author)
American College of Radiology Accreditation Program for mammographic screening sites: Physical evaluation criteria

International Nuclear Information System (INIS)

Hendrick, R.E.; Haus, A.G.; Hubbard, L.B.; Lasky, H.J.; McCrohan, J.; McLelland, R.; Rothenberg, L.N.; Tanner, R.L.; Zinninger, M.D.

1987-01-01

The American College of Radiology has initiated a program for the accreditation of mammographic screening sites, which includes evaluation by mail of image quality and average glandular breast dose. Image quality is evaluated by use of a specially designed phantom (a modified RMI 152D Mammographic Phantom) containing simulated microcalcifications, fibrils and masses. Average glandular dose to a simulated 4.5-cm-thick (50% glandular, 50% fat) compressed breast is evaluated by thermoluminescent dosimeter measurements of entrance exposure and half value layer. Standards for acceptable image quality and patient doses are presented and preliminary results of the accreditation program are discussed
Environmental Survey preliminary report, Nevada Test Site, Mercury, Nevada

International Nuclear Information System (INIS)

1988-04-01

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Nevada Test Site (NTS), conducted June 22 through July 10, 1987. The Survey is being conducted by a multidisciplinary team of environmental specialists led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team members are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the NTS. The Survey covers all environment media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations and activities performed at the NTS, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain environmental problems identified during its on-site activities. The Sampling and Analysis Plan is being executed by the Battelle Columbus Division under contract with DOE. When completed, the results will be incorporated into the NTS Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the NTS Survey. 165 refs., 42 figs., 52 tabs
Preliminary site characterization - final report

International Nuclear Information System (INIS)

Clark, D.; Smith, L.B.

1993-12-01

This report summarizes the ecological unit reconnaissance conducted at the F-Area Burning/Rubble Pit(s) RCRA/CERCLA Unit (F-Area BRP) on August 30 and 31, 1993 as part of the RFI/RI baseline risk assessment for the waste unit The baseline risk assessment will assess the potential endangerment to human health and the environment associated with the unit and will be used to evaluate remediation criteria, if needed. The information presented in this report will be used in subsequent stages of the ecological risk assessment to refine the conceptual site model, assist in the selection of contaminants of concern, identify potential ecological receptors, and evaluate trophic relationships and other exposure pathways. The unit reconnaissance survey was conducted in accordance with Specification No. E-18272, Rev. 1 dated August 5, 1993, and the Draft open-quotes Ecological Risk Assessment Program Plan for Evaluation of Waste Sites on the Savannah River Siteclose quotes. The objectives of the site reconnaissance were to: Assess the general characteristics of on-unit biological communities including mammals, birds, reptiles, amphibians, and any aquatic communities present. Determine the location, extent, and characteristics of on-unit ecological resources, such as forested areas and wetlands, that could serve as important wildlife habitat or provide other ecological functions. Identify any overt effects of contamination on biological communities. The field investigations included mapping and describing all wetland and terrestrial habitats; recording wildlife observations of birds, mammals, and reptiles; and investigating ecological resources in nearby downgradient and downstream areas which could be affected by mobile contaminants or future remedial actions. In preparation for the field investigation, existing unit information including aerial photographs and reports were reviewed to help identify and describe ecological resources at the waste unit
Preliminary Hazard Classification for the Remediation of the 100-B/C Area Remaining Sites (Confirmatory Sampling Effort)

International Nuclear Information System (INIS)

Routt, T.M.

2000-01-01

This document provides the preliminary hazard classification for the sampling and characterization activities to be conducted at the 100-B/C confirmatory sampling effort sites in support of remedial design and eventual remediation of these sites
Preliminary thermal/thermomechanical analyses of the Site Characterization Plan's Conceptual Design for a repository containing horizontally emplaced waste packages at the Deaf Smith County site

International Nuclear Information System (INIS)

Ghantous, N.Y.; Raines, G.E.

1987-10-01

This report presents thermal/thermomechanical analyses of the Site Characterization Plan Conceptual Design for horizontal package emplacement at the Deaf Smith County site, Texas. The repository was divided into three geometric regions. Then two-dimensional finite-element models were set up to approximate the three-dimensional nature of each region. Thermal and quasistatic thermomechanical finite-element analyses were performed to evaluate the thermal/thermomechanical responses of the three regions. The exponential-time creep law was used to represent the creep behavior of salt rock. The repository design was evaluated by comparing the thermal/thermomechanical responses obtained for the three regions with interim performance constraints. The preliminary results show that all the performance constraints are met except for those of the waste package. The following factors were considered in interpreting these results: (1) the qualitative description of the analytical responses; (2) the limitations of the analyses; and (3) either the conclusions based on overall evaluation of limitations and analytical results or the conclusions based on the fact that the repository design may be evaluated only after further analyses. Furthermore, a parametric analysis was performed to estimate the effect of material parameters on the predicted thermal/thermomechanical response. 23 refs., 34 figs., 9 tabs
Canada's Deep Geological Repository for Used Nuclear Fuel - Geo-scientific Site Evaluation Process - 13117

International Nuclear Information System (INIS)

Blyth, Alec; Ben Belfadhel, Mahrez; Hirschorn, Sarah; Hamilton, Duncan; McKelvie, Jennifer

2013-01-01

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable rock formation at a depth of approximately 500 meters (m) (1,640 feet [ft]). In May 2010, the NWMO published a nine-step site selection process that serves as the road map to decision-making on the location for the deep geological repository. The safety and appropriateness of any potential site will be assessed against a number of factors, both technical and social in nature. The selected site will be one that can be demonstrated to be able to safely contain and isolate used nuclear fuel, protecting humans and the environment over the very long term. The geo-scientific suitability of potential candidate sites will be assessed in a stepwise manner following a progressive and thorough site evaluation process that addresses a series of geo-scientific factors revolving around five safety functions. The geo-scientific site evaluation process includes: Initial Screenings; Preliminary Assessments; and Detailed Site Evaluations. As of November 2012, 22 communities have entered the site selection process (three in northern Saskatchewan and 18 in northwestern and southwestern Ontario). (authors)
Site 300 hazardous-waste-assessment project. Interim report: December 1981. Preliminary site reconnaissance and project work plan

International Nuclear Information System (INIS)

Raber, E.; Helm, D.; Carpenter, D.; Peifer, D.; Sweeney, J.

1982-01-01

This document was prepared to outline the scope and objectives of the Hazardous Waste Assessment Project (HWAP) at Site 300. This project was initiated in October, 1981, to investigate the existing solid waste landfills in an effort to satisfy regulatory guidelines and assess the potential for ground-water contamination. This involves a site-specific investigation (utilizing geology, hydrology, geophysics and geochemistry) with the goal of developing an effective ground-water quality monitoring network. Initial site reconnaissance work has begun and we report the results, to date, of our geologic hydrogeologic studies. All known solid waste disposal locations are underlain by rocks of either the Late Miocene Neroly Formation or the Cierbo Formation, both of which are dominantly sandstones interbedded with shale and claystone. The existence of a regional confined (artesian) aquifer, as well as a regional water-table aquifer is postulated for Site 300. Preliminary analysis has led to an understanding of directions and depths of regional ground-water flow
Preliminary Evaluation of a Practice-Based EBVM Skills Development Program

Directory of Open Access Journals (Sweden)

Ava Firth

2016-12-01

Full Text Available Whilst there is a small body of research that investigates the development of EBVM skills in veterinary undergraduates there is a paucity of research that aims to understand the development of EBVM skills in practice-based post-graduate veterinary surgeons. This paper is a small step in remedying that shortfall. In particular, the paper provides a progress report on an RCVS Knowledge funded study that is evaluating a practice-based EBVM development program. The program is being conducted with a cohort of 20 veterinary surgeons and veterinary nurses employed in a private practice veterinary company across multiple sites. The facilitated instruction approach incorporates multiple supports including; group based and one-to-one, synchronous and asynchronous, and, face-to-face and online strategies. This paper will provide details of both the facilitation and evaluation approaches that have been adopted. The paper will also report on preliminary results of the evaluation which focuses on barriers and facilitators to EBVM development.This is a podcast of Ava and Ian's talk at the Veterinary Evidence Today conference, Edinburgh November 2, 2016.

Preliminary Geological Survey on the Proposed Sites for the New Research Reactor

International Nuclear Information System (INIS)

Lim, In Cheol; Ha, J. J.; Oh, K. B.

2010-12-01

· Performing the preliminary geological survey on the proposed sites for the new research reactor through the technical service · Ordering a technical service from The Geological Society of Korea · Contents of the geological survey - Confirmation of active fault - Confirmation of a large-scale fracture zone or weak zone - Confirmation of inappropriate items related to the underground water - Confirmation of historical seismicity and instrumental earthquakes data · Synthesized analysis and holding a report meeting · Results of the geological survey - Confirmation of the geological characteristics of the sites and drawing the requirements for the precise geological survey in the future
Process for determining the remediation category of hazardous substance sites

International Nuclear Information System (INIS)

Sieben, A.K.

1994-01-01

An evaluation process has been developed that aids in selecting the appropriate remediation category of hazardous substance sites. Three general remediation categories have been established: No further Action: Potential Early Action: and Defer for RI/FS or Transition/Decontamination and Decommissioning. This evaluation method is a preliminary screening process only and will not identify the most appropriate remediation alternative for each site. The remedy selection process can proceed only after a remediation category is determined for each site. All sites are evaluated at a preliminary screening level to determine the general remediation category. After the first screen, a secondary evaluation is performed on both the PEA sites and the DEFER sites. For PEAs, this secondary evaluation will incorporate additional specific factors, such as a screening level risk assessment. For the DEFER sites feasibility factors will be used to distinguish between the sites which should undergo a normal RI/FS and the sites which will be recommended to be remediated in association with D ampersand D of buildings. Ultimately, all of the sites will be placed into one of four remediation categories
Identification and evaluation of areas of interest (AOIs): A screening tool for CERCLA preliminary assessments

International Nuclear Information System (INIS)

Autry, A.R.; Allen, K.L.; Smith, L.A.; Schumacher, J.; McDermott, M.

1994-01-01

A cost-effective alternative to the traditional Preliminary Assessment (PA) procedure is to identify and evaluate potential Areas of Interest (AOIs) that may become Comprehensive Environmental Response, Liability and Compensation Act of 1980 (CERCLA) sites prior to entry into Comprehensive Environmental Response, Liability Information System (CERCLIS) and the execution of a PA. AOIs would be identified by using much of the same methodology as would be used for site discovery in a CERCLA investigation, including aerial photograph review, reviews of building drawings, a limited review of historical records, and limited interviews and site visits. Once AOIs have been identified in this manner, decision criteria can be used to ascertain the regulatory status of the AOI and, based on regulatory guidance, whether the site should be considered for further investigation under CERCLA. This approach was used at Griffiss Air Force Base to identify 463 AOIs, where the primary problem was petroleum spills
Environmental Survey preliminary report, Nevada Test Site, Mercury, Nevada

Energy Technology Data Exchange (ETDEWEB)

1988-04-01

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Nevada Test Site (NTS), conducted June 22 through July 10, 1987. The Survey is being conducted by a multidisciplinary team of environmental specialists led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team members are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the NTS. The Survey covers all environment media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations and activities performed at the NTS, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain environmental problems identified during its on-site activities. The Sampling and Analysis Plan is being executed by the Battelle Columbus Division under contract with DOE. When completed, the results will be incorporated into the NTS Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the NTS Survey. 165 refs., 42 figs., 52 tabs.
Lessons learned from the preliminary performance assessment exercise for the Vienne site strategies for investigating the granodiorite confinement capability

International Nuclear Information System (INIS)

Lebon, P.

1999-01-01

One of the three sites under study by ANDRA is located on the Poitou shoal in the Vienne Department. The granitic basement rock is overlain by a 160 m thick layer of Jurassic sediments containing two seasonally pumped aquifers. The preliminary hydrogeological model of the granitic basement assumed that regional flow is SE-NW, and circulates in the hecto-metric fractures, and that groundwater flow velocity is very low. A preliminary performance assessment exercise focusing on the geological barrier was carried out based on these assumptions and a disposal concept where radwaste is stored in separate granodiorite 'blocks' delimited by the water-bearing fractures. As regards of the granodioritic blocks, the programme goals include analysing of detailed structure, obtaining uncontaminated samples of interstitial ground water in order to determine its physicochemical properties and evaluating transport and retention parameters. (author)
Towards understanding household-level forest reliance in Cambodia - study sites, methods, and preliminary findings

DEFF Research Database (Denmark)

Ra, Koy; Pichdara, Lonn; Dararath, Yem

There is growing international interest in the role of forests in poverty prevention and reduction. In consequence, this broad area of investigation has been subject to increased research; one major international research project is that facilitated by the Poverty Environment Network (PEN). This ......). This project covers a large number of sites in 26 countries throughout the tropics. The present report contains contextual details, methodological information and preliminary findings for the PEN sites in Cambodia....
Construction of Basic Evaluation Criteria for Candidate HLW Repository Sites (1)

International Nuclear Information System (INIS)

Koh, Yong Kwon; Bae, Dae Seok; Kim, Kyung Su; Kim, Geon Young; Park, Kyung Woo; Ji, Sung Hoon; Ryu, Ji Hun

2009-08-01

We constructed the preliminary site assessment system for selection of proper site as high level radioactive disposal repository with consideration of Korean geological characteristics and underground environments. And, site assessment factor and standard as a point of geologic aspect were suggested for decision of candidate radioactive disposal site in Korea. The results can be used to develop the geological information system for assessment of candidate disposal site
Evaluation of the suitability of the WIPP site

International Nuclear Information System (INIS)

Neill, R.H.; Channell, J.K.; Chaturvedi, L.; Little, M.S.; Rehfeldt, K.; Spiegler, P.

1983-05-01

Determination of the suitability of the site for WIPP is only the first major phase in the evaluation of the radiological impact of the repository on the public health and safety. The Environmental Evaluation Group (EEG) will continue to independently review the design of the facility, the operational procedures, the criteria for packaging and shipment of the waste, the plans, procedures and results of the WIPP experiments, emergency preparedness, adherence to EPA and pertinent NRC regulations, and other important features of the project. EEG has concluded from existing evidence that the Los Medanos site for the WIPP project has been characterized in sufficient detail to warrant confidence in the validation of the site for the permanent emplacement of approximately 6 million cubic feet of defense transuranic waste. This conclusion is based on the assumption that the maximum surface dose rate for the unshielded remote-handled transuranic waste canisters will be 100 rem/hr with a maximum radionuclide concentration of 23 Ci/liter. The Site and Preliminary Design Validation program, through the drilling of two shafts to the selected repository level at 2160 ft below the surface and excavation of about 9000 ft of tunnels, has confirmed the interpretations made about the subsurface geological conditions at the site. For an assessment of the potential radiation effects of the nuclear waste repository on the public health and safety, it is necessary to understand the regional geological and hydrological setting. Much work has been done to understand these conditions and to address several specific issues which have arisen as a result of such studies. However, it is almost inevitable that some questions remain unanswered at a given time in the decision-making process. EEG has identified work which still needs to be done at the Los Medanos site in order to improve confidence in the worst case scenario models of possible breaches of the repository
Chemical Analysis of the Moon at the Surveyor VII Landing Site: Preliminary Results.

Science.gov (United States)

Turkevich, A L; Franzgrote, E J; Patterson, J H

1968-10-04

The alpha-scattering experiment aboard Surveyor VII has provided a chemical analysis of the moon in the area of the crater Tycho. The preliminary results indicate a chemical composition similar to that already found at two mare sites, but with a lower concentration of elements of the iron group (titanium through copper).
Regional hydrogeological simulations using CONECTFLOW. Preliminary site description. Laxemar sub area - version 1.2

International Nuclear Information System (INIS)

Hartley, Lee; Hunter, Fiona; Jackson, Peter; McCarthy, Rachel; Gylling, Bjoern; Marsic, Niko

2006-04-01

The main objective of this study is to support the development of a preliminary Site Description of the Laxemar subarea on a regional-scale based on the available data of November 2004 (Data Freeze L1.2). A more specific objective of this study is to assess the role of both known and less quantified hydrogeological conditions in determining the present-day distribution of saline groundwater in the Laxemar subarea on a regional-scale. An improved understanding of the palaeo-hydrogeology is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. This is to serve as a basis for describing the present hydrogeological conditions on a local-scale, as well as predictions of future hydrogeological conditions. Another objective is to assess the flow-paths from the local-scale model domain, based on the present-day flow conditions, to assess the distribution of discharge and recharge areas connected to the flow at the approximate repository depth to inform the Preliminary Safety Evaluation. Significant new features incorporated in the modelling include: a depth variation in hydraulic properties within the deformation zones; a dependence on rock domain and depth in the rock mass properties in regional-scale models; a more detailed model of the overburden in terms of a layered system of spatially variable thickness made up of several different types of Quaternary deposits has been implemented; and several variants on the position of the watertable have been tried. The motivation for introducing a dependence on rock domain was guided by the hydrogeological interpretation with the aim of honouring the observed differences in hydraulic properties measured at the boreholes
Regional hydrogeological simulations using CONECTFLOW. Preliminary site description. Laxemar sub area - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Hartley, Lee; Hunter, Fiona; Jackson, Peter; McCarthy, Rachel [Serco Assurance, Risley (United Kingdom); Gylling, Bjoern; Marsic, Niko [Kemakta Konsult AB, Stockholm (Sweden)

2006-04-15

The main objective of this study is to support the development of a preliminary Site Description of the Laxemar subarea on a regional-scale based on the available data of November 2004 (Data Freeze L1.2). A more specific objective of this study is to assess the role of both known and less quantified hydrogeological conditions in determining the present-day distribution of saline groundwater in the Laxemar subarea on a regional-scale. An improved understanding of the palaeo-hydrogeology is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. This is to serve as a basis for describing the present hydrogeological conditions on a local-scale, as well as predictions of future hydrogeological conditions. Another objective is to assess the flow-paths from the local-scale model domain, based on the present-day flow conditions, to assess the distribution of discharge and recharge areas connected to the flow at the approximate repository depth to inform the Preliminary Safety Evaluation. Significant new features incorporated in the modelling include: a depth variation in hydraulic properties within the deformation zones; a dependence on rock domain and depth in the rock mass properties in regional-scale models; a more detailed model of the overburden in terms of a layered system of spatially variable thickness made up of several different types of Quaternary deposits has been implemented; and several variants on the position of the watertable have been tried. The motivation for introducing a dependence on rock domain was guided by the hydrogeological interpretation with the aim of honouring the observed differences in hydraulic properties measured at the boreholes.
EPA [Environmental Protection Agency] SITE [Superfund Innovative Technology Evaluation] program seeks technology proposals

International Nuclear Information System (INIS)

Anon.

1989-01-01

EPA will issue an RFP to initiate the SITE-005 solicitation for demonstration of technologies under the Superfund Innovative Technology Evaluation (SITE) Program. This portion of the SITE program offers a mechanism for conducting a joint technology demonstration between EPA and the private sector. The goal of the demonstration program is to provide an opportunity for developers to demonstrate the performance of their technologies on actual hazardous wastes at Superfund sites, and to provide accurate and reliable data on that performance. Technologies selected must be of commercial scale and provide solutions to problems encountered at Superfund Sites. Primary emphasis in the RFP is on technologies that address: treatment of mixed, low level radioactive wastes in soils and groundwater; treatment of soils and sludges contaminated with organics and/or inorganics, materials handling as a preliminary step to treatment or further processing, treatment trains designed to handle specific wastes, are in situ technologies, especially those processes providing alternatives to conventional groundwater pump and treat techniques
Preliminary evaluation of crisis-relocation fallout-shelter options. Volume 2. Detailed analysis

International Nuclear Information System (INIS)

Santini, D.J.; Clinch, J.M.; Davis, F.H.; Hill, L.G.; Lynch, E.P.; Tanzman, E.A.; Wernette, D.R.

1982-12-01

This report presents a preliminary, detailed evaluation of various shelter options for use if the President orders crisis relocation of the US urban population because of strong expectation of a nuclear war. The availability of livable shelter space at 40 ft 2 per person (congregate-care space) by state is evaluated. Options are evaluated for construction of fallout shelters allowing 10 ft 2 per person - such shelters are designed to provide 100% survival at projected levels of radioactive fallout. The FEMA concept of upgrading existing buildings to act as fallout shelters can, in principle, provide adequate shelter throughout most of the US. Exceptions are noted and remedies proposed. In terms of upgrading existing buildings to fallout shelter status, great benefits are possible by turning away from a standard national approach and adopting a more site-specific approach. Existing FEMA research provides a solid foundation for successful crisis relocation planning, but the program can be refined by making suitable modifications in its locational, engineering, and institutionally specific elements
Preliminary report on the utilization of the Fermilab site for a future accelerator

International Nuclear Information System (INIS)

1996-10-01

This report is a preliminary assessment of the utility of the Fermilab site for future accelerator projects. It responds to a request from the Director to evaluate how the Fermilab site and infrastructure may be relevant to future accelerator projects in the U.S. The SSC experience suggests that any major new project will have to be based on the existing infrastructure at one of the National Laboratories. This work presents only the technical issues and the benefits of the Fermilab site and infrastructure. The projects treated are: (1) A really large hadron collider based on the ''Pipetron'' vision of low-field (2 Tesla) magnets in a small diameter tunnel. Another option, not treated in detail, is a hadron collider using high field magnets. (2) Muon Colliders with 250 GeV and 2 TeV per beam. (3) A linear electron collider with 250 to 500 GeV per beam. The infrastructure of the state of Illinois - geology, hydrology, power and surface water- seems remarkably well suited to any of these projects. The geology of most of Illinois, including Fermilab, contains a dolomite layer that: has low seismic activity, is at an appropriate depth to provide radiation protection, is essentially impervious to water movement and thus satisfies hydrology requirements. There is adequate electrical power - both locally and statewide. We first give brief overviews of the Fermilab and Illinois infrastructure - geology, hydrology, power, and water - and then a summary of each project. On the basis of what we have learned, we feel that Fermilab must be considered seriously as a site for any of these projects. Beyond this point, however site-specific plans will need to be developed for each of the projects
Preliminary analysis of alternative fuel cycles for proliferation evaluation

Energy Technology Data Exchange (ETDEWEB)

Steindler, M. J.; Ripfel, H. C.F.; Rainey, R. H.

1977-01-01

The ERDA Division of Nuclear Research and Applications proposed 67 nuclear fuel cycles for assessment as to their nonproliferation potential. The object of the assessment was to determine which fuel cycles pose inherently low risk for nuclear weapon proliferation while retaining the major benefits of nuclear energy. This report is a preliminary analysis of these fuel cycles to develop the fuel-recycle data that will complement reactor data, environmental data, and political considerations, which must be included in the overall evaluation. This report presents the preliminary evaluations from ANL, HEDL, ORNL, and SRL and is the basis for a continuing in-depth study. (DLC)
Subsurface characterization and geohydrologic site evaluation West Chestnut Ridge site

International Nuclear Information System (INIS)

1984-01-01

The West Chestnut Ridge Site at the Oak Ridge National Laboratory is being considered for use as a repository for low-level radioactive waste. The purposes of this study were to provide a geohydrological characterization of the site for use in pathways analysis, and to provide preliminary geotechnical recommendations that would be used for development of a site utilization plan. Subsurface conditions were investigated at twenty locations and observation wells were installed. Field testing at each location included the Standard Penetration Test and permeability tests in soil and rock. A well pumping test was ocmpleted at one site. Laboratory testing included permeability, deformability, strength and compaction tests, as well as index and physical property tests. The field investigations showed that the subsurface conditions include residual soil overlying a weathered zone of dolomite which grades into relatively unweathered dolomite at depth. The thickness of residual soil is typically 80 ft (24 m) on the ridges, but can be as little as 10 ft (3 m) in the valleys. Trench excavations to depths of 30 ft (9 m) should not present serious slope stability problems above the water table. On-site soils can be used for liners or trench backfill but these soils may require moisture conditioning to achieve required densities. 19 figures, 8 tables
Hazard Ranking System evaluation of CERCLA [Comprehensive Environmental Response, Compensation, and Liability Act] inactive waste sites at Hanford: Volume 1, Evaluation methods and results

International Nuclear Information System (INIS)

Stenner, R.D.; Cramer, K.H.; Higley, K.A.; Jette, S.J.; Lamar, D.A.; McLaughlin, T.J.; Sherwood, D.R.; Van Houten, N.C.

1988-10-01

The purpose of this report is to formally document the individual site Hazard Ranking System (HRS) evaluations conducted as part of the preliminary assessment/site inspection (PA/SI) activities at the US Department of Energy (DOE) Hanford Site. These activities were carried out pursuant to the DOE orders that describe the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Program addressing the cleanup of inactive waste sites. These orders incorporate the US Environmental Protection Agency methodology, which is based on the Superfund Amendments and Reauthorization Act of 1986 (SARA). The methodology includes six parts: PA/SI, remedial investigation/feasibility study, record of decision, design and implementation of remedial action, operation and monitoring, and verification monitoring. Volume 1 of this report discusses the CERCLA inactive waste-site evaluation process, assumptions, and results of the HRS methodology employed. Volume 2 presents the data on the individual CERCLA engineered-facility sites at Hanford, as contained in the Hanford Inactive Site Surveillance (HISS) Data Base. Volume 3 presents the data on the individual CERCLA unplanned-release sites at Hanford, as contained in the HISS Data Base. 34 refs., 43 figs., 47 tabs
Hazard Ranking System evaluation of CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act) inactive waste sites at Hanford: Volume 1, Evaluation methods and results

Energy Technology Data Exchange (ETDEWEB)

Stenner, R.D.; Cramer, K.H.; Higley, K.A.; Jette, S.J.; Lamar, D.A.; McLaughlin, T.J.; Sherwood, D.R.; Van Houten, N.C.

1988-10-01

The purpose of this report is to formally document the individual site Hazard Ranking System (HRS) evaluations conducted as part of the preliminary assessment/site inspection (PA/SI) activities at the US Department of Energy (DOE) Hanford Site. These activities were carried out pursuant to the DOE orders that describe the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Program addressing the cleanup of inactive waste sites. These orders incorporate the US Environmental Protection Agency methodology, which is based on the Superfund Amendments and Reauthorization Act of 1986 (SARA). The methodology includes six parts: PA/SI, remedial investigation/feasibility study, record of decision, design and implementation of remedial action, operation and monitoring, and verification monitoring. Volume 1 of this report discusses the CERCLA inactive waste-site evaluation process, assumptions, and results of the HRS methodology employed. Volume 2 presents the data on the individual CERCLA engineered-facility sites at Hanford, as contained in the Hanford Inactive Site Surveillance (HISS) Data Base. Volume 3 presents the data on the individual CERCLA unplanned-release sites at Hanford, as contained in the HISS Data Base. 34 refs., 43 figs., 47 tabs.
Results of the preliminary radiological survey at the former Diamond Magnesium Company site, Luckey, Ohio (DML001)

International Nuclear Information System (INIS)

Foley, R.D.; Crutcher, J.W.

1990-02-01

As part of the Formerly Utilized Sites Remedial Action Program, the US Department of Energy (DOE) is implementing a radiological survey program to determine the radiological conditions at sites that were used by the department's predecessor agencies. One such site is the former Diamond Magnesium Company facility in Luckey, Ohio. The preliminary radiological survey discussed in this report was conducted at the request of DOE by members of the Measurement Applications and Development group of Oak Ridge National Laboratory in December 1988. The former Diamond Magnesium Company site in Luckey, Ohio, was used as a magnesium reduction plant during World War 2. It was closed in 1945 and reopened in 1949 as a beryllium production facility, operated by Brush Wellman for the US Atomic Energy Commission. The preliminary radiological survey included: a surface gamma scan of part of the property outdoors, collection of surface and subsurface soil samples, and collection of water samples. Laboratory analysis of soil samples showed concentrations of 226 Ra in excess of applicable DOE guidelines. A follow-up, detailed survey is recommended. 9 refs., 10 figs., 4 tabs
International workshop on site investigation and evaluation based on the siting process in Sweden

International Nuclear Information System (INIS)

Andersson, Johan; Stroem, A.

2001-06-01

the site-specific conditions for the three sites of interest. Most groups agreed that core drilling at a location within what is presumed to be a 'block of good rock' should be started as soon as possible. However, to be meaningful it is first necessary to formulate a preliminary structural model of the site such that the results of the bore hole investigations can be properly evaluated. The suite of investigation methods available to SKB and included in the SKB programme was discussed. The working groups only identified a few more site characterisation methods worth considering. Particular consideration was recommended for 3D seismic surveying and long directional drilling. Most groups pointed out the need for SKB to establish sufficient structure, in terms of decision-making and project management organisation, to enable prioritisation of programme objectives, clear demarcation of programme responsibilities and the positive identification of intermediate programme goals. Several groups suggested quite similar organisations with different teams at each site but combined with a rather strong central evaluation function. The need for integrating Safety Assessment, Design and Site Investigation was stressed. SKB is presently in the process of changing the organisation to meet the demands of site characterisation work. Finally, the timing was excellent for having our reports reviewed by a group of international experts and to get comments and proposals at different levels. The summary of the workshop as presented in this report will be essential for the continued planning work

Evaluation of the state of stress at the Forsmark site. Preliminary site investigation Forsmark area - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Sjoeberg, Jonny; Lindfors, Ulf; Perman, Fredrik; Ask, Daniel [SwedPower AB, Stockholm (Sweden)

2005-09-15

This report presents an evaluation of the state of stress at the Forsmark site, based on all conducted stress measurements to date at the site, indirect stress estimates, geological and tectonic description of the site, and regional stress data from nearby locations. The work included (i) compilation of measurement results from Forsmark, as well as from nearby (regional) sites/locations, (ii) analysis of confidence intervals for each group of measurement, (iii) assessment of the stress state for the Forsmark site accounting for geological/tectonic evolution at the site, (iv) assessment of stress state for selected nearby (regional) sites/locations, and (v) comparison and combined interpretation of similarities and/or differences in stress state from a regional perspective. The combined assessment of the local (site-scale) and regional stress data for Forsmark showed that the major stress is orientated sub-horizontally and trending NW-SE; however, with significant local variation. A thrust faulting ({sigma}H > {sigma}h > {sigma}v) or possibly strike-slip faulting ({sigma}H > {sigma}v > {sigma}h) stress regime is evident at the Forsmark site. The maximum horizontal stress tends to be higher at the site compared to nearby sites and regional conditions. The site and regional data indicate that the vertical stress seems to be solely due to the overburden pressure. The lack of solid core discing for large portions of the boreholes at Forsmark was used to estimate an upper limit of the maximum horizontal stress magnitude. However, such an estimation is highly uncertain due to e.g. partly unknown mechanism for core discing failure, and unknown effects of the simplifying assumptions made in the analysis. The possible effects of shallow-dipping deformation zones on the stress state, could not be verified from the currently available data. However, the possibility of different stress regimes above and below deformation zones must be considered in future work. Slightly lower
Evaluation of the state of stress at the Forsmark site. Preliminary site investigation Forsmark area - version 1.2

International Nuclear Information System (INIS)

Sjoeberg, Jonny; Lindfors, Ulf; Perman, Fredrik; Ask, Daniel

2005-09-01

This report presents an evaluation of the state of stress at the Forsmark site, based on all conducted stress measurements to date at the site, indirect stress estimates, geological and tectonic description of the site, and regional stress data from nearby locations. The work included (i) compilation of measurement results from Forsmark, as well as from nearby (regional) sites/locations, (ii) analysis of confidence intervals for each group of measurement, (iii) assessment of the stress state for the Forsmark site accounting for geological/tectonic evolution at the site, (iv) assessment of stress state for selected nearby (regional) sites/locations, and (v) comparison and combined interpretation of similarities and/or differences in stress state from a regional perspective. The combined assessment of the local (site-scale) and regional stress data for Forsmark showed that the major stress is orientated sub-horizontally and trending NW-SE; however, with significant local variation. A thrust faulting (σH > σh > σv) or possibly strike-slip faulting (σH > σv > σh) stress regime is evident at the Forsmark site. The maximum horizontal stress tends to be higher at the site compared to nearby sites and regional conditions. The site and regional data indicate that the vertical stress seems to be solely due to the overburden pressure. The lack of solid core discing for large portions of the boreholes at Forsmark was used to estimate an upper limit of the maximum horizontal stress magnitude. However, such an estimation is highly uncertain due to e.g. partly unknown mechanism for core discing failure, and unknown effects of the simplifying assumptions made in the analysis. The possible effects of shallow-dipping deformation zones on the stress state, could not be verified from the currently available data. However, the possibility of different stress regimes above and below deformation zones must be considered in future work. Slightly lower horizontal stress was found in
Site study plan for cultural resources, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

The Cultural Resources Site Study Plan describes a field program to identify and evaluate the archaeological, historical, and Native American Indian resources of the site on local and regional perspectives; monitor and manage discovered cultural resources; and establish a worker education program. The archaeological field program consists of three pedestrian surveys: Survey 1 includes two EDBH seismic survey lines and the area within the exploratory shaft facility (ESF); Survey 2 includes the remainder of the site plus a 1/4 to 3/4-mi border area; and Survey 3 includes an assortment of offsite areas. The historical studies will identify and evaluate known and discovered historical sites and structures and the Native American Indian will identify and evaluate cultural and religious concerns expressed by Indian tribal groups. Prehistoric and historic sites will be evaluated to determine if they meet eligibility criteria for listing on the National Register of Historic Places. This site study plan describes the need for each study; its design and design rationale; analysis, management, and use of data; schedule of field activities; organization of field personnel and sample management; and quality assurance requirements. The cultural resource studies will provide data for satisfying the Programmatic Agreement, engineering design needs, and SRP requirements for permits and approvals, and for minimizing effects to any cultural properties discovered during site characterization. 75 refs., 10 figs., 2 tabs
Preliminary evaluation of crisis-relocation fallout-shelter options. Volume 2. Detailed analysis

Energy Technology Data Exchange (ETDEWEB)

Santini, D.J.; Clinch, J.M.; Davis, F.H.; Hill, L.G.; Lynch, E.P.; Tanzman, E.A.; Wernette, D.R.

1982-12-01

This report presents a preliminary, detailed evaluation of various shelter options for use if the President orders crisis relocation of the US urban population because of strong expectation of a nuclear war. The availability of livable shelter space at 40 ft/sup 2/ per person (congregate-care space) by state is evaluated. Options are evaluated for construction of fallout shelters allowing 10 ft/sup 2/ per person - such shelters are designed to provide 100% survival at projected levels of radioactive fallout. The FEMA concept of upgrading existing buildings to act as fallout shelters can, in principle, provide adequate shelter throughout most of the US. Exceptions are noted and remedies proposed. In terms of upgrading existing buildings to fallout shelter status, great benefits are possible by turning away from a standard national approach and adopting a more site-specific approach. Existing FEMA research provides a solid foundation for successful crisis relocation planning, but the program can be refined by making suitable modifications in its locational, engineering, and institutionally specific elements.
Preliminary Hydrogeochemical Site Description SFR (version 0.2)

Energy Technology Data Exchange (ETDEWEB)

Nilsson, Ann-Chatrin (Geosigma AB, Uppaala (Sweden)); Tullborg, Eva-Lena (Terralogica AB, Graabo (Sweden)); Smellie, John (Conterra AB, Partille (Sweden))

2010-05-15

The final repository for low and intermediate level radioactive operational waste, SFR, located about 150 km north of Stockholm, is to undergo a future extension. The present on-going project, scheduled from 2007 to 2011, is to define and characterise a suitable bedrock volume for the extended repository. This will include the drilling and geoscientific evaluation of seven core-drilled and four percussion boreholes as well as subsequent interpretation and modelling based on the obtained results in order to provide the necessary information for safety assessment and repository design. This report presents a preliminary hydrogeochemical site description for the SFR site and should be considered as an early progress report rather than a complete hydrochemical site descriptive model. The completed hydrogeochemical field investigations have yielded chemical data from a total of 12 borehole sections in five boreholes and additional data from the entire length of two open boreholes in connection with hydraulic tests. These data, together with data from a total of 18 early boreholes in the present SFR tunnel system, were used in the interpretation work. The main part of the data consisted of basic groundwater analyses including major ions and isotopes. Some sporadic gas, microbe and measured redox data are available, but these are either not treated in this report, or are only briefly discussed. This was due to time constraints since special care is needed when interpreting few data of varying quality. The groundwaters in the SFR dataset cover a maximum depth down to about .400 masl and represent a relatively limited salinity range (1,500 to 5,500 mg/L chloride). However, the delta18O values show a wide variation (-1.55 to -0.75% V-SMOW) similar to that reported from the Forsmark site investigations. At the SFR, marine indicators such as Mg/Cl, K/Cl and Br/Cl also show relatively large variations considering the limited salinity range. From very few measured Eh values, and
Preliminary Hydrogeochemical Site Description SFR (version 0.2)

International Nuclear Information System (INIS)

Nilsson, Ann-Chatrin; Tullborg, Eva-Lena; Smellie, John

2010-05-01

The final repository for low and intermediate level radioactive operational waste, SFR, located about 150 km north of Stockholm, is to undergo a future extension. The present on-going project, scheduled from 2007 to 2011, is to define and characterise a suitable bedrock volume for the extended repository. This will include the drilling and geoscientific evaluation of seven core-drilled and four percussion boreholes as well as subsequent interpretation and modelling based on the obtained results in order to provide the necessary information for safety assessment and repository design. This report presents a preliminary hydrogeochemical site description for the SFR site and should be considered as an early progress report rather than a complete hydrochemical site descriptive model. The completed hydrogeochemical field investigations have yielded chemical data from a total of 12 borehole sections in five boreholes and additional data from the entire length of two open boreholes in connection with hydraulic tests. These data, together with data from a total of 18 early boreholes in the present SFR tunnel system, were used in the interpretation work. The main part of the data consisted of basic groundwater analyses including major ions and isotopes. Some sporadic gas, microbe and measured redox data are available, but these are either not treated in this report, or are only briefly discussed. This was due to time constraints since special care is needed when interpreting few data of varying quality. The groundwaters in the SFR dataset cover a maximum depth down to about .400 masl and represent a relatively limited salinity range (1,500 to 5,500 mg/L chloride). However, the δ 18 O values show a wide variation (-1.55 to -0.75% V-SMOW) similar to that reported from the Forsmark site investigations. At the SFR, marine indicators such as Mg/Cl, K/Cl and Br/Cl also show relatively large variations considering the limited salinity range. From very few measured Eh values, and
A preliminary analysis of the risk of transporting nuclear waste to potential candidate commercial repository sites

International Nuclear Information System (INIS)

Madsen, M.M.

1984-01-01

In accordance with the provisions of the Nuclear Waste Policy Act of 1982, environmental assessments for potential candidate sites are required to provide a basis for selection of the first site for disposal of commercial radioactive waste in deep geologic repositories. A preliminary analysis of the impacts of transportation for each of the five potential sites will be described. Transportation was assumed to be entirely by truck or entirely by rail in order to obtain bounding impacts. This paper presents both radiological and nonradiological risks for the once-through fuel cycle
Preliminary rail access study

International Nuclear Information System (INIS)

1990-01-01

The Yucca Mountain site, located on the southwestern edge of the Nevada Test Site, is an undeveloped area under investigation as a potential site for nuclear waste disposal by the US Department of Energy. The site currently lacks rail service and an existing rail right-of-way. If the site is suitable and selected for development as a disposal site, rail service is desirable to the Office of Civilian Radioactive Waste Management Program because of the potential of rail to reduce number of shipments and costs relative to highway transportation. This preliminary report is a summary of progress to date for activities to identify and evaluate potential rail options from major rail carriers in the region to the Yucca Mountain site. It is currently anticipated that the rail spur will be operational after the year 2000. 9 refs., 13 figs., 2 tabs
Canada's Deep Geological Repository for Used Nuclear Fuel - Geo-scientific Site Evaluation Process - 13117

Energy Technology Data Exchange (ETDEWEB)

Blyth, Alec; Ben Belfadhel, Mahrez; Hirschorn, Sarah; Hamilton, Duncan; McKelvie, Jennifer [Nuclear Waste Management Organization, 22 St. Clair Avenue East, Toronto, Ontario M4T 2S3 (Canada)

2013-07-01

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable rock formation at a depth of approximately 500 meters (m) (1,640 feet [ft]). In May 2010, the NWMO published a nine-step site selection process that serves as the road map to decision-making on the location for the deep geological repository. The safety and appropriateness of any potential site will be assessed against a number of factors, both technical and social in nature. The selected site will be one that can be demonstrated to be able to safely contain and isolate used nuclear fuel, protecting humans and the environment over the very long term. The geo-scientific suitability of potential candidate sites will be assessed in a stepwise manner following a progressive and thorough site evaluation process that addresses a series of geo-scientific factors revolving around five safety functions. The geo-scientific site evaluation process includes: Initial Screenings; Preliminary Assessments; and Detailed Site Evaluations. As of November 2012, 22 communities have entered the site selection process (three in northern Saskatchewan and 18 in northwestern and southwestern Ontario). (authors)
SSC [Superconducting Super Collider] site evaluations

International Nuclear Information System (INIS)

1988-11-01

With this report, the SSC Site Task Force forwards to the Director, Office of Energy Research, US Department of Energy (DOE), its evaluation of the technical criteria and life-cycle costs for the proposed SSC sites judged to be the best qualified. The criteria against which each site was evaluated are those set forth in the Invitation for Site Proposals for the Superconducting Super Collider (DOE/ER-0315) (Invitation) which was prepared by the Task Force and issued in April 1987. The methodology followed by the Task Force in this report and in all other phases of the proposal evaluation has been consistent with the SSC site selection process approved by DOE's Energy System Acquisition Advisory Board (ESAAB). The goal of the site selection process is to identify a site that will permit the highest level of research productivity and overall effectiveness of the SSC at a reasonable cost of construction and operation and with minimial impact on the environment. The Task Force acknowledges that all seven sites are, indeed, highly qualified locations for the construction and operation of the SSC on the basis of technical and cost considerations. In performing its evaluation, which is presented in this paper, the Task Force took an in-depth look at each site on the basis of site visits and extensive technical analyses. A consensus rating for each technical evaluation criterion and subcriterion was developed for each site
Preliminary results of the evaluation of the Wind power resource in several sites of the state of Zacatecas; Resultados preliminares de la evaluacion del recurso eolico en varios sitios del estado de Zacatecas

Energy Technology Data Exchange (ETDEWEB)

Reta, Manuel; Soto, Cristian; De la Torre, Jorge; Ibarra, Salvador; Alvarez, Jose; Romo, Guillermo; Banuelos, Francisco; Ochoa, Carlos; Martinez, Antonio; Aguilar, Efrain; Medina Garcia, G; Rumayor R, A.F. (Mexico)

2009-07-15

The present article shows the preliminary results of the analysis of wind power monitoring of fifteen agro-climatic stations 3 m high, of Instituto Nacional de Investigationes Forestales, Agricolas y Pecuarias of Zacatecas state. The preliminary analysis of the available data of wind velocity allows to extrapolate values at 10 m and 30 m of high in each one of the measured sites, and to evaluate the Wind potential, in W/m{sup 2}, at 30 m high. These results will allow selecting the best sites for the collection of wind power generators of medium and low scale for the possible development of wind farms in rural zones not connected to the national power network. [Spanish] El presente articulo muestra los resultados preliminares del analisis de monitoreo eolico de quince estaciones agroclimaticas a 3 m de altura, del Instituto Nacional de Investigaciones Forestales Agricolas y Pecuarias (INIFAP), distribuidas en el estado de Zacatecas. El analisis preliminar de los datos disponibles de velocidad de viento permite extrapolar valores a 10 m y 30 m de altura en cada uno de los sitios medidos, y a evaluar el potencial eolico, en W/m{sup 2}, a 30 m de altura. Estos resultados permitiran seleccionar los mejores sitios para la coleccion de aerogeneradores de mediana y baja escala para el posible desarrollo de granjas eolicas en zonas rurales desconectadas de la red electrica nacional.
Site description of Forsmark at completion of the site investigation phase. SDM-Site Forsmark

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

north-western part of the candidate area lacks hydraulically conductive, gently dipping fracture zones at potential repository depth and was selected as the target area for the complete site investigation work, following the initial investigations at the site. Prior to the presentation of the SDM-Site report, three versions of a site descriptive model have been completed for the Forsmark area and presented for peer review. The last version, referred to as version 1.2, was a preliminary site description that concluded the initial site investigation work and was presented in 2005. This preliminary site description formed the basis for a preliminary safety evaluation (PSE) of the Forsmark area, a preliminary repository layout (step D1), and the first evaluation of the long-term safety of this layout for KBS-3 repositories in the context of the SR-Can project. The final site descriptive model, SDM-Site, builds on a coordinated geological model in 3D, into which other discipline-specific models have been integrated without any major conflicting interpretations. In particular, the thermal properties of the bedrock at the site have been coupled to identified rock domains in the geological model and an integrated model that links the current stress regime, the hydrogeology and the chemistry of the groundwater to fracture domains and fracture zones in the geological model has evolved. These mutually consistent results demonstrate that a fundamental understanding of the current state of conditions and the on-going processes in the Forsmark area, from the surface down to potential repository depth, has been achieved. In addition, the properties of the area can be explained in the context of an understanding of the past evolution, throughout a long period of geological history. This integrated understanding of the area is presented in chapter 11 of this report and this chapter serves as an executive summary. A systematic assessment of the confidence in the model, including
Site description of Laxemar at completion of the site investigation phase. SDM-Site Laxemar

Energy Technology Data Exchange (ETDEWEB)

2009-12-15

the waning stages of the Svecokarelian orogeny. The candidate area is circular-shaped with an area of 54 km2, and hosts the Laxemar subarea in its eastern part. The south-western part of the Laxemar subarea was selected as the focused area for the complete site investigation work, following the initial investigations at the site. Prior to the presentation of the SDM-Site report, three versions of a site descriptive model have been completed for the Laxemar-Simpevarp area and subjected to peer review. The last version, referred to as version Laxemar 1.2, constituted a preliminary site description that concluded the initial site investigation work and was presented in 2006. This preliminary site description formed the basis for a preliminary safety evaluation (PSE) of the Laxemar subarea, a preliminary repository layout, and the first evaluation of the long-term safety of this layout for a KBS-3 repository in the context of the SR-Can project. The final site descriptive model, SDM-Site Laxemar, builds on a coordinated geological model in 3D, into which other discipline-specific models have been integrated without any major conflicting interpretations. In particular, the bedrock thermal and strength properties of the bedrock at the site have been coupled to lithology and identified rock domains in the geological model and an integrated description has been devised that links the hydrogeology and the chemistry of the groundwater to hydraulic conductor domains (deformation zones) and hydraulic rock domains (and underlying fracture domains) and their division in depth zones. These mutually consistent results demonstrate that a fundamental understanding of the current state, properties and processes in Laxemar, from the surface down to potential repository depth, has been achieved. In addition, the properties of the area can be explained in the context of an understanding of its past evolution, throughout a long period of geological history. This integrated understanding of
Site description of Laxemar at completion of the site investigation phase. SDM-Site Laxemar

International Nuclear Information System (INIS)

2009-12-01

the waning stages of the Svecokarelian orogeny. The candidate area is circular-shaped with an area of 54 km 2 , and hosts the Laxemar subarea in its eastern part. The south-western part of the Laxemar subarea was selected as the focused area for the complete site investigation work, following the initial investigations at the site. Prior to the presentation of the SDM-Site report, three versions of a site descriptive model have been completed for the Laxemar-Simpevarp area and subjected to peer review. The last version, referred to as version Laxemar 1.2, constituted a preliminary site description that concluded the initial site investigation work and was presented in 2006. This preliminary site description formed the basis for a preliminary safety evaluation (PSE) of the Laxemar subarea, a preliminary repository layout, and the first evaluation of the long-term safety of this layout for a KBS-3 repository in the context of the SR-Can project. The final site descriptive model, SDM-Site Laxemar, builds on a coordinated geological model in 3D, into which other discipline-specific models have been integrated without any major conflicting interpretations. In particular, the bedrock thermal and strength properties of the bedrock at the site have been coupled to lithology and identified rock domains in the geological model and an integrated description has been devised that links the hydrogeology and the chemistry of the groundwater to hydraulic conductor domains (deformation zones) and hydraulic rock domains (and underlying fracture domains) and their division in depth zones. These mutually consistent results demonstrate that a fundamental understanding of the current state, properties and processes in Laxemar, from the surface down to potential repository depth, has been achieved. In addition, the properties of the area can be explained in the context of an understanding of its past evolution, throughout a long period of geological history. This integrated understanding
Site description of Forsmark at completion of the site investigation phase. SDM-Site Forsmark

International Nuclear Information System (INIS)

2008-12-01

north-western part of the candidate area lacks hydraulically conductive, gently dipping fracture zones at potential repository depth and was selected as the target area for the complete site investigation work, following the initial investigations at the site. Prior to the presentation of the SDM-Site report, three versions of a site descriptive model have been completed for the Forsmark area and presented for peer review. The last version, referred to as version 1.2, was a preliminary site description that concluded the initial site investigation work and was presented in 2005. This preliminary site description formed the basis for a preliminary safety evaluation (PSE) of the Forsmark area, a preliminary repository layout (step D1), and the first evaluation of the long-term safety of this layout for KBS-3 repositories in the context of the SR-Can project. The final site descriptive model, SDM-Site, builds on a coordinated geological model in 3D, into which other discipline-specific models have been integrated without any major conflicting interpretations. In particular, the thermal properties of the bedrock at the site have been coupled to identified rock domains in the geological model and an integrated model that links the current stress regime, the hydrogeology and the chemistry of the groundwater to fracture domains and fracture zones in the geological model has evolved. These mutually consistent results demonstrate that a fundamental understanding of the current state of conditions and the on-going processes in the Forsmark area, from the surface down to potential repository depth, has been achieved. In addition, the properties of the area can be explained in the context of an understanding of the past evolution, throughout a long period of geological history. This integrated understanding of the area is presented in chapter 11 of this report and this chapter serves as an executive summary. A systematic assessment of the confidence in the model, including
Preliminary safety evaluation for the plutonium stabilization and packaging system

International Nuclear Information System (INIS)

Shapley, J.E.

1997-01-01

This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS
Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

International Nuclear Information System (INIS)

Conner, J.C.

1994-01-01

This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue
Criteria for the development and use of the methodology for environmentally-acceptable fossil energy site evaluation and selection. Volume 2. Final report

Energy Technology Data Exchange (ETDEWEB)

Eckstein, L.; Northrop, G.; Scott, R.

1980-02-01

This report serves as a companion document to the report, Volume 1: Environmentally-Acceptable Fossil Energy Site Evaluation and Selection: Methodology and Users Guide, in which a methodology was developed which allows the siting of fossil fuel conversion facilities in areas with the least environmental impact. The methodology, known as SELECS (Site Evaluation for Energy Conversion Systems) does not replace a site specific environmental assessment, or an environmental impact statement (EIS), but does enhance the value of an EIS by thinning down the number of options to a manageable level, by doing this in an objective, open and selective manner, and by providing preliminary assessment and procedures which can be utilized during the research and writing of the actual impact statement.
Site study plan for Transportation, Deaf Smith County Site, Texas: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

This site study plan describes transportation field studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. The studies are needed to identify and assess potential project impacts to transportation infrastructure and systems in the project vicinity and along potential transportation routes to the site across the State of Texas. The studies are also needed to locate and design project transportation facilities, and to evaluate and design impact mitigation. After identifying the transportation information requirements needed to comply with Federal, State, and local regulations and repository program requirements, the site study plan describes the study design and rationale, the field data collection procedures and equipment, the data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs for the characterization of site vicinity rail corridors and highway corridors, characterization of alternative statewide transportation routes, monitoring of site characterization effects on transportation, characterization of aircraft overflight patterns and hazardous material transportation patterns, and assessment of emergency response preparedness along alternative statewide transportation routes. 34 refs., 10 figs., 2 tabs
Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

Energy Technology Data Exchange (ETDEWEB)

Waters, R.D.; Gruebel, M.M. [eds.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site
Preliminary recommendations on the design of the characterization program for the Hanford Site single-shell tanks: A system analysis

International Nuclear Information System (INIS)

Buck, J.W.; Peffers, M.S.; Hwang, S.T.

1991-11-01

The work described in this volume was conducted by Pacific Northwest Laboratory to provide preliminary recommendations on data quality objectives (DQOs) to support the Waste Characterization Plan (WCP) and closure decisions for the Hanford Site single-shell tanks (SSTs). The WCP describes the first of a two-phase characterization program that will obtain information to assess and implement disposal options for SSTs. This work was performed for the Westinghouse Hanford Company (WHC), the current operating contractor on the Hanford Site. The preliminary DQOs contained in this volume deal with the analysis of SST wastes in support of the WCP and final closure decisions. These DQOs include information on significant contributors and detection limit goals (DLGs) for SST analytes based on public health risk
Preliminary results from comparisons of redundant tiltmeters at three sites in central california

Science.gov (United States)

Mortensen, C.E.; Johnston, M.J.S.

1979-01-01

The U.S. Geological Survey has been operating a network of shallow-borehole tiltmeters in central California since June 1973. At six sites redundant instruments have been installed as a check on data coherency. These include the Sage Ranch, Tres Pinos, New Idria, Aromas, Bear Valley and San Juan Bautista tiltmeter sites. Preliminary results from the comparison of redundant data from the Aromas, Bear Valley and San Juan Bautista sites for periods of eight, three and seven months respectively, suggest that short period tilt signals in the range 5 min < T < 3-5 h and ranging in amplitude from 5 ?? 10-8 to 10-6 rad, but not including step offsets, show excellent agreement on closely spaced instruments. Agreement is not as good in this period range for instruments at San Juan Bautista with a separation of 200 m. Signals of interest observed in this period range include coseismic tilts, teleseisms and tilts associated with creep events. Tilt signals in the period range 3-5 h < T < 2- 5 weeks are not always coherent at all three of the redundant tilt sites studied. Tilt signals in this period range have amplitudes up to 5 ?? 10-6 rad and wavelengths down to at least the instrument separation at the closely spaced sites (~several meters). Regarding longerterm coherency, the instruments at San Juan Bautista with 200-m spacing, agree within 0.5 ??rad for the N-S component and 0.7 jurad for the E-W component for a period of two months. The closely spaced redundant instruments at Aromas agree within 2 ??rad for the N-S component and 1 ??rad for the E-W component for the eight-month period of operation. Data from the three sites have been checked for effects of temperature, atmospheric pressure and rainfall. The latter appears to be critically site dependent. The worst case tilts for 1 inch of rainfall can be more than 1 jurad with a duration of a few days to a week. Typical rain-induced tilts are less than 0.3 ??rad for 1 inch of rain. The two instruments at the Sage Ranch
Ecological and radioecological studies of nuclear installation sites

International Nuclear Information System (INIS)

Caries, J. C.; Hugon, J.; Grauby, A.

1988-01-01

The site study method consists of a dynamic and estimated analysis and of following up the release impact on all natural or non natural media compartments that take a part in the protection of man and his environment. The stages of knowing a nuclear site include the site preliminary radioecological evaluation, diffusion parameters evaluation, the quantification of factors of radioelements transfer to man, the ecological baseline carrying out, the radioactive baseline establishment, the radioecological synthesis of the results, the site radioactive and ecological control. This method applys to selection and detailed study of site. 1 tab., 7 refs. (F.M.)
Preliminary siting characterization Salt Disposition Facility - Site B

International Nuclear Information System (INIS)

Wyatt, D.

2000-01-01

A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ''Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data
Regional hydrogeological simulations for Forsmark - numerical modelling using CONNECTFLOW. Preliminary site description Forsmark area - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Hartley, Lee; Cox, Ian; Hunter, Fiona; Jackson, Peter; Joyce, Steve; Swift, Ben [Serco Assurance, Risley (United Kingdom); Gylling, Bjoern; Marsic, Niko [Kemakta Konsult AB, Stockholm (Sweden)

2005-05-01

objective of this study is to assess the role of known and unknown hydrogeological conditions for the present-day distribution of saline groundwater in the Forsmark area on a regional scale. An improved understanding of the palaeo-hydrogeology is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. The latter will serve as a basis for describing the present-day hydrogeological conditions on a local scale as well as predictions of future hydrogeological conditions. Finally, this study aims to identify some of the issues that may impact the SR-Can Performance Safety Assessment (PSA) project, and where possible provide a preliminary evaluation of sensitivities to such issues. In particular, recommendations are made as to which uncertainties need to be addressed as part of SR-Can. The numerical modelling was performed by two separate modelling teams. The work presented in this report was conducted by The CONNECTFLOW Team involving modelling experts from Serco Assurance, Kemakta Konsult and Golder Associates.
Evaluation of the on-site immunoassay drug-screening device Triage-TOX in routine forensic autopsy.

Science.gov (United States)

Tominaga, Mariko; Michiue, Tomomi; Maeda, Hitoshi

2015-11-01

Instrumental identification of drugs with quantification is essential in forensic toxicology, while on-site immunoassay urinalysis drug-screening devices conveniently provide preliminary information when adequately used. However, suitable or sufficient urine specimens are not always available. The present study evaluated the efficacy of a new on-site immunoassay drug-screening device Triage-TOX (Alere Inc., San Diego, CA, USA), which has recently been developed to provide objective data on the one-step automated processor, using 51 urine and 19 pericardial fluid samples from 66 forensic autopsy cases, compared with Triage-Drug of Abuse (DOA) and Monitect-9. For benzodiazepines, the positive predictive value and specificity of Triage-TOX were higher than those of Triage-DOA; however, sensitivity was higher with Monitect-9, despite frequent false-positives. The results for the other drugs with the three devices also included a few false-negatives and false-positives. These observations indicate the applicability of Triage-TOX in preliminary drug screening using urine or alternative materials in routine forensic autopsy, when a possible false-negative is considered, especially for benzodiazepines, providing objective information; however, the combined use of another device such as Monitect-9 can help minimize misinterpretation prior to instrumental analysis. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.
Site evaluation for nuclear installations. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site
Nuclear power plant site evaluation using site population-meterology factor

International Nuclear Information System (INIS)

Rho, B.H.; Kang, C.H.

1982-01-01

In this paper, as a site evaluation technique, SPNF(Site Population Neteorology Factor) which is modified from SPF(Site Population Factor) of the USNRC model, is defined from site population and meteorology data in order to consider the radiological impacts to the population at large from the atmospheric dispersion of the radioactive effluents released during routine plant operation as well as accidental conditions. The SPMF model proved its propriety from the comparison of SPMF and SPF for Kori site. The relative suitability of Korean sites to the U.S. sites have been also examined using SPF. (Author)
Preliminary constitutive properties for salt and nonsalt rocks from four potential repository sites

International Nuclear Information System (INIS)

Pfeifle, T.W.; Mellegard, K.D.; Senseny, P.E.

1983-07-01

Results are presented from laboratory strength and creep tests performed on salt and nonsalt specimens from the Richton Dome in Mississippi, the Vacherie Dome in Louisiana, the Permian Basin in Texas, and the Paradox Basin in Utah. The constititive properties obtained for salt are the elastic moduli and the failure envelope at 24 0 C and parameter values for the exponential-time creep law. Some additional data are presented to indicate how the elastic moduli and strength change with temperature. The nonsalt constitutive properties reported are the elastic moduli, the unconfined compressive strength and the tensile strength at 24 0 C. The properties given in this report will be used in subsequent numerical simulations that will provide information to assist in the screening and selection of site locations for a nuclear waste repository and to assist in the repository design at the selected site. The matrix of tests performed is the minimum effort required to obtain these constitutive properties. The preliminary values obtained will be supplemented by additional testing for sites that are selected for further investigation
Preliminary site description Forsmark area - version 1.1

International Nuclear Information System (INIS)

2004-03-01

This report presents the interim version (model version 1.1) of the preliminary Site Descriptive Model for Forsmark. The basis for this interim version is quality-assured, geoscientific and ecological field data from Forsmark that were available in the SKB databases SICADA and GIS at April 30, 2003 as well as version 0 of the Site Descriptive Model. The new data acquired during the initial site investigation phase to the date of data freeze 1.1 constitute the basis for the updating of version 0 to version 1.1. These data originate from surface investigations on the candidate area with its regional environment and from drilling and investigations in boreholes. The surface-based data sets were rather extensive whereas the data sets from boreholes were limited to information from one 1,000 m deep cored borehole (KFM01A) and eight 150 to 200 m deep percussion-drilled boreholes in the Forsmark candidate area. Discipline specific models are developed for a selected regional and local model volume and these are then integrated into a site description. The current methodologies for developing the discipline specific models and the integration of these are documented in methodology reports or strategy reports. In the present work, the guidelines given in those reports were followed to the extent possible with the data and information available at the time for data freeze for model version 1.1. Compared with version 0 there are considerable additional features in the version 1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and much higher resolution surface data. The existence of highly fractured sub-horizontal zones has been verified and these are now part of the model of the deformation zones. A discrete fracture network (DFN) model has also been developed. The rock mechanics model is based on strength information from SFR and an empirical
Hydrogeochemical evaluation for Simpevarp model version 1.2. Preliminary site description of the Simpevarp area

International Nuclear Information System (INIS)

Laaksoharju, Marcus

2004-12-01

Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Simpevarp groundwater analytical data collected up to April, 2004. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1.7 km. Model version 1.2 focusses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1000 m depth. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1000 m depending on local topography. The marked differences in the groundwater flow regimes between Laxemar and Simpevarp are reflected in the groundwater chemistry where four major hydrochemical groups of groundwaters (types A-D) have been identified: TYPE A: This type comprises dilute groundwaters ( 3 type present at shallow ( 300 m) levels at Simpevarp, and at even greater depths (approx. 1200 m) at Laxemar. At Simpevarp the groundwaters are mainly Na-Ca-Cl with increasingly enhanced Br and SO 4 with depth. At Laxemar they are mainly Ca-Na-Cl also with increasing enhancements of Br and SO 4 with depth. Main reactions involve ion exchange (Ca). At both sites a glacial component and a deep saline component are present. At Simpevarp the saline component may be potentially non marine and/or non-marine/old Littorina marine in origin; at Laxemar it is more likely to be non-marine in origin. TYPE D: This type comprises reducing highly saline groundwaters (> 20 000 mg/L Cl; to a maximum of ∼70 g/L TDS) and only has been identified at Laxemar at depths exceeding 1200 m. It is mainly Ca-Na-Cl with higher Br but lower SO 4 compared
A Preliminary Assessment of Daily Weather Conditions in Nuclear Site for Development of Effective Emergency Plan

International Nuclear Information System (INIS)

Han, Seok Jung; Ahn, Kwang Il

2012-01-01

A radiological emergency preparedness for nuclear sites is recognized as an important measure against anticipated severe accidents with environmental releases of radioactive materials. While there are many individual means in the emergency preparedness for nuclear accidents, one of most important means is to make a decision of evacuation or shelter of the public residents with the emergency plan zone (EPZ) of a nuclear site. In order to prepare an effective strategy for the evacuation as a basis of the emergency preparedness, it may need the understanding of atmospheric dispersion characteristics of radiation releases to the environment, mainly depending upon the weather conditions of a radiation releases location, i.e., a nuclear site. As a preliminary study for the development of an effective emergency plan, the basic features of the weather conditions of a specific site were investigated. A main interest of this study is to identify whether or not the site weather conditions have specific features helpful for a decision making of evacuation of the public residents
Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

1992-01-01

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``
Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C.; Ballou, L.B.; Revelli, M.A.; Ducharme, A.R.; Shephard, L.E.; Dudley, W.W.; Hoxie, D.T.; Herbst, R.J.; Patera, E.A.; Judd, B.R.; Docka, J.A.; Rickertsen, L.D.

1992-01-01

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE's Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ''current information'' or ''available evidence.''
Summary report of the experiences from TVO's site investigations

International Nuclear Information System (INIS)

Oehberg, A.; Saksa, P.; Ahokas, H.; Ruotsalainen, P.; Snellman, M.

1994-09-01

In 1992 Teollisuuden Voima Oy (TVO) completed preliminary site investigations for radioactive waste disposal at five sites in Finland. The aim of this report was the compilation of the experiences from TVO's site investigations. The main interest was focused on investigation strategies and the most important investigation methods for the conceptual modelling. The objective of the preliminary site investigations was to obtain data on the bedrock properties in order to evaluate the areas. The programme was divided into four stages, each stage having its own subobjective. The site-specific investigation programme for each site included a large common part and a small site-specific part. The strategies (objectives) and experiences from different disciplines, geology, hydrogeochemistry, geophysics and geohydrology, are presented in the report. The conceptual modelling work procedure including both bedrock and groundwater modelling is described briefly using the Olkiluoto site as an example. Each of the other areas has undergone similar phases of work. (52 refs., 45 figs., 5 tabs.)
Preliminary post-closure safety assessment of repository concepts for low level radioactive waste at the Bruce Site, Ontario

International Nuclear Information System (INIS)

Little, R.H.; Penfold, J.S.S.; Egan, M.J.; Leung, H.

2005-01-01

The preliminary post-closure safety assessment of permanent repository concepts for low-level radioactive waste (LLW) at the Ontario Power Generation (OPG) Bruce Site is described. The study considered the disposal of both short and long-lived LLW. Four geotechnically feasible repository concepts were considered (two near-surface and two deep repositories). An approach consistent with best international practice was used to provide a reasoned and comprehensive analysis of post-closure impacts of the repository concepts. The results demonstrated that the deep repository concepts in shale and in limestone, and the surface repository concept on sand should meet radiological protection criteria. For the surface repository concept on glacial till, it appears that increased engineering such as grouting of waste and voids should be considered to meet the relevant dose constraint. Should the project to develop a permanent repository for LLW proceed, it is expected that this preliminary safety assessment would need to be updated to take account of future site-specific investigations and design updates. (author)
Evaluation of chemical sensors for in situ ground-water monitoring at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Murphy, E.M.; Hostetler, D.D.

1989-03-01

This report documents a preliminary review and evaluation of instrument systems and sensors that may be used to detect ground-water contaminants in situ at the Hanford Site. Three topics are covered in this report: (1) identification of a group of priority contaminants at Hanford that could be monitored in situ, (2) a review of current instrument systems and sensors for environmental monitoring, and (3) an evaluation of instrument systems that could be used to monitor Hanford contaminants. Thirteen priority contaminants were identified in Hanford ground water, including carbon tetrachloride and six related chlorinated hydrocarbons, cyanide, methyl ethyl ketone, chromium (VI), fluoride, nitrate, and uranium. Based on transduction principles, chemical sensors were divided into four classes, ten specific types of instrument systems were considered: fluorescence spectroscopy, surface-enhanced Raman spectroscopy (SERS), spark excitation-fiber optic spectrochemical emission sensor (FOSES), chemical optrodes, stripping voltammetry, catalytic surface-modified ion electrode immunoassay sensors, resistance/capacitance, quartz piezobalance and surface acoustic wave devices. Because the flow of heat is difficult to control, there are currently no environmental chemical sensors based on thermal transduction. The ability of these ten instrument systems to detect the thirteen priority contaminants at the Hanford Site at the required sensitivity was evaluated. In addition, all ten instrument systems were qualitatively evaluated for general selectivity, response time, reliability, and field operability. 45 refs., 23 figs., 7 tabs.
Evaluation of chemical sensors for in situ ground-water monitoring at the Hanford Site

International Nuclear Information System (INIS)

Murphy, E.M.; Hostetler, D.D.

1989-03-01

This report documents a preliminary review and evaluation of instrument systems and sensors that may be used to detect ground-water contaminants in situ at the Hanford Site. Three topics are covered in this report: (1) identification of a group of priority contaminants at Hanford that could be monitored in situ, (2) a review of current instrument systems and sensors for environmental monitoring, and (3) an evaluation of instrument systems that could be used to monitor Hanford contaminants. Thirteen priority contaminants were identified in Hanford ground water, including carbon tetrachloride and six related chlorinated hydrocarbons, cyanide, methyl ethyl ketone, chromium (VI), fluoride, nitrate, and uranium. Based on transduction principles, chemical sensors were divided into four classes, ten specific types of instrument systems were considered: fluorescence spectroscopy, surface-enhanced Raman spectroscopy (SERS), spark excitation-fiber optic spectrochemical emission sensor (FOSES), chemical optrodes, stripping voltammetry, catalytic surface-modified ion electrode immunoassay sensors, resistance/capacitance, quartz piezobalance and surface acoustic wave devices. Because the flow of heat is difficult to control, there are currently no environmental chemical sensors based on thermal transduction. The ability of these ten instrument systems to detect the thirteen priority contaminants at the Hanford Site at the required sensitivity was evaluated. In addition, all ten instrument systems were qualitatively evaluated for general selectivity, response time, reliability, and field operability. 45 refs., 23 figs., 7 tabs
Preliminary site description Forsmark area - version 1.1

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-03-01

This report presents the interim version (model version 1.1) of the preliminary Site Descriptive Model for Forsmark. The basis for this interim version is quality-assured, geoscientific and ecological field data from Forsmark that were available in the SKB databases SICADA and GIS at April 30, 2003 as well as version 0 of the Site Descriptive Model. The new data acquired during the initial site investigation phase to the date of data freeze 1.1 constitute the basis for the updating of version 0 to version 1.1. These data originate from surface investigations on the candidate area with its regional environment and from drilling and investigations in boreholes. The surface-based data sets were rather extensive whereas the data sets from boreholes were limited to information from one 1,000 m deep cored borehole (KFM01A) and eight 150 to 200 m deep percussion-drilled boreholes in the Forsmark candidate area. Discipline specific models are developed for a selected regional and local model volume and these are then integrated into a site description. The current methodologies for developing the discipline specific models and the integration of these are documented in methodology reports or strategy reports. In the present work, the guidelines given in those reports were followed to the extent possible with the data and information available at the time for data freeze for model version 1.1. Compared with version 0 there are considerable additional features in the version 1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and much higher resolution surface data. The existence of highly fractured sub-horizontal zones has been verified and these are now part of the model of the deformation zones. A discrete fracture network (DFN) model has also been developed. The rock mechanics model is based on strength information from SFR and an empirical

A Preliminary Rubric Design to Evaluate Mixed Methods Research

Science.gov (United States)

Burrows, Timothy J.

2013-01-01

With the increase in frequency of the use of mixed methods, both in research publications and in externally funded grants there are increasing calls for a set of standards to assess the quality of mixed methods research. The purpose of this mixed methods study was to conduct a multi-phase analysis to create a preliminary rubric to evaluate mixed…
Connecticut Transit (CTTRANSIT) Fuel Cell Transit Bus: Preliminary Evaluation Results

Energy Technology Data Exchange (ETDEWEB)

Chandler, K.; Eudy, L.

2008-10-01

This report provides preliminary results from a National Renewable Energy Laboratory evaluation of a protoptye fuel cell transit bus operating at Connecticut Transit in Hartford. Included are descriptions of the planned fuel cell bus demonstration and equipment; early results and agency experience are also provided.
Preliminary assessment of potential underground stability (wedge and spalling) at Forsmark, Simpevarp and Laxemar sites

Energy Technology Data Exchange (ETDEWEB)

Martin, Derek [Univ. of Alberta, Edmonton (Canada). Geotechnical Engineering

2005-12-15

In SKB's Underground Design Premises the objective in the early design phase is to estimate if there is sufficient space for the repository at a site. One of the conditions that could limit the space available is stability of the underground openings, i.e., deposition tunnels and deposition boreholes. The purpose of this report is to provide a preliminary assessment of the potential for wedge instability and spalling that may be encountered at the Forsmark, Simpevarp and Laxemar sites based on information from the site investigations program up to July 30, 2004. The rock mass spalling strength was defined using the in-situ results from SKB's Aespoe Pillar Stability Experiment and AECL's Mine-by Experiment. These experiments suggest that the rock mass spalling strength for crystalline rocks can be estimated as 0.57 of the mean laboratory uniaxial compressive strength. A probability-based methodology utilizing this in-situ rock mass spalling strength has been developed for assessing the risk for spalling in a repository at the Forsmark, Simpevarp and Laxemar sites. The in-situ stresses and the uniaxial compressive strength data from these sites were used as the bases for the analyses. Preliminary findings from all sites suggest that, generally, the risk for spalling increases as the depth of the repository increases, simply because the stress magnitudes increase with depth. The depth at which the risk for spalling is significant, depends on the individual sites which are discussed below. The greatest uncertainty in the spalling analyses for Forsmark is related to the uncertainty in the horizontal stress magnitudes and associated stress gradients with depth. The confidence in these analyses can only be increased by increasing the confidence in the stress and geology model for the site. From the analyses completed it appears that spalling in the deposition tunnels can be controlled by orienting the tunnels approximately parallel to the maximum horizontal
Preliminary systems engineering evaluations for the National Ecological Observatory Network.

Energy Technology Data Exchange (ETDEWEB)

Robertson, Perry J.; Kottenstette, Richard Joseph; Crouch, Shannon M.; Brocato, Robert Wesley; Zak, Bernard Daniel; Osborn, Thor D.; Ivey, Mark D.; Gass, Karl Leslie; Heller, Edwin J.; Dishman, James Larry; Schubert, William Kent; Zirzow, Jeffrey A.

2008-11-01

The National Ecological Observatory Network (NEON) is an ambitious National Science Foundation sponsored project intended to accumulate and disseminate ecologically informative sensor data from sites among 20 distinct biomes found within the United States and Puerto Rico over a period of at least 30 years. These data are expected to provide valuable insights into the ecological impacts of climate change, land-use change, and invasive species in these various biomes, and thereby provide a scientific foundation for the decisions of future national, regional, and local policy makers. NEON's objectives are of substantial national and international importance, yet they must be achieved with limited resources. Sandia National Laboratories was therefore contracted to examine four areas of significant systems engineering concern; specifically, alternatives to commercial electrical utility power for remote operations, approaches to data acquisition and local data handling, protocols for secure long-distance data transmission, and processes and procedures for the introduction of new instruments and continuous improvement of the sensor network. The results of these preliminary systems engineering evaluations are presented, with a series of recommendations intended to optimize the efficiency and probability of long-term success for the NEON enterprise.
Description of surface systems. Preliminary site description. Forsmark area Version 1.2

Energy Technology Data Exchange (ETDEWEB)

Lindborg, Tobias [ed.

2005-06-01

Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in
Description of surface systems. Preliminary site description. Forsmark area Version 1.2

International Nuclear Information System (INIS)

Lindborg, Tobias

2005-06-01

Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in
Drift design methodology and preliminary application for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Hardy, M.P.; Bauer, S.J.

1991-12-01

Excavation stability in an underground nuclear waste repository is required during construction, emplacement, retrieval (if required), and closure phases to ensure worker health and safety, and to prevent development of potential pathways for radionuclide migration in the post-closure period. Stable excavations are developed by appropriate excavation procedures, design of the room shape, design and installation of rock support reinforcement systems, and implementation of appropriate monitoring and maintenance programs. In addition to the loads imposed by the in situ stress field, the repository drifts will be impacted by thermal loads developed after waste emplacement and, periodically, by seismic loads from naturally occurring earthquakes and underground nuclear events. A priori evaluation of stability is required for design of the ground support system, to confirm that the thermal loads are reasonable, and to support the license application process. In this report, a design methodology for assessing drift stability is presented. This is based on site conditions, together with empirical and analytical methods. Analytical numerical methods are emphasized at this time because empirical data are unavailable for excavations in welded tuff either at elevated temperatures or under seismic loads. The analytical methodology incorporates analysis of rock masses that are systematically jointed, randomly jointed, and sparsely jointed. In situ thermal and seismic loads are considered. Methods of evaluating the analytical results and estimating ground support requirements for all the full range of expected ground conditions are outlines. The results of a preliminary application of the methodology using the limited available data are presented. 26 figs., 55 tabs
Summary report of the experiences from TVO's site investigations

International Nuclear Information System (INIS)

Oehberg, A.; Saksa, P.; Ahokas, H.; Ruotsalainen, P.; Snellman, M.

1994-05-01

Teollisuuden Voima Oy (TVO) has completed preliminary site investigations at five sites in Finland. At the end of 1992 TVO presented the final report to the authorities. The preliminary site investigation phase 1986-1992 was conducted according to the investigation programme compiled by TVO. The aim of this report was to compile a report on experiences from TVOs site investigations. The main interest was focused on investigation strategies and the most important investigation methods for the conceptual modelling. The objective of the preliminary site investigations was to obtain data on the bedrock properties in order to evaluate the areas. The programme was divided into four stages, each stage having its own sub-objective. The site-specific investigation programme for each site included a large common part and a small site-specific part. The strategies (objectives) and experiences from different disciplines, geology, hydrogeochemistry, geophysics and geohydrology, are presented in the report. The conceptual modelling work procedure including both bedrock and groundwater modelling is described briefly using the Olkiluoto site as an example. Each of the other areas has undergone similar phases of work. The uncertainties associated with conceptual modelling are also discussed. The usefulness of the investigation strategy and the investigation methods for conceptual modelling is discussed in the report. Some new equipment, methods or enhancements that have not yet been used in TVOs site investigations have become new tools in site characterisation and are briefly presented in the report. 52 refs, 35 figs, 1 tab
Evaluation of melter technologies for vitrification of Hanford site low-level tank waste - phase 1 testing summary report

Energy Technology Data Exchange (ETDEWEB)

Wilson, C.N., Westinghouse Hanford

1996-06-27

Following negotiation of the fourth amendment to the Tri- Party Agreement for Hanford Site cleanup, commercially available melter technologies were tested during 1994 and 1995 for vitrification of the low-level waste (LLW) stream to be derived from retrieval and pretreatment of the radioactive defense wastes stored in 177 underground tanks. Seven vendors were selected for Phase 1 testing to demonstrate vitrification of a high-sodium content liquid LLW simulant. The tested melter technologies included four Joule-heated melters, a carbon electrode melter, a combustion melter, and a plasma melter. Various dry and slurry melter feed preparation processes also were tested. The technologies and Phase 1 testing results were evaluated and a preliminary technology down-selection completed. This report describes the Phase 1 LLW melter vendor testing and the tested technologies, and summarizes the testing results and the preliminary technology recommendations.
External human induced events in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of the present Safety Guide is to provide recommendations and guidance for the examination of the region considered for site evaluation for a plant in order to identity hazardous phenomena associated with human induced events initiated by sources external to the plant. In some cases it also presents preliminary guidance for deriving values of relevant parameters for the design basis. This Safety Guide is also applicable for periodic site evaluation and site evaluation following a major human induced event, and for the design and operation of the site's environmental monitoring system. Site evaluation includes site characterization. Consideration of external events that could lead to a degradation of the safety features of the plant and cause a release of radioactive material from the plant and/or affect the dispersion of such material in the environment. And consideration of population issues and access issues significant to safety (such as the feasibility of evacuation, the population distribution and the location of resources). The process of site evaluation continues throughout the lifetime of the facility, from siting to design, construction, operation and decommissioning. The external human induced events considered in this Safety Guide are all of accidental origin. Considerations relating to the physical protection of the plant against wilful actions by third parties are outside its scope. However, the methods described herein may also have some application for the purposes of such physical protection. The present Safety Guide may also be used for events that may originate within the boundaries of the site, but from sources which are not directly involved in the operational states of the nuclear power plant units, such as fuel depots or areas for the storage of hazardous materials for the construction of other facilities at the same site. Special consideration should be given to the hazardous material handled during the construction, operation and
Suicide intervention training evaluation: a preliminary report.

Science.gov (United States)

Tierney, R J

1994-01-01

To date, very little work has been done on evaluating training in suicide intervention. This study developed and piloted a comprehensive method for evaluating suicide intervention training by applying three studies of immediate training effects on (a) suicide intervention abilities, (b) attitudes to suicide and suicide intervention, and (c) knowledge about suicide. The focus of the evaluation was a broadly used 2-day suicide intervention training program. Changes in suicide intervention abilities were measured by the Suicide Intervention Response Inventory (SIRI) and by performance in simulated suicide intervention situations, scored with the Suicide Intervention Protocol (SIP). Subjects consisted of 19 workshop participants in a pre-post condition and 17 participants in a post-test only condition. Results indicated significant increases in skills in suicide intervention situations. No significant effects were noted on the SIRI. Results from the attitudes and knowledge studies were very preliminary. They are reported here so that others may become aware of the methodology being used and the status of evaluation of the target program. Implications for further research are discussed.
Preliminary design package for solar heating and hot water system

Science.gov (United States)

1976-01-01

Two prototype solar heating and hot water systems for use in single-family dwellings or commercial buildings were designed. Subsystems included are: collector, storage, transport, hot water, auxiliary energy, and government-furnished site data acquisition. The systems are designed for Yosemite, California, and Pueblo, Colorado. The necessary information to evaluate the preliminary design for these solar heating and hot water systems is presented. Included are a proposed instrumentation plan, a training program, hazard analysis, preliminary design drawings, and other information about the design of the system.
Evaluations on the R Wave in asymptomatic subjects: a preliminary ...

African Journals Online (AJOL)

This preliminary cross-sectional survey on the R wave of the 12-lead electrocardiogram (ECG) was undertaken to evaluate the normal R wave duration and amplitude of the young adult Nigerian from Jos; to ascertain significant correlation coefficients for R wave duration and amplitude, age and anthropometric ...
Bioremediation evaluation of surface soils contaminated with organic compounds

International Nuclear Information System (INIS)

Tezak, J.; Miller, J.A.; Lawrence, A.W.; Keffer, R.E.; Weightman, R.; Hayes, T.D.

1994-01-01

This paper presents background information on bioremediation; information on biotechnologies that have been proven in other industries and that may be applicable to the natural gas industry; a protocol for assessing the feasibility of bioremediation; and, some preliminary results on some soils that were evaluated using the protocol. Background information related to natural gas production and processing sites and chemicals that are typically used are presented because both are important preliminary feasibility screening criteria. Applications of bioremediation to sites with similar chemicals such as refineries, wood treating plants, and former manufactured gas plants (MGP's) have been used for approximately 30 years, however bioremediation is not widely used to treat wellhead sites or natural gas production and processing sites. Examples of applications of bioremediation to non-natural gas industry sites are presented and the similarities, primarily chemical, are presented. The GRI developed an Accelerated Biotreatability Protocol for former MGP sites and it is currently being modified for application to the Exploration and Production (E and P) industry. The Accelerated Treatability Protocol is a decision-making framework to evaluate the potential full-scale biological treatment options. Preliminary results from some soils collected and evaluated using the protocol are presented
Evaluation of breastfeeding Web sites for patient education.

Science.gov (United States)

Dornan, Barbara A; Oermann, Marilyn H

2006-01-01

To evaluate the quality of Web sites on breastfeeding for patient education. Descriptive study of 30 Web sites on breastfeeding for patient education, evaluated based on the Health Information Technology Institute (HITI) criteria, readability, and eight content criteria from the American Academy of Pediatrics (AAP) policy statement on breastfeeding. The mean Flesch-Kincaid Grade Level for readability of the 30 sites was 9.2. Seven of the sites included all eight of the content criteria from the AAP, and three sites did not include any of the information recommended by the AAP content criteria. Nurses should be able to recommend best patient education materials for their patients. The five best Web sites for breastfeeding education are identified for patient teaching, and the HITI criteria are explained for nurses to learn how to evaluate Web sites for themselves and their patients.
Evaluation of the Overall Costs for the Croatian Repository: Varying Site, Design and Financial Parameters

International Nuclear Information System (INIS)

Kucar-Dragicevic, S.; Subasic, D.; Lebegner, J.

2000-01-01

Preliminary preparations for the construction of a LILW repository in Croatia included a number of activities and projects related to the siting process, safety assessment, disposal technology and repository design, and public acceptance issues. Costs evaluations have always been a part of the developing project documentation. However, only the estimates of the facility construction and equipment acquisition costs had been included, while other costs associated with the project development and management have not been considered up to now. For the first time the infrastructure status at the potential sites has been evaluated, and the costs of the repository operations as well as the post-closure management has been estimated. Cost parameters have been considered from both technical and fiscal points of view, comparing their relative influence on the overall repository costs. Assessment of the total project costs in eight cases for the four preferential sites and two repository designs gave a clearer picture of the development and management costs differences for the considered options. Without considerations of the operational and post-operational repository management expenses, the total project costs appear to have been heavily underestimated. Also, while the construction costs for the tunnel and the surface type repositories are significantly different, this influence of the repository type on the total project costs becomes far less important when the later phases management expenses are added. Finally, the role of fiscal parameters may further diminish the site and technology impacts on the overall costs. (author)
Ecological criteria for evaluating candidate sites for marine reserves

Science.gov (United States)

Roberts, Callum M.; Andelman, Sandy; Branch, George; Bustamante, Rodrigo H.; Castilla, Juan Carlos; Dugan, Jenifer; Halpern, Benjamin S.; Lafferty, Kevin D.; Leslie, Heather; Lubchenco, Jane; McArdle, Deborah; Possingham, Hugh P.; Ruckelshaus, Mary; Warner, Robert R.

2003-01-01

Several schemes have been developed to help select the locations of marine reserves. All of them combine social, economic, and biological criteria, and few offer any guidance as to how to prioritize among the criteria identified. This can imply that the relative weights given to different criteria are unimportant. Where two sites are of equal value ecologically, then socioeconomic criteria should dominate the choice of which should be protected. However, in many cases, socioeconomic criteria are given equal or greater weight than ecological considerations in the choice of sites. This can lead to selection of reserves with little biological value that fail to meet many of the desired objectives. To avoid such a possibility, we develop a series of criteria that allow preliminary evaluation of candidate sites according to their relative biological values in advance of the application of socioeconomic criteria. We include criteria that, while not strictly biological, have a strong influence on the species present or ecological processes. Our scheme enables sites to be assessed according to their biodiversity, the processes which underpin that diversity, and the processes that support fisheries and provide a spectrum of other services important to people. Criteria that capture biodiversity values include biogeographic representation, habitat representation and heterogeneity, and presence of species or populations of special interest (e.g., threatened species). Criteria that capture sustainability of biodiversity and fishery values include the size of reserves necessary to protect viable habitats, presence of exploitable species, vulnerable life stages, connectivity among reserves, links among ecosystems, and provision of ecosystem services to people. Criteria measuring human and natural threats enable candidate sites to be eliminated from consideration if risks are too great, but also help prioritize among sites where threats can be mitigated by protection. While our
Preliminary design package for solar heating and hot water system

Science.gov (United States)

1977-01-01

The preliminary design review on the development of a multi-family solar heating and domestic hot water prototype system is presented. The report contains the necessary information to evaluate the system. The system consists of the following subsystems: collector, storage, transport, control and Government-furnished site data acquisition.
Interactive Block Games for Assessing Children's Cognitive Skills: Design and Preliminary Evaluation

Directory of Open Access Journals (Sweden)

Kiju Lee

2018-05-01

Full Text Available Background: This paper presents design and results from preliminary evaluation of Tangible Geometric Games (TAG-Games for cognitive assessment in young children. The TAG-Games technology employs a set of sensor-integrated cube blocks, called SIG-Blocks, and graphical user interfaces for test administration and real-time performance monitoring. TAG-Games were administered to children from 4 to 8 years of age for evaluating preliminary efficacy of this new technology-based approach.Methods: Five different sets of SIG-Blocks comprised of geometric shapes, segmented human faces, segmented animal faces, emoticons, and colors, were used for three types of TAG-Games, including Assembly, Shape Matching, and Sequence Memory. Computational task difficulty measures were defined for each game and used to generate items with varying difficulty. For preliminary evaluation, TAG-Games were tested on 40 children. To explore the clinical utility of the information assessed by TAG-Games, three subtests of the age-appropriate Wechsler tests (i.e., Block Design, Matrix Reasoning, and Picture Concept were also administered.Results: Internal consistency of TAG-Games was evaluated by the split-half reliability test. Weak to moderate correlations between Assembly and Block Design, Shape Matching and Matrix Reasoning, and Sequence Memory and Picture Concept were found. The computational measure of task complexity for each TAG-Game showed a significant correlation with participants' performance. In addition, age-correlations on TAG-Game scores were found, implying its potential use for assessing children's cognitive skills autonomously.
The opportunities and challenges of multi-site evaluations: lessons from the jail diversion and trauma recovery national cross-site evaluation.

Science.gov (United States)

Stainbrook, Kristin; Penney, Darby; Elwyn, Laura

2015-06-01

Multi-site evaluations, particularly of federally funded service programs, pose a special set of challenges for program evaluation. Not only are there contextual differences related to project location, there are often relatively few programmatic requirements, which results in variations in program models, target populations and services. The Jail Diversion and Trauma Recovery-Priority to Veterans (JDTR) National Cross-Site Evaluation was tasked with conducting a multi-site evaluation of thirteen grantee programs that varied along multiple domains. This article describes the use of a mixed methods evaluation design to understand the jail diversion programs and client outcomes for veterans with trauma, mental health and/or substance use problems. We discuss the challenges encountered in evaluating diverse programs, the benefits of the evaluation in the face of these challenges, and offer lessons learned for other evaluators undertaking this type of evaluation. Copyright © 2015 Elsevier Ltd. All rights reserved.

Preliminary research on groundwater flow characteristics of the low- and Intermediate-level radioactive waste disposal site

International Nuclear Information System (INIS)

Koh, Young Kwon; Bae, Dae Seok; Kim, Geon Young; Ryu, Ji Hoon; Park, Kyung Woo; Ji, Sung Hoon; Kim, Kyung Su

2009-08-01

Preliminary site survey and candidate survey complements the purpose of the current site selection and disposal place selected for the study because of hydraulic to the geological survey done for the general idea was brought in the field of geochemistry survey was made. Therefore, this report hydraulic - the underlying structure of the model deterministic deformation zone model to focus on the configuration kept, according to data survey by hydraulic and hydraulic rock star pitcher trying to figure out the scope of the structure factors were hydraulic. Groundwater and related land place shares characteristics of the existing data and complementary research and laboratory research performed on the basis of geochemical data, based on the following major finding were present
Conceptual Site Treatment Plan Laboratory for Energy-Related Health Research Environmental Restoration Project

Energy Technology Data Exchange (ETDEWEB)

Chapman, T.E.

1993-10-01

The Federal Facilities Compliance Act (the Act) of 1992 waives sovereign immunity for federal facilities for fines and penalties under the provisions of the Resource Recovery and Conservation Act, state, interstate, and local hazardous and solid waste management requirements. However, for three years the Act delays the waiver for violations involving US Department of Energy (DOE) facilities. The Act, however, requires that the DOE prepare a Conceptual Site Treatment Plan (CSTP) for each of its sites that generate or store mixed wastes (MWs). The purpose of the CSTP is to present DOE`s preliminary evaluations of the development of treatment capacities and technologies for treating a site`s MW. This CSTP presents the preliminary capacity and technology evaluation for the Laboratory for Energy-Related Health Research (LEHR). The five identified MW streams at LEHR are evaluated to the extent possible given available information. Only one MW stream is sufficiently well defined to permit a technology evaluation to be performed. Two other MW streams are in the process of being characterized so that an evaluation can be performed. The other two MW streams will be generated by the decommissioning of inactive facilities onsite within the next five years.
Preliminary design package for prototype solar heating system

Energy Technology Data Exchange (ETDEWEB)

1978-12-01

A summary is given of the preliminary analysis and design activity on solar heating systems. The analysis was made without site specific ata other than weather; therefore, the results indicate performance expected under these special conditions. Major items in this report include systeem candidates, design approaches, trade studies and other special data required to evaluate the preliminary analysis and design. The program calls for the development and delivery of eight prototype solar heating and coolin systems for installation and operational test. Two-heating and six heating and cooling units will be delivered for Single Family Residences (SFR), Multi-Family Residences (MFR) and commercial applications.
Effect of ionizing radiation on radionuclide speciation: Preliminary results from site-specific experiments in a basaltic system

International Nuclear Information System (INIS)

Reed, D.T.; Burnell, J.R.

1986-01-01

Rockwell Hanford Operations, under contract to the Department of Energy, is investigating the suitability of the Hanford site in the state of Washington as a high level nuclear waste repository. An important consideration in these investigations is the effect of ionizing radiation on the speciation of radionuclides in the groundwater after the high-level-waste container has been breached and there is direct contact between the groundwater and the waste form (controlled released period). The effect of ionizing radiation on radionuclide speciation depends on the radiation environment and site-specific chemistry near the waste container. With respect to these two aspects, the following results will be presented: a definition of the radiation environment during the controlled release period; preliminary site-specific experimental results: (1) basaltic systems spiked with radionuclides; (2) spent fuel-groundwater-basalt experiments
Super-Efficient Refrigerator Program (SERP) evaluation volume 2: Preliminary impact and market transformation assessment

Energy Technology Data Exchange (ETDEWEB)

Lee, A.D.; Conger, R.L.

1996-08-01

The Super Efficient Refrigerator Program (SERP) is a collaborative utility program intended to transform the market for energy-efficient and environmentally friendly refrigerators. It is one of the first examples of a large-scale {open_quotes}market transformation{close_quotes} energy efficiency program. This report documents the preliminary impact and market transformation evaluation of SERP ({open_quotes}the Program{close_quotes}). Pacific Northwest National Laboratory (PNNL) conducted this evaluation for the U.S. Department of Energy. This study focuses on the preliminary impact evaluation and market transformation assessment, but also presents limited process evaluation information. It is based on interviews with refrigerator dealers and manufacturers, interviews with utility participants, industry data, and information from the Program administrators. Results from this study complement those from prior process evaluation also conducted by PNNL. 42 refs., 5 figs., 4 tabs.
Evaluation of a committed fusion site. Final report

International Nuclear Information System (INIS)

1979-07-01

This report is divided into five technical sections. Section 2 is a summary. In Section 3, which covers device and site analyses the major characteristics of devices that might be placed at the site, as envisioned by major fusion laboratories, are described; the characteristics of a site (baseline site) which would accommodate these devices are defined; and various approaches to a committed site meeting the baseline site requirements are discussed. Section 4 describes the scenarios selected to represent possible site development outcomes; these scenarios are evaluated with respect to comparative cost and schedule effects. Section 5 presents a brief evaluation of the effects fusion-fission hybrids might have on the committed site. Major conclusions and recommendations are discussed in Section 6
SITE-94. Discrete-feature modelling of the Aespoe site: 4. Source data and detailed analysis procedures

Energy Technology Data Exchange (ETDEWEB)

Geier, J E [Golder Associates AB, Uppsala (Sweden)

1996-12-01

Specific procedures and source data are described for the construction and application of discrete-feature hydrological models for the vicinity of Aespoe. Documentation is given for all major phases of the work, including: Statistical analyses to develop and validate discrete-fracture network models, Preliminary evaluation, construction, and calibration of the site-scale model based on the SITE-94 structural model of Aespoe, Simulation of multiple realizations of the integrated model, and variations, to predict groundwater flow, and Evaluation of near-field and far-field parameters for performance assessment calculations. Procedures are documented in terms of the computer batch files and executable scripts that were used to perform the main steps in these analyses, to provide for traceability of results that are used in the SITE-94 performance assessment calculations. 43 refs.
SITE-94. Discrete-feature modelling of the Aespoe site: 4. Source data and detailed analysis procedures

International Nuclear Information System (INIS)

Geier, J.E.

1996-12-01

Specific procedures and source data are described for the construction and application of discrete-feature hydrological models for the vicinity of Aespoe. Documentation is given for all major phases of the work, including: Statistical analyses to develop and validate discrete-fracture network models, Preliminary evaluation, construction, and calibration of the site-scale model based on the SITE-94 structural model of Aespoe, Simulation of multiple realizations of the integrated model, and variations, to predict groundwater flow, and Evaluation of near-field and far-field parameters for performance assessment calculations. Procedures are documented in terms of the computer batch files and executable scripts that were used to perform the main steps in these analyses, to provide for traceability of results that are used in the SITE-94 performance assessment calculations. 43 refs
Guidance for performing preliminary assessments under CERCLA

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-09-01

EPA headquarters and a national site assessment workgroup produced this guidance for Regional, State, and contractor staff who manage or perform preliminary assessments (PAs). EPA has focused this guidance on the types of sites and site conditions most commonly encountered. The PA approach described in this guidance is generally applicable to a wide variety of sites. However, because of the variability among sites, the amount of information available, and the level of investigative effort required, it is not possible to provide guidance that is equally applicable to all sites. PA investigators should recognize this and be aware that variation from this guidance may be necessary for some sites, particularly for PAs performed at Federal facilities, PAs conducted under EPA`s Environmental Priorities Initiative (EPI), and PAs at sites that have previously been extensively investigated by EPA or others. The purpose of this guidance is to provide instructions for conducting a PA and reporting results. This guidance discusses the information required to evaluate a site and how to obtain it, how to score a site, and reporting requirements. This document also provides guidelines and instruction on PA evaluation, scoring, and the use of standard PA scoresheets. The overall goal of this guidance is to assist PA investigators in conducting high-quality assessments that result in correct site screening or further action recommendations on a nationally consistent basis.
Remediation Technology of Contaminated Areas with Organochlorines: A Preliminary Evaluation Seeking Potential Applications on the Site of Street Capua, Santo André - SP

Directory of Open Access Journals (Sweden)

Mauro Silva Ruiz

2012-12-01

Full Text Available This paper is aimed to analyze the use of remediation technologies for areas contaminated with organochlorine based on a literature review and discussions with specialists. The remediation technologies analyzed were bioremediation, phytoremediation, nanotechnology, chemical oxidation, and thermal desorption. The purpose is to identify and compare “key problems” for each of these technologies envisaging the use of one or more of these them f or the remediation of the Capua Street site in Santo André, SP. Four databases were used in the preliminary literature review: Scopus, SciELO, Web of Science, and Science Direct. A survey questionnaire was designed to gather information on publications of scientific papers and patents, specific uses of these technologies by companies, and cases of application. Since the quality of the data and information obtained from this questionnaire application was not satisfactory, a new research approach for complementing them was undertaken. For this purpose, the Web of Science was selected as the most adequate data basis to carry out this second survey. However, it was realized that even for this database - that is reference for evaluating academic institutions, researchers and maturity of technologies – bias coming from the original data source can affect the survey results. Moreover, as the number of keywords used in the research consisted of generic terms for each technology, it can also be assumed that if some authors have used very specific terms, a small amount of work published by them would possibly have been misrepresented in the final result.
A new methodology for repository site suitability evaluation

International Nuclear Information System (INIS)

Miller, I.; Kossik, R.; Cunnane, M.

1992-01-01

Golder Associates Inc. (GAI) has developed a probabilistic total system performance assessment and strategy evaluation model (RIP) which can be applied in an iterative manner to evaluate repository site suitability and guide site characterization. The major portion of the software is the performance assessment model, which consists of a series of coupled component models for radionuclide transfer. The performance model itself is embedded within a decision analysis model which allows the user to evaluate alternative site characterization strategies. This paper provides an overview of the methodology, and summarizes the basic concepts of RIP
Geoscientific long-term prognosis. Preliminary safety analysis for the site Gorleben; Geowissenschaftliche Langzeitprognose. Bericht zum Arbeitspaket 2. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

Energy Technology Data Exchange (ETDEWEB)

Mrugalla, Sabine [Bundesanstalt fuer Geowissenschaften und Rohstoffe, Hannover (Germany)

2011-07-15

The preliminary safety analysis of the site Gorleben includes the following chapters: (1) Introduction; (2) Aim and content of the geoscientific long-term prognosis for the site Gorleben; (3) Boundary conditions at the site Gorleben: climate; geomorphology; overlying rocks and adjoining rocks; hydrogeology; salt deposit Gorleben. (4) Probable future geological developments at the site Gorleben: supraregional developments with effects on the site Gorleben; glacial period developments; developments of the geomorphology, overlying and adjoining rocks; future developments of the hydrological systems at the site Gorleben; future saliniferous specific developments of the salt deposit Gorleben. (5) Commentary on the unlikely or excludable developments of the site Gorleben.
Preliminary Seismic Performance Evaluation of RPS Cabinet in a Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Kwag, Shinyoung; Oh, Jinho; Lee, Jongmin; Kim, Youngki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-05-15

This RPS cabinet mainly provides the operators with the physical interface to monitor and handle the RPS. The objective of this paper is to perform seismic analyses and evaluate the preliminary structural integrity and seismic capacity of the RPS cabinet. For this purpose, a 3-D finite element model of the RPS cabinet is developed and its modal analyses are carried out for analyzing the dynamic characteristics. Response time history analyses and related safety evaluation are performed for the RPS cabinet subjected to seismic loads. Finally, the seismic margin and seismic fragility of the RPS cabinet are investigated. The seismic analysis, and preliminary structural integrity and seismic margin of the RPS cabinet under self weight and seismic load have been evaluated. For this purpose, 3-D finite element models of the RPS cabinet were developed. A modal analysis, response time history analysis, and seismic fragility analysis were then performed. From the structural analysis results, the RPS cabinet is below the structural design limit under PGA 0.3g (hor.) and 0.2g (ver.) and structurally withstands until PGA 3g (hor.) and 2g (ver.)
Preliminary results of studies of the Valea Morilor Upper Palaeolithic site (Chisinau, Republic of Moldova) : A new camp of mammoth hunters

NARCIS (Netherlands)

Obada, Teodor; van der Plicht, Johannes; Markova, Anastasia; Prepelitsa, Afanasie

2012-01-01

Preliminary results are presented from the studies of a newly found Paleolithic site - Valea Morilor (Chisingu, Republic of Moldova). The excavations produced unquestionable evidence of mammoth hunting (Mammuthus primigenius Blumenbach, 1799). Excavations of 2009-2010 opened an area of 1264 m(2).
Global positioning site environment evaluator

International Nuclear Information System (INIS)

Leffler, S.; Reeser, H.G.; Zaker, E.; Hansen, W.; Sikorski, R.W.

1990-01-01

Development of an innovative, integrated, automated system (Global Positioning Site Environment Evaluator - GPSEETM) for surveying contaminated waste sites is described. This system makes novel use of the Global Positioning System (GPS) satellite constellation for establishing specific locations and current times for surveying radioactive, hazardous, or mixed-waste sites. GPSEE may also be used for waste site contamination surveys after remediation activities to ensure environmental remediation is complete. A base station is established for collecting and recording data and directing field operations for field stations which may be located many miles from the base station. The field operators collect site surveying and contamination data utilizing a variety of chemical and radiological sensors. A major goal for the data collection process is to collect all data utilizing in situ sensors, thereby minimizing the need for collecting soil and water samples. Site contamination data is transmitted electronically to the base station for recording and processing. The GPSEE system is being developed for use at DOE/DOD and a variety of industrial facilities. 3 figs
Site descriptive modelling - strategy for integrated evaluation

International Nuclear Information System (INIS)

Andersson, Johan

2003-02-01

The current document establishes the strategy to be used for achieving sufficient integration between disciplines in producing Site Descriptive Models during the Site Investigation stage. The Site Descriptive Model should be a multidisciplinary interpretation of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and ecosystems using site investigation data from deep bore holes and from the surface as input. The modelling comprise the following iterative steps, evaluation of primary data, descriptive and quantitative modelling (in 3D), overall confidence evaluation. Data are first evaluated within each discipline and then the evaluations are checked between the disciplines. Three-dimensional modelling (i.e. estimating the distribution of parameter values in space and its uncertainty) is made in a sequence, where the geometrical framework is taken from the geological model and in turn used by the rock mechanics, thermal and hydrogeological modelling etc. The three-dimensional description should present the parameters with their spatial variability over a relevant and specified scale, with the uncertainty included in this description. Different alternative descriptions may be required. After the individual discipline modelling and uncertainty assessment a phase of overall confidence evaluation follows. Relevant parts of the different modelling teams assess the suggested uncertainties and evaluate the feedback. These discussions should assess overall confidence by, checking that all relevant data are used, checking that information in past model versions is considered, checking that the different kinds of uncertainty are addressed, checking if suggested alternatives make sense and if there is potential for additional alternatives, and by discussing, if appropriate, how additional measurements (i.e. more data) would affect confidence. The findings as well as the modelling results are to be documented in a Site Description
Gasbuggy Site Assessment and Risk Evaluation

Energy Technology Data Exchange (ETDEWEB)

None

2011-03-01

This report describes the geologic and hydrologic conditions and evaluates potential health risks to workers in the natural gas industry in the vicinity of the Gasbuggy, New Mexico, site, where the U.S. Atomic Energy Commission detonated an underground nuclear device in 1967. The 29-kiloton detonation took place 4,240 feet below ground surface and was designed to evaluate the use of a nuclear detonation to enhance natural gas production from the Pictured Cliffs Formation in the San Juan Basin, Rio Arriba County, New Mexico, on land administered by Carson National Forest. A site-specific conceptual model was developed based on current understanding of the hydrologic and geologic environment. This conceptual model was used for establishing plausible contaminant exposure scenarios, which were then evaluated for human health risk potential. The most mobile and, therefore, the most probable contaminant that could result in human exposure is tritium. Natural gas production wells were identified as having the greatest potential for bringing detonation-derived contaminants (tritium) to the ground surface in the form of tritiated produced water. Three exposure scenarios addressing potential contamination from gas wells were considered in the risk evaluation: a gas well worker during gas-well-drilling operations, a gas well worker performing routine maintenance, and a residential exposure. The residential exposure scenario was evaluated only for comparison; permanent residences on national forest lands at the Gasbuggy site are prohibited
Monitored retrievable storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force
Monitored retrievable storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force.
SITE-94. Site specific base data for the performance assessment

International Nuclear Information System (INIS)

Geier, J.; Tiren, S.; Dverstorp, B.; Glynn, P.

1996-06-01

This report documents the site specific base data that were available, and the utilization of these data within SITE-94. A brief summary is given of SKB's preliminary site investigations for the Aespoe Hard Rock Laboratory (HRL), which were the main source of site-specific data for SITE-94, and an overview is given of the field methods and instrumentation for the preliminary investigations. A compilation is given of comments concerning the availability and quality of the data for Aespoe, and specific recommendations are given for future site investigations. It was found that the HRL pre-investigations produced a large quantity of data which were, for the most part, of sufficient quality to be valuable for a performance assessment. However, some problems were encountered regarding documentation, procedural consistency, positional information, and storage of the data from the measurements. 77 refs, 4 tabs

Wood-waste fuelled indirectly-fired gas turbine cogeneration plant for sawmill applications. Phase 2. Site-specific preliminary engineering and financial analysis

Energy Technology Data Exchange (ETDEWEB)

1988-03-01

The use of conventional steam/electricity cogeneration systems is not generally economical at the sawmill scale of operation. This paper describes an evaluation of a wood-waste fueled and, indirectly, gas fired turbine cogeneration plant aimed at developing a cost-effective wood-waste fired power generation and dry kiln heating system for sawmill applications. A preliminary engineering design and financial analysis of the system was prepared for a demonstration site in British Columbia. A number of alternative system configurations were identified and preliminary engineering designs prepared for each. In the first option , wood wastes combusted in a wet cell hot gas generator powered a 600 kW turbine, and produced 7,000 kW for the drying kilns. The second option provided the same electrical and heat output but used a down-fired suspension burner unit fuelled by clean, dried sawdust, together with an integral air heater heat exchanger. The third option represented a commercial-scale configuration with an electrical output of 1,800 kW, and sufficient heat output for the dry kilns. A financial analyis based on a computerized feasibility model was carried out on the last two options. Low electricity rates in British Columbia combined with the small scale of a demonstration project provide an inadequate rate of return at the site without substantial outside support. At a commercial scale of operation and with the higher electricity prices that exist outside of British Columbia the financial analysis indicates that the incremental investment in the electric generation portion of the system provides very attractive rates of return for the 3 options. 11 figs., 10 tabs.
Preliminary area selection considerations for radioactive waste repositories in bedded salt

International Nuclear Information System (INIS)

Wagoner, J.L.; Steinborn, T.L.

1979-01-01

This guide describes an approach to selection of areas of bedded salt which contain potentially suitable sites for the storage of radioactive waste. To evaluate a site selected by a license applicant, it is necessary to understand the technical site characteristics which should be considered in the preliminary phase of site selection. These site characteristics are presented here in checklist form, and each item is accompanied by a discussion which explains its significance. These qualitative considerations are used first to select an area of interest within a broad geologic or geomorphic region. Once an area has been selected, more quantitative information must be acquired to determine whether the proposed site meets the resultations for storage of nuclear waste
Monitored Retrievable Storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume
Monitored retrievable storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document
Monitored retrievable storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs{hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document.
Design principle of TVO's final repository and preliminary adaptation to site specific conditions

International Nuclear Information System (INIS)

Salo, J-P.; Reikkola, R.

1995-01-01

Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs
National uranium resource evaluation, preliminary report

International Nuclear Information System (INIS)

1976-06-01

The results of the initial phase of the National Uranium Resource Evaluation (NURE) are reported. NURE is a comprehensive nationwide program to evaluate uranium resources and to identify areas favorable for uranium exploration. Part I presents estimates of uranium ore reserves and potential resources available at costs (not prices) of $10, $15, and $30 per pound U 3 O 8 (uranium oxide). These estimates comprise the national uranium resource position. They are, however, preliminary because limitations of time and available geologic data prevented adequate assessment of some areas that may be favorable for potential resources. Part II presents the potential uranium resources for each of 13 regions, whose boundaries have been drawn chiefly on geologic considerations. The general geology is summarized, and the types of uranium deposits are described. Although limited geologic reconnaissance was done in various parts of the country, the report is based primarily on the compilation and evaluation of data in ERDA files. Mining companies furnished a substantial amount of information on exploration results, development, production, and future plans. Published, manuscript, and open-file reports by government agencies, universities, and research organizations were reviewed. In addition, many individuals affiliated with universities and with state and federal agencies provided supplemental geologic information. This was particularly helpful in the eastern and central states and in Alaska, where information on uranium occurrences is limited
Preliminary design package for solar hot water system

Energy Technology Data Exchange (ETDEWEB)

Fogle, Val; Aspinwall, David B.

1977-12-01

The information necessary to evaluate the preliminary design of the Solar Engineering and Manufacturing Company's (SEMCO) solar hot water system is presented. This package includes technical information, schematics, drawings and brochures. This system, being developed by SEMCO, consists of the following subsystems: collector, storage, transport, control, auxiliary energy, and Government-furnished site data acquisition. The two units being manufactured will be installed at Loxahatchee, Florida, and Macon, Georgia.
Preliminary Site Characterization Report, Rulsion Site, Colorado

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

This report is a summary of environmental information gathered during a review of the documents pertaining to Project Rulison and interviews with personnel who worked on the project. Project Rulison was part of Operation Plowshare (a program designed to explore peaceful uses for nuclear devices). The project consisted of detonating a 43-kiloton nuclear device on September 10, 1969, in western Colorado to stimulate natural gas production. Following the detonation, a reentry well was drilled and several gas production tests were conducted. The reentry well was shut-in after the last gas production test and was held in standby condition until the general cleanup was undertaken in 1972. A final cleanup was conducted after the emplacement and testing wells were plugged in 1976. However, some surface radiologic contamination resulted from decontamination of the drilling equipment and fallout from the gas flaring during drilling operations. With the exception of the drilling effluent pond, all surface contamination at the Rulison Site was removed during the cleanup operations. All mudpits and other excavations were backfilled, and both upper and lower drilling pads were leveled and dressed. This report provides information regarding known or suspected areas of contamination, previous cleanup activities, analytical results, a review of the regulatory status, the site`s physical environment, and future recommendations for Project Ruhson. Based on this research, several potential areas of contamination have been identified. These include the drilling effluent pond and mudpits used during drilling operations. In addition, contamination could migrate in the gas horizon.
Probabilistic performance assessments for evaluations of the Yucca Mountain site

International Nuclear Information System (INIS)

Rickertsen, L.D.; Noronha, C.J.

1992-01-01

Site suitability evaluations are conducted to determine if a repository system at a particular site will be able to meet the performance objectives for that system. Early evaluations to determine if the Yucca Mountain site is suitable for repository development have been made in the face of large uncertainties in site features and conditions. Because of these large uncertainties, the evaluations of the site have been qualitative in nature, focusing on the presence or absence of particular features or conditions thought to be important to performance, rather than on results of quantitative performance assessments. Such a qualitative approach was used in the recently completed evaluation of the Yucca Mountain site, the Early Site-Suitability Evaluation (ESSE). In spite of the qualitative approach, the ESSE was able to conclude that no disqualifying conditions are likely to be present at the site and that all of the geologic conditions that would qualify the site are likely to be met. At the same time, because of the qualitative nature of the approach used in the ESSE, the precise importance of the identified issues relative to performance could not be determined. Likewise, the importance of the issues relative to one another could not be evaluated, and, other than broad recommendations, specific priorities for future testing could not be set. The authors have conducted quantitative performance assessments for the Yucca Mountain site to address these issues
Assessment of mixed hazardous and radioactive waste sites at Hanford

International Nuclear Information System (INIS)

McLaughlin, T.J.; Cramer, K.H.; Lamar, D.A.; Sherwood, D.R.; Stenner, R.D.; Schulze, W.B.

1987-10-01

The US Department of Energy and Pacific Northwest Laboratory recently completed a preliminary assessment of 685 inactive hazardous waste sites located on the Hanford Site. The preliminary assessment involved collecting historical data and individual site information, conducting site inspections, and establishing an environmental impact priority, using the Hazard Ranking System, for each of these 685 sites. This preliminary assessment was the first step in the remediation process required by the Comprehensive Environmental Response, Compensation and Liability Act. This paper presents the results of that preliminary assessment. 10 refs., 4 figs., 1 tab
Expression, purification, crystallization and preliminary X-ray analysis of wild-type and of an active-site mutant of glyceraldehyde-3-phosphate dehydrogenase from Campylobacter jejuni

International Nuclear Information System (INIS)

Tourigny, David S.; Elliott, Paul R.; Edgell, Louise J.; Hudson, Gregg M.; Moody, Peter C. E.

2010-01-01

The cloning, expression, purification, crystallization and preliminary X-ray analysis of wild-type and of an active-site mutant of C. jejuni glyceraldehyde-3-phosphate dehydrogenase is reported. The genome of the enteric pathogen Campylobacter jejuni encodes a single glyceraldehyde-3-phosphate dehydrogenase that can utilize either NADP + or NAD + as coenzymes for the oxidative phosphorylation of glyceraldehyde-3-phosphate to 1,3-diphosphoglycerate. Here, the cloning, expression, purification, crystallization and preliminary X-ray analysis of both the wild type and an active-site mutant of the enzyme are presented. Preliminary X-ray analysis revealed that in both cases the crystals diffracted to beyond 1.9 Å resolution. The space group is shown to be I4 1 22, with unit-cell parameters a = 90.75, b = 90.75, c = 225.48 Å, α = 90.46, β = 90.46, γ = 222.79°; each asymmetric unit contains only one subunit of the tetrameric enzyme
Conceptual Site Treatment Plan Laboratory for Energy-Related Health Research Environmental Restoration Project

International Nuclear Information System (INIS)

Chapman, T.E.

1993-10-01

The Federal Facilities Compliance Act (the Act) of 1992 waives sovereign immunity for federal facilities for fines and penalties under the provisions of the Resource Recovery and Conservation Act, state, interstate, and local hazardous and solid waste management requirements. However, for three years the Act delays the waiver for violations involving US Department of Energy (DOE) facilities. The Act, however, requires that the DOE prepare a Conceptual Site Treatment Plan (CSTP) for each of its sites that generate or store mixed wastes (MWs). The purpose of the CSTP is to present DOE's preliminary evaluations of the development of treatment capacities and technologies for treating a site's MW. This CSTP presents the preliminary capacity and technology evaluation for the Laboratory for Energy-Related Health Research (LEHR). The five identified MW streams at LEHR are evaluated to the extent possible given available information. Only one MW stream is sufficiently well defined to permit a technology evaluation to be performed. Two other MW streams are in the process of being characterized so that an evaluation can be performed. The other two MW streams will be generated by the decommissioning of inactive facilities onsite within the next five years
Monitored Retrievable Storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs {hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume.
American National Standard: guidelines for evaluating site-related geotechnical parameters at nuclear power sites

International Nuclear Information System (INIS)

Anon.

1978-01-01

This standard presents guidelines for evaluating site-related geotechnical parameters for nuclear power sites. Aspects considered include geology, ground water, foundation engineering, and earthwork engineering. These guidelines identify the basic geotechnical parameters to be considered in site evaluation, and in the design, construction, and performance of foundations and earthwork aspects for nuclear power plants. Also included are tabulations of typical field and laboratory investigative methods useful in identifying geotechnical parameters. Those areas where interrelationships with other standards may exist are indicated
Site specific information in site selection

International Nuclear Information System (INIS)

Aeikaes, T.; Hautojaervi, A.

1998-01-01

The programme for the siting of a deep repository for final disposal of spent nuclear fuel was started already in 1983 and is carried out today by Posiva Oy which continues the work started by Teollisuuden Voima Oy. The programme aims at site selection by the end of the year 2000. The programme has progressed in successive interim stages with defined goals. After an early phase for site identification, five sites were selected in 1987 for preliminary site characterisation. Three of these were selected and judged to be best suited for the more detailed characterisation in 1992. An additional new site was included into the programme based on a separate feasibility study in the beginning of 1997. Since the year 1983 several safety assessments together with technical plans of the facility have been completed. When approaching the site selection the needs for more detailed consideration of the site specific properties in the safety assessment have been increased. The Finnish regulator STUK has published a proposal for general safety requirements for the final disposal of spent nuclear fuel in Finland. This set of requirements has been projected to be used in conjunction of the decision making by the end 2000. Based on the site evaluation all sites can provide a stable environment and there is evidence that the requirements for the longevity of the canister can be fulfilled at each site. In this manner the four candidate sites do not differ too much from each other. The main difference between the sites is in the salinity of the deep groundwater. The significance of differences in the salinity for the long-term safety cannot be defined yet. The differences may contribute to the discussion of the longevity of the bentonite buffer and also to the modelling of the groundwater flow and transport. The use of the geosphere as a transport barrier is basically culminated on the questions about sparse but fast flow routes and 'how bad channeling can be'. To answer these questions
Radioactive waste shredding: Preliminary evaluation

International Nuclear Information System (INIS)

Soelberg, N.R.; Reimann, G.A.

1994-07-01

The critical constraints for sizing solid radioactive and mixed wastes for subsequent thermal treatment were identified via a literature review and a survey of shredding equipment vendors. The types and amounts of DOE radioactive wastes that will require treatment to reduce the waste volume, destroy hazardous organics, or immobilize radionuclides and/or hazardous metals were considered. The preliminary steps of waste receipt, inspection, and separation were included because many potential waste treatment technologies have limits on feedstream chemical content, physical composition, and particle size. Most treatment processes and shredding operations require at least some degree of feed material characterization. Preliminary cost estimates show that pretreatment costs per unit of waste can be high and can vary significantly, depending on the processing rate and desired output particle size
Shallow-land burial of low-level radioactive wastes: preliminary simulations of long-term health risks

International Nuclear Information System (INIS)

Fields, D.E.; Little, C.A.; Emerson, C.J.; Hiromoto, G.

1982-01-01

PRESTO, a computer code developed for the Environmental Protection Agency for the evaluation of possible health effects associated with shallow-land rad-waste burial areas, has been used to perform simulations for three such sites. Preliminary results for the 1000 y period following site closure suggest that shallow burial, at properly chosen sites, is indeed an appropriate disposal practice for low-level wastes. Periods of maximum risk to subject populations are also inferred
Effectiveness evaluation of alternative fixed-site safeguard security systems

International Nuclear Information System (INIS)

Chapman, L.D.

1976-01-01

An evaluation of a fixed-site physical protection system must consider the interrelationships of barriers, alarms, on-site and off-site guards, and their effectiveness against a forcible adversary attack intent on creating an act of sabotage of theft. A computer model, Forcible Entry Safeguard Effectiveness Model (FESEM), was developed for the evaluation of alternative fixed-site protection systems. It was written in the GASP IV simulation language. A hypothetical fixed-state protection system is defined and relative evaluations from a cost-effectiveness point of view are presented in order to demonstrate how the model can be used. Trade-offs involving on-site and off-site response forces and response times, perimeter system alarms, barrier configurations, and varying levels of threat are analyzed. The computer model provides a framework for performing inexpensive experiments on fixed-site security systems, for testing alternative decisions, and for determining the relative cost effectiveness associated with these decision policies
Preliminary evaluation of beta-spodumene as a fusion reactor structural material

International Nuclear Information System (INIS)

Kelsey, P.V. Jr.; Schmunk, R.E.; Henslee, S.P.

1982-01-01

Beta-spodumene was investigated as a candidate material for use in fusion reactor environments. Properties which support the use of beta-spodumene include good thermal shock resistance, a very low coefficient of thermal expansion, a low-Z composition which would result in minimum impact on the plasma, and flexibility in fabrication processes. Specimens were irradiated in the Advanced Test Reactor (ATR) to a fluence of 5.3 x 10 22 n/m 2 , E > MeV, and 4.9 x 10 23 n/m 2 thermal fluence in order to obtain a preliminary evaluation of the impact of irradiation on the material. Preliminary data indicate that the mechanical properties of beta-spodumene are little affected by irradiation. Gas production and release have also been investigated. (orig.)

Development and preliminary analyses of material balance evaluation model in nuclear fuel cycle

International Nuclear Information System (INIS)

Matsumura, Tetsuo

1994-01-01

Material balance evaluation model in nuclear fuel cycle has been developed using ORIGEN-2 code as basic engine. This model has feature of: It can treat more than 1000 nuclides including minor actinides and fission products. It has flexibility of modeling and graph output using a engineering work station. I made preliminary calculation of LWR fuel high burnup effect (reloading fuel average burnup of 60 GWd/t) on nuclear fuel cycle. The preliminary calculation shows LWR fuel high burnup has much effect on Japanese Pu balance problem. (author)
(11)C-labeling and preliminary evaluation of vortioxetine as a PET radioligand

DEFF Research Database (Denmark)

Andersen, Valdemar L; Hansen, Hanne D; Herth, Matthias M

2014-01-01

. Preliminary evaluation of [(11)C]vortioxetine in a Danish Landrace pig showed rapid brain uptake and brain distribution in accordance with the pharmacological profile, all though an unexpected high binding in cerebellum was also observed. [(11)C]vortioxetine displayed slow tracer kinetics with peak uptake...
Hydrogeochemical evaluation for Simpevarp model version 1.2. Preliminary site description of the Simpevarp area

Energy Technology Data Exchange (ETDEWEB)

Laaksoharju, Marcus (ed.) [Geopoint AB, Stockholm (Sweden)

2004-12-01

Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Simpevarp groundwater analytical data collected up to April, 2004. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1.7 km. Model version 1.2 focusses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1000 m depth. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1000 m depending on local topography. The marked differences in the groundwater flow regimes between Laxemar and Simpevarp are reflected in the groundwater chemistry where four major hydrochemical groups of groundwaters (types A-D) have been identified: TYPE A: This type comprises dilute groundwaters (< 1000 mg/L Cl; 0.5-2.0 g/L TDS) of Na-HCO{sub 3} type present at shallow (<200 m) depths at Simpevarp, but at greater depths (0-900 m) at Laxemar. At both localities the groundwaters are marginally oxidising close to the surface, but otherwise reducing. Main reactions involve weathering, ion exchange (Ca, Mg), surface complexation, and dissolution of calcite. Redox reactions include precipitation of Fe-oxyhydroxides and some microbially mediated reactions (SRB). Meteoric recharge water is mainly present at Laxemar whilst at Simpevarp potential mixing of recharge meteoric water and a modern sea component is observed. Localised mixing of meteoric water with deeper saline groundwaters is indicated at both Laxemar and Simpevarp. TYPE B: This type comprises brackish groundwaters (1000-6000 mg/L Cl; 5-10 g/L TDS) present at
Preliminary Phytochemical Evaluation of Seed Extracts of Cucurbita Maxima Duchense

OpenAIRE

Ashok Sharma; Ashish K. Sharma; Tara Chand; Manoj Khardiya; Kailash Chand Yadav

2013-01-01

Cucurbita maxima Duchense (family:Cucurbitaceae) is a trailing annual herb, widely cultivated throughout India and in most warm regions of the world, for used as vegetables as well as medicines. The present study deals with preliminary physicochemical and phytochemical evaluation of seed extract of Cucurbita maxima. The study includes preparation of different extracts by successive solvent extraction for detailed analysis. Different physicochemical parameters such as ash value (total ash, aci...
Geochemical analysis of the sealing system. Technical Report to work package 9.1.2. Preliminary safety case of the Gorleben site (VSG)

Energy Technology Data Exchange (ETDEWEB)

Xie, Mingliang; Herbert, Horst-Juergen

2012-02-15

The geochemical reaction simulation of ground water and brines with sealing materials for a proposed repository at the Gorleben site is a task under the framework of the VSG project. The calculations presented in this report are aimed to provide a preliminary evaluation of the geochemical stability of three potential engineering barrier materials foreseen in the shaft sealing system in case of groundwater and brine intrusion. The long-term stability of these materials is a key issue for the sealing function of the shaft seals. This is governed by many factors such as geotechnical, hydraulic and geochemical processes. In order to better understand the potential effect of geochemical processes on the long-term properties of these sealing materials, geochemical simulations of the potential interactions between groundwater and brine and shaft sealing materials were performed.
The accumulation of a platelet protein, thrombospondin, at the site of arterial thrombus formation: Preliminary report

International Nuclear Information System (INIS)

Perlman, S.B.; Hammes, R.J.; Besozzi, M.C.; Folts, J.D.; Mosher, D.F.

1987-01-01

There are many methods available for the detection of thrombosis, none of which are noninvasive, rapid and accurate. Thrombosponding is a platelet protein that is present in the developing thrombus and may be an effective substance to use for imaging thrombosis. Vascular stenosis and thrombosis were produced in coronary, carotid and femoral arteries in eleven adult mongrel dogs. 131 I labeled thrombosponding was administered to each animal to determine whether the radiotracer accumulated at the site of thrombus formation. The radioactivity per gram of vessels with thrombi was significantly different from the control vessels or whole blood (p=0.0037 and p=0.015, respectively, paired t-test). This preliminary work suggests that iodinated thrombosponding accumulates at the site of thrombus formation. Labeled thrombosponding may be a rapid, safe and accurate method of detecting arterial thrombosis. (orig.)
Preliminary evaluation of sweet spot size in virtual sound reproduction using dipoles

DEFF Research Database (Denmark)

Lacouture Parodi, Yesenia; Rubak, Per

2009-01-01

to the loudspeakers. In this paper we present a follow up evaluation of the performance of the three inversion techniques when these conditions are violated. A setup to measure the sweet spot of different loudspeakers arrangements is described. Preliminary measurement results are presented for loudspeakers placed...
75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

Science.gov (United States)

2010-01-07

...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.
Verification study on technology for preliminary investigation for HLW geological disposal. Part 2. Verification of surface geophysical prospecting through establishing site descriptive models

International Nuclear Information System (INIS)

Kondo, Hirofumi; Suzuki, Koichi; Hasegawa, Takuma; Goto, Keiichiro; Yoshimura, Kimitaka; Muramoto, Shigenori

2012-01-01

The Yokosuka demonstration and validation project using Yokosuka CRIEPI site has been conducted since FY 2006 as a cooperative research between NUMO (Nuclear Waste Management Organization of Japan) and CRIEPI. The objectives of this project are to examine and to refine the basic methodology of the investigation and assessment of properties of geological environment in the stage of Preliminary Investigation for HLW geological disposal. Within Preliminary Investigation technologies, surface geophysical prospecting is an important means of obtaining information from deep geological environment for planning borehole surveys. In FY 2010, both seismic prospecting (seismic reflection and vertical seismic profiling methods) for obtaining information about geological structure and electromagnetic prospecting (magneto-telluric and time domain electromagnetic methods) for obtaining information about resistivity structure reflecting the distribution of salt water/fresh water boundary to a depth of over several hundred meters were conducted in the Yokosuka CRIEPI site. Through these surveys, the contribution of geophysical prospecting methods in the surface survey stage to improving the reliability of site descriptive models was confirmed. (author)
Radiological risk assessment of a radioactively contaminated site

International Nuclear Information System (INIS)

Devgun, J.S.

1990-01-01

A limited-scope preliminary assessment of radiological risk has been conducted at a radioactively contaminated site under current site use conditions and based on the available preliminary radiological characterization data for the site. The assessment provides useful input to the remedial action planning for the site. 8 refs., 1 fig., 2 tabs
Soil structural analysis tools and properties for Hanford site waste tank evaluation

International Nuclear Information System (INIS)

Moore, C.J.; Holtz, R.D.; Wagenblast, G.R.; Weiner, E.D.; Marlow, R.S.

1995-09-01

As Hanford Site contractors address future structural demands on nuclear waste tanks, built as early as 1943, it is necessary to address their current safety margins and ensure safe margins are maintained. Although the current civil engineering practice guidelines for soil modeling are suitable as preliminary design tools, future demands potentially result in loads and modifications to the tanks that are outside the original design basis and current code based structural capabilities. For example, waste removal may include cutting a large hole in a tank. This report addresses both spring modeling of site soils and finite-element modeling of soils. Additionally seismic dynamic modeling of Hanford Site soils is also included. Of new and special interest is Section 2.2 that Professor Robert D. Holtz of the University of Washington wrote on plane strain soil testing versus triaxial testing with Hanford Site application to large buried waste tanks
Soil structural analysis tools and properties for Hanford site waste tank evaluation

Energy Technology Data Exchange (ETDEWEB)

Moore, C.J.; Holtz, R.D.; Wagenblast, G.R.; Weiner, E.D.; Marlow, R.S.

1995-09-01

As Hanford Site contractors address future structural demands on nuclear waste tanks, built as early as 1943, it is necessary to address their current safety margins and ensure safe margins are maintained. Although the current civil engineering practice guidelines for soil modeling are suitable as preliminary design tools, future demands potentially result in loads and modifications to the tanks that are outside the original design basis and current code based structural capabilities. For example, waste removal may include cutting a large hole in a tank. This report addresses both spring modeling of site soils and finite-element modeling of soils. Additionally seismic dynamic modeling of Hanford Site soils is also included. Of new and special interest is Section 2.2 that Professor Robert D. Holtz of the University of Washington wrote on plane strain soil testing versus triaxial testing with Hanford Site application to large buried waste tanks.
The disposal of Canada's nuclear fuel waste: site screening and site evaluation technology

International Nuclear Information System (INIS)

Davison, C.C.; Brown, A.; Everitt, R.A.; Gascoyne, M.; Kozak, E.T.; Lodha, G.S.; Martin, C.D.; Soonawala, N.M.; Stevenson, D.R.; Thorne, G.A.; Whitaker, S.H.

1994-06-01

The concept for the disposal of Canada's nuclear fuel waste is to dispose of the waste in an underground vault, nominally at 500 m to 1000 m depth, at a suitable site in plutonic rock of the Canadian Shield. The feasibility of this concept and assessments of its impact on the environment and human health, will be documented by AECL in an Environmental Impact Statement (EIS). This report is one of nine primary references for the EIS. It describes the approach and methods that would be used during the siting stage of the disposal project to identify a preferred candidate disposal site and to confirm its suitability for constructing a disposal facility. The siting stage is divided into two distinct but closely related substages, site screening and site evaluation. Site screening would mainly involve reconnaissance investigations of siting regions of the Shield to identify potential candidate areas where suitable vault locations are likely to exist. Site screening would identify a small number of candidate areas where further detailed investigations were warranted. Site evaluation would involve progressively more detailed surface and subsurface investigations of the candidate areas to first identify potentially suitable vault locations within the candidate areas, and then characterize these potential disposal sites to identify the preferred candidate location for constructing the disposal vault. Site evaluation would conclude with the construction of exploratory shafts and tunnels at the preferred vault location, and underground characterization would be done to confirm the suitability of the preferred candidate site. An integrated program of geological, geophysical, hydrogeological, geochemical and geomechanical investigations would be implemented to obtain the geoscience information needed to assess the suitability of the candidate siting areas and candidate sites for locating a disposal vault. The candidate siting areas and candidate disposal vault sites would be
Preliminary Performance Assessment for Disposal of APT and CLWR/TEF Wastes at SRS

International Nuclear Information System (INIS)

Wilhite, E.L.

1998-01-01

This section provides the descriptive information for understanding the analyses presented in this preliminary performance assessment. This section addresses the approach taken in the PA, provides a general description of the Savannah River Site E-Area low-level waste facility, and discusses the performance criteria used for evaluating performance
Preliminary evaluation of uranium deposits. A geostatistical study of drilling density in Wyoming solution fronts

International Nuclear Information System (INIS)

Sandefur, R.L.; Grant, D.C.

1976-01-01

Studies of a roll-front uranium deposit in Shirley Basin Wyoming indicate that preliminary evaluation of the reserve potential of an ore body is possible with less drilling than currently practiced in industry. Estimating ore reserves from sparse drilling is difficult because most reserve calculation techniques do not give the accuracy of the estimate. A study of several deposits with a variety of drilling densities shows that geostatistics consistently provides a method of assessing the accuracy of an ore reserve estimate. Geostatistics provides the geologist with an additional descriptive technique - one which is valuable in the economic assessment of a uranium deposit. Closely spaced drilling on past properties provides both geological and geometric insight into the occurrence of uranium in roll-front type deposits. Just as the geological insight assists in locating new ore bodies and siting preferential drill locations, the geometric insight can be applied mathematically to evaluate the accuracy of a new ore reserve estimate. By expressing the geometry in numerical terms, geostatistics extracts important geological characteristics and uses this information to aid in describing the unknown characteristics of a property. (author)
Gasbuggy Site Assessment and Risk Evaluation

Energy Technology Data Exchange (ETDEWEB)

None

2011-03-01

The Gasbuggy site is in northern New Mexico in the San Juan Basin, Rio Arriba County (Figure 1-1). The Gasbuggy experiment was designed to evaluate the use of a nuclear detonation to enhance natural gas production from the Pictured Cliffs Formation, a tight, gas-bearing sandstone formation. The 29-kiloton-yield nuclear device was placed in a 17.5-inch wellbore at 4,240 feet (ft) below ground surface (bgs), approximately 40 ft below the Pictured Cliffs/Lewis shale contact, in an attempt to force the cavity/chimney formed by the detonation up into the Pictured Cliffs Sandstone. The test was conducted below the southwest quarter of Section 36, Township 29 North, Range 4 West, New Mexico Principal Meridian. The device was detonated on December 10, 1967, creating a 335-ft-high chimney above the detonation point and a cavity 160 ft in diameter. The gas produced from GB-ER (the emplacement and reentry well) during the post-detonation production tests was radioactive and diluted, primarily by carbon dioxide. After 2 years, the energy content of the gas had recovered to 80 percent of the value of gas in conventionally developed wells in the area. There is currently no technology capable of remediating deep underground nuclear detonation cavities and chimneys. Consequently, the U.S. Department of Energy (DOE) must continue to manage the Gasbuggy site to ensure that no inadvertent intrusion into the residual contamination occurs. DOE has complete control over the 1/4 section (160 acres) containing the shot cavity, and no drilling is permitted on that property. However, oil and gas leases are on the surrounding land. Therefore, the most likely route of intrusion and potential exposure would be through contaminated natural gas or contaminated water migrating into a producing natural gas well outside the immediate vicinity of ground zero. The purpose of this report is to describe the current site conditions and evaluate the potential health risks posed by the most plausible
Preliminary site description. Simpevarp area - version 1.1

Energy Technology Data Exchange (ETDEWEB)

Winberg, Anders [ed.

2004-08-01

Site characterisation in the Oskarshamn area is currently conducted at two adjoining localities, the Simpevarp and Laxemar subareas. This report presents the interim version (model version Simpevarp 1.1 of S1.1 for short) of the preliminary Site Descriptive Model for the Simpevarp subarea. The basis for this interim version is quality-assured, geoscientific and ecological field data from the Simpevarp subarea (and in part from the Laxemar area) available in the SKB SICADA and GIS data bases as of July 1, 2003 as well as version 0 of the Site Descriptive Model. The new data collected during the initial site investigation phase up till the date of data freeze S1.1 constitute the basis for the update of version 0 to version S1.1. These data include results from surface investigations in the subarea with its regional environment and from drillings and investigations in boreholes. The surface-based data sets were, in a relative sense, extensive compared with data sets from boreholes, were the information largely was limited to information from one c. 1,000 m deep cored borehole (KSH01A), two existing cored boreholes and three c. 200 m deep percussion-drilled boreholes. Discipline-specific models are developed for the selected regional and local model volumes and these models are subsequently integrated into a unified site description. The current methodologies for developing discipline-specific models and their integration are documented in methodology/ strategy reports. In the present work, the procedures and guidelines given in those reports were followed to the extent possible given the data and information available at the time of data freeze for model version S1.1. Compared with version 0 there are considerable additional features in the version S1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and surface data of much higher
Preliminary site description. Simpevarp area - version 1.1

International Nuclear Information System (INIS)

Winberg, Anders

2004-08-01

Site characterisation in the Oskarshamn area is currently conducted at two adjoining localities, the Simpevarp and Laxemar subareas. This report presents the interim version (model version Simpevarp 1.1 of S1.1 for short) of the preliminary Site Descriptive Model for the Simpevarp subarea. The basis for this interim version is quality-assured, geoscientific and ecological field data from the Simpevarp subarea (and in part from the Laxemar area) available in the SKB SICADA and GIS data bases as of July 1, 2003 as well as version 0 of the Site Descriptive Model. The new data collected during the initial site investigation phase up till the date of data freeze S1.1 constitute the basis for the update of version 0 to version S1.1. These data include results from surface investigations in the subarea with its regional environment and from drillings and investigations in boreholes. The surface-based data sets were, in a relative sense, extensive compared with data sets from boreholes, were the information largely was limited to information from one c. 1,000 m deep cored borehole (KSH01A), two existing cored boreholes and three c. 200 m deep percussion-drilled boreholes. Discipline-specific models are developed for the selected regional and local model volumes and these models are subsequently integrated into a unified site description. The current methodologies for developing discipline-specific models and their integration are documented in methodology/ strategy reports. In the present work, the procedures and guidelines given in those reports were followed to the extent possible given the data and information available at the time of data freeze for model version S1.1. Compared with version 0 there are considerable additional features in the version S1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and surface data of much higher
Finite-element model evaluation of barrier configurations to reduce infiltration into waste-disposal structures: preliminary results and design considerations

International Nuclear Information System (INIS)

Lu, A.H.; Phillips, S.J.; Adams, M.R.

1982-09-01

Barriers to reduce infiltration into waste burial disposal structures (trenches, pits, etc.) may be required to provide adequate waste confinement. The preliminary engineering design of these barriers should consider interrelated barrier performance factors. This paper summarizes preliminary computer simulation activities to further engineering barrier design efforts. Several barrier configurations were conceived and evaluated. Models were simulated for each barrier configuration using a finite element computer code. Results of this preliminary evaluation indicate that barrier configurations, depending on their morphology and materials, may significantly influence infiltration, flux, drainage, and storage of water through and within waste disposal structures. 9 figures
10 CFR 960.3-1-5 - Basis for site evaluations.

Science.gov (United States)

2010-01-01

... comparative evaluations of sites in terms of the capabilities of the natural barriers for waste isolation and.... Comparative site evaluations shall place primary importance on the natural barriers of the site. In such... the sensitivity of the natural barriers to such realistic engineered barriers. For a better...

Geologic report for the Weldon Spring Raffinate Pits Site

International Nuclear Information System (INIS)

1984-10-01

A preliminary geologic site characterization study was conducted at the Weldon Spring Raffinate Pits Site, which is part of the Weldon Spring Site, in St. Charles County, Missouri. The Raffinate Pits Site is under the custody of the Department of Energy (DOE). Surrounding properties, including the Weldon Spring chemical plant, are under the control of the Department of the Army. The study determined the following parameters: site stratigraphy, lithology and general conditions of each stratigraphic unit, and groundwater characteristics and their relation to the geology. These parameters were used to evaluate the potential of the site to adequately store low-level radioactive wastes. The site investigation included trenching, geophysical surveying, borehole drilling and sampling, and installing observation wells and piezometers to monitor groundwater and pore pressures
Standard protocol for evaluation of environmental transfer factors around NPP sites

International Nuclear Information System (INIS)

Hegde, A.G.; Verma, P.C.; Rao, D.D.

2009-01-01

This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for evaluation of environmental transfer factors around NPP sites. The studies on transfer factors are being carried out at various NPP sites under DAE-BRNS projects for evaluation of site specific transfer factors for radionuclides released from power plants. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)
Development of a comprehensive management site evaluation methodology

International Nuclear Information System (INIS)

Rodgers, J.C.; Onishi, Y.

1981-01-01

The Nuclear Regulatory Commission is in the process of preparing regulations that will define the necessary conditions for adequate disposal of low-level waste (LLW) by confinement in an LLW disposal facility. These proposed regulations form the context in which the motivation for the joint Los Alamos National Laboratory Battelle Pacific Northwest Laboratory program to develop a site-specific, LLW site evaluation methodology is discussed. The overall effort is divided into three development areas: land-use evaluation, environmental transport modelling, and long term scenario development including long-range climatology projections. At the present time four steps are envisioned in the application of the methodology to a site: site land use suitability assessment, land use-ecosystem interaction, contaminant transport simulation, and sensitivity analysis. Each of these steps is discussed in the paper. 12 refs
Digital Discernment: An E-Commerce Web Site Evaluation Tool

Science.gov (United States)

Sigman, Betsy Page; Boston, Brian J.

2013-01-01

Students entering the business workforce today may well share some responsibility for developing, revising, or evaluating their company's Web site. They may lack the experience, however, to critique their employer's Web presence effectively. The purpose of developing Digital Discernment, an e-commerce Web site evaluation tool, was to prepare…
Treating Substance-Using Women and Their Children in Public Housing: Preliminary Evaluation Findings.

Science.gov (United States)

Metsch, Lisa R.; Wolfe, Harlan P.; Fewell, Rebecca; McCoy, Clyde B.; Elwood, William N.; Wohler-Torres, Brad; Petersen-Baston, Pamela; Haskins, Henry V.

2001-01-01

SafePort is a residential substance abuse treatment program within public housing to provide drug treatment to parenting women in Key West, Florida. All family members--women, children, and significant others--receive comprehensive assessments to determine appropriate therapeutic interventions. Preliminary evaluation findings suggest that women…
Preliminary results of a techno-economic assessment of CO2 capture-network configurations in the industry

NARCIS (Netherlands)

Berghout, N.A.; Kuramochi, T.; van den Broek, M.A.; Ramirez, C.A.; Faaij, A.P.C.

2013-01-01

This paper evaluated the techno economic performance of several CO2 capture-network configurations for a cluster of sixteen industrial plants in the Netherlands using bottom up analysis. Preliminary findings indicate that centralizing capture equipment instead of capture equipment at plant sites
Baseline risk assessment of groundwater contamination at the uranium mill tailings site, near Gunnison, Colorado. Revision 2

International Nuclear Information System (INIS)

1996-06-01

This report is the second site-specific risk assessment document prepared for the Ground Water Project at the Gunnison site. A preliminary risk assessment was conducted in 1990 to determine whether long-term use of ground water from private wells near the Gunnison site had the potential for adverse health effects. Due to the results of that preliminary risk assessment, the residents were provided bottled water on an interim basis. In July 1994, the residents and the nearby Valco cement/concrete plant were given the option to connect to anew alternate water supply system, eliminating the bottled water option. This document evaluates current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether more action is needed to protect human health and the environment and to comply with the EPA standards
Baseline risk assessment of groundwater contamination at the uranium mill tailings site, near Gunnison, Colorado. Revision 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

This report is the second site-specific risk assessment document prepared for the Ground Water Project at the Gunnison site. A preliminary risk assessment was conducted in 1990 to determine whether long-term use of ground water from private wells near the Gunnison site had the potential for adverse health effects. Due to the results of that preliminary risk assessment, the residents were provided bottled water on an interim basis. In July 1994, the residents and the nearby Valco cement/concrete plant were given the option to connect to anew alternate water supply system, eliminating the bottled water option. This document evaluates current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether more action is needed to protect human health and the environment and to comply with the EPA standards.
Binding and preclusive effect of part-construction permits and preliminary licenses

International Nuclear Information System (INIS)

Jarass, H.D.

1983-01-01

This contribution discusses the binding and preclusive effect of part-construction permits and preliminary licenses granted in accordance with the laws on air pollution abatement and the Atomic Energy Act. The author states that the granting of a part-construction permit must be based on a final decision over the entire project and must include a preliminary judgement and evaluation of the entire project, also covering site selection and design concept approval. The binding effort and preclusive effect of part-permits are examined in great detail, namely their definition, basic principles, extent, coming into force and term of validity and, (for the preclusive effect), its prerequisites, consequences, considerations regarding immediate execution). The author concludes by stating that there is no difference in regard to binding or preclusive effect between part-construction permits and a preliminary licence. (HP) [de
Preliminary shielding design evaluation for reactor assembly of SMART

International Nuclear Information System (INIS)

Kim, Kyo Youn; Kang, Chang M.; Kim, Ha Yong; Zee, Sung Quun; Chang, Moon Hee

1999-03-01

This report describes a preliminary evaluations of SMART shielding design near the reactor core by using the DORT two-dimensional discrete ordinates transport code. The results indicate that maximum neutron fluence at the bottom of reactor vessel is 1.64x10 17 n/cm 2 and that on the radial surface of reactor vessel is 6.71x10 16 n/cm 2 . These results meet the requirement, 1.0x10 20 n/cm 2 , in 10 CFR 50.61 and the integrity of SMART reactor vessel is confirmed during the lifetime of reactor. (Author). 20 refs., 11 tabs., 8 figs
Site locality identification study: Hanford Site. Volume II. Data cataloging

International Nuclear Information System (INIS)

1980-07-01

Data compilation and cataloging for the candidate site locality identification study were conducted in order to provide a retrievable data cataloging system for the present siting study and future site evaluation and licensng processes. This task occurred concurrently with and also independently of other tasks of the candidate site locality identification study. Work in this task provided the data utilized primarily in the development and application of screening and ranking processes to identify candidate site localities on the Hanford Site. The overall approach included two steps: (1) data acquisition and screening; and (2) data compilation and cataloging. Data acquisition and screening formed the basis for preliminary review of data sources with respect to their probable utilization in the candidate site locality identification study and review with respect to the level of completeness and detail of the data. The important working assumption was that the data to be used in the study be based on existing and available published and unpublished literature. The data compilation and cataloging provided the basic product of the Task; a retrievable data cataloging system in the form of an annotated reference list and key word index and an index of compiled data. The annotated reference list and key word index are cross referenced and can be used to trace and retrieve the data sources utilized in the candidate site locality identification study
A study of methodology and its applications for the evaluation of total system performance which considered the site-information and the design-information

International Nuclear Information System (INIS)

Inagaki, Manabu; Ebina, Takanori

2008-01-01

The step-by-step approach which chooses detailed investigation area(s) from the preliminary investigations area(s) in the volunteer sites is adopted on the high-level radioactive waste disposal in JAPAN. It's requested at the stage of chooses detailed investigation area that there are few fears that surf zone and groundwater stream exert bad influence on disposal facility as well as stability of the geological environment. In order to evaluate influence of groundwater stream, it is necessary to evaluate of total performance of disposal system with limited information from preliminary investigations and several design options which have been assumed on the generic geological environment. For a rational procedure of total system evaluation, it is essential to arrange of known information of the former performance evaluation, and so, when same part of those information was changed, we become able to pick a scenario, models, parameters with a possibility which changes out by tracing these information. In this study, as a first step, we carried out make a methodology to structure a flow of a series of information from a geological survey result in detail and until performance evaluation. We tried to make a structuralization of known information by base on this methodology. And, we discussed realistic performance of over-pack by tracing this structured information. (author)
Usability Evaluation of Public Web Mapping Sites

Science.gov (United States)

Wang, C.

2014-04-01

Web mapping sites are interactive maps that are accessed via Webpages. With the rapid development of Internet and Geographic Information System (GIS) field, public web mapping sites are not foreign to people. Nowadays, people use these web mapping sites for various reasons, in that increasing maps and related map services of web mapping sites are freely available for end users. Thus, increased users of web mapping sites led to more usability studies. Usability Engineering (UE), for instance, is an approach for analyzing and improving the usability of websites through examining and evaluating an interface. In this research, UE method was employed to explore usability problems of four public web mapping sites, analyze the problems quantitatively and provide guidelines for future design based on the test results. Firstly, the development progress for usability studies were described, and simultaneously several usability evaluation methods such as Usability Engineering (UE), User-Centered Design (UCD) and Human-Computer Interaction (HCI) were generally introduced. Then the method and procedure of experiments for the usability test were presented in detail. In this usability evaluation experiment, four public web mapping sites (Google Maps, Bing maps, Mapquest, Yahoo Maps) were chosen as the testing websites. And 42 people, who having different GIS skills (test users or experts), gender (male or female), age and nationality, participated in this test to complete the several test tasks in different teams. The test comprised three parts: a pretest background information questionnaire, several test tasks for quantitative statistics and progress analysis, and a posttest questionnaire. The pretest and posttest questionnaires focused on gaining the verbal explanation of their actions qualitatively. And the design for test tasks targeted at gathering quantitative data for the errors and problems of the websites. Then, the results mainly from the test part were analyzed. The
Preliminary evaluation of the air pollution in 2010; Luftbelastungssituation 2010. Vorlaeufige Auswertung. Hintergrund

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-01-25

In the contribution under consideration, the Federal Office for Environment Protection (Dessau-Rosslau, Federal Republic of Germany) evaluates the situation of air pollution in the year 2010 in comparison to the previous years. The evaluation is based on preliminary data and considers the pollutants fine dust (PM{sub 1}0), nitrogen dioxide and ozone. In 2010, these pollutants exceed the up-to-date valid limiting values for the protection of the human health.
Site-characterization data needs for hydrogeological evaluation

International Nuclear Information System (INIS)

Geier, J.

1997-12-01

A review of data utilization and data sufficiency for the multiple lines of hydrological analysis in the SITE-94 study yields insight regarding how site characterization relates to key uncertainties in geologic-barrier performance for performance assessment (PA). Significant uncertainties arise from (1) lack of data regarding interrelationships between hydraulic and transport properties in water-conducting features, (2) insufficient data to discriminate between different conceptual models for large-scale spatial correlation of hydraulic properties, and (3) inadequate determination of effective boundary conditions for site-scale models. For future site characterization in support of hydrological modelling for PA, recommendations that can be offered includes: (1) to develop methods for the evaluation of site-specific transport properties, particularly flow porosity, flow wetted surface, matrix diffusion coefficients, and possibly effective sorption coefficients, (2) to emphasize the use of multiple tracers and multiple scales of observation in pumping and tracer tests, in order to allow evaluation of the effects of scale and heterogeneity in hydrologic and transport properties, (3) to develop a structured, systematic approach to borehole investigations, sampling, and core logging, in order to ensure that the data thus gathered will support meaningful statistical analysis, and to ensure that the development of alternative conceptual models is supported, and finally (4) to improve documentation and checking of site-characterization data in order to avoid unnecessary introduction of uncertainty in PA. A full list of recommendations is given in Chapter 4 of this report
Site-characterization data needs for hydrogeological evaluation

Energy Technology Data Exchange (ETDEWEB)

Geier, J. [Clearwater Hardrock Consulting, Monmouth, ON (United States)

1997-12-01

A review of data utilization and data sufficiency for the multiple lines of hydrological analysis in the SITE-94 study yields insight regarding how site characterization relates to key uncertainties in geologic-barrier performance for performance assessment (PA). Significant uncertainties arise from (1) lack of data regarding interrelationships between hydraulic and transport properties in water-conducting features, (2) insufficient data to discriminate between different conceptual models for large-scale spatial correlation of hydraulic properties, and (3) inadequate determination of effective boundary conditions for site-scale models. For future site characterization in support of hydrological modelling for PA, recommendations that can be offered includes: (1) to develop methods for the evaluation of site-specific transport properties, particularly flow porosity, flow wetted surface, matrix diffusion coefficients, and possibly effective sorption coefficients, (2) to emphasize the use of multiple tracers and multiple scales of observation in pumping and tracer tests, in order to allow evaluation of the effects of scale and heterogeneity in hydrologic and transport properties, (3) to develop a structured, systematic approach to borehole investigations, sampling, and core logging, in order to ensure that the data thus gathered will support meaningful statistical analysis, and to ensure that the development of alternative conceptual models is supported, and finally (4) to improve documentation and checking of site-characterization data in order to avoid unnecessary introduction of uncertainty in PA. A full list of recommendations is given in Chapter 4 of this report. 31 refs.
Preliminary characterization of abandoned septic tank systems. Volume 1

International Nuclear Information System (INIS)

1995-12-01

This report documents the activities and findings of the Phase I Preliminary Characterization of Abandoned Septic Tank Systems. The purpose of the preliminary characterization activity was to investigate the Tiger Team abandoned septic systems (tanks and associated leachfields) for the purpose of identifying waste streams for closure at a later date. The work performed was not to fully characterize or remediate the sites. The abandoned systems potentially received wastes or effluent from buildings which could have discharged non-domestic, petroleum hydrocarbons, hazardous, radioactive and/or mixed wastes. A total of 20 sites were investigated for the preliminary characterization of identified abandoned septic systems. Of the 20 sites, 19 were located and characterized through samples collected from each tank(s) and, where applicable, associated leachfields. The abandoned septic tank systems are located in Areas 5, 12, 15, 25, and 26 on the Nevada Test Site
Transforming Pinus pinaster forest to recreation site: preliminary effects on LAI, some forest floor, and soil properties.

Science.gov (United States)

Öztürk, Melih; Bolat, İlyas

2014-04-01

This study investigates the effects of forest transformation into recreation site. A fragment of a Pinus pinaster plantation forest was transferred to a recreation site in the city of Bartın located close to the Black Sea coast of northwestern Turkey. During the transformation, some of the trees were selectively removed from the forest to generate more open spaces for the recreationists. As a result, Leaf Area Index (LAI) decreased by 0.20 (about 11%). Additionally, roads and pathways were introduced into the site together with some recreational equipment sealing parts of the soil surface. Consequently, forest environment was altered with a semi-natural landscape within the recreation site. The purpose of this study is to assess the effects of forest transformation into recreation site particularly in terms of the LAI parameter, forest floor, and soil properties. Preliminary monitoring results indicate that forest floor biomass is reduced by 26% in the recreation site compared to the control site. Soil temperature is increased by 15% in the recreation site where selective removal of trees expanded the gaps allowing more light transmission. On the other hand, the soil bulk density which is an indicator of soil compaction is unexpectedly slightly lower in the recreation site. Organic carbon (C(org)) and total nitrogen (N(total)) together with the other physical and chemical parameter values indicate that forest floor and soil have not been exposed to much disturbance. However, subsequent removal of trees that would threaten the vegetation, forest floor, and soil should not be allowed. The activities of the recreationists are to be concentrated on the paved spaces rather than soil surfaces. Furthermore, long-term monitoring and management is necessary for both the observation and conservation of the site.
Small scale hydroelectric power potential in Nevada: a preliminary reconnaissance survey

Energy Technology Data Exchange (ETDEWEB)

Cochran, G.F.; Fordham, J.W.; Richard, K.; Loux, R.

1981-04-01

This preliminary reconnaissance survey is intended to: develop a first estimate as to the potential number, location and characteristics of small-scale (50 kW to 15 MW) hydroelectric sites in Nevada; provide a compilation of various Federal and state laws and regulations, including tax and financing regulations, that affect small-scale hydroelectric development and provide information on sources of small-scale hydroelectric generation hardware and consultants/ contractors who do small scale hydroelectric work. The entire survey has been conducted in the office working with various available data bases. The site survey and site evaluation methods used are described, and data are tabulated on the flow, power potential, predicted capital expenditures required, etc. for 61 potential sites with measured flows and for 77 sites with derived flows. A map showing potential site locations is included. (LCL)
Preliminary Information on the Vertebrate Fauna (Animalia: Vertebrata of the NATURA2000 Site “Rice Fields Tsalapitsa” (Bulgaria

Directory of Open Access Journals (Sweden)

Ivayla L. Klimentova

2011-12-01

Full Text Available The study was carried out by tree visits in different areas of the Natura 2000 site “Rice Fields Tsalapitsa” BG 0002086 (West of Plovdiv city, near village of Tsalapitsa. Our preliminary research showed that in the area vertebrates with high conservation status occurred included in the Bulgarian Bidiversity Act, Appendix II and III, Appendix II of the Bern convention, Natura 2000 species list, the Bonn convention, Appendix II, the Convention of the International Trade of Endangered Species, and the list of the International Union for Conservation of the Nature. This information will help in future preparation of the management plan of the Natura 2000 site and showed the need of studies focused on such areas which will help undertaking adequate measures for their proper way of conservation.

Implications of the timing of the preliminary determination of suitability

International Nuclear Information System (INIS)

Cotton, T.A.

1986-01-01

The Nuclear Waste Policy Act of 1982 requires that the Enviromental Impact Statement prepared for the recommendation of a repository site must consider three sites -- the one selected for the repository and at least two alternatives. All of these sites must have been characterized, and the Secretary of Energy must have made a preliminary determination that each is suitable for development as a repository. There is great disagreement about whether that ''preliminary determination of suitability'' is to be made before or after site characterization. If the Act is interpreted as requiring the determination to be made after characterization is completed, DOE cannot recommend the first site for licensing until it has three sites that appear suitable after full characterization; if the determination can be made before characterization, DOE can proceed to licensing even if only one site survives characterization. While DOE plans to make the preliminary determination before starting characterization, the uncertainty about how a court might ultimately interpret the Act injects a significant institutional uncertainty into the schedule for the repository, and complicates contingency planning for the siting process. Early resolution of the interpretation would greatly aid DOE's planning for the siting program
Evaluation of the preliminary auditory profile test battery in an international multi-centre study

NARCIS (Netherlands)

van Esch, T.E.M.; Kollmeier, B.; Vormann, M.; Lijzenga, J.; Houtgast, T.; Hallgren, M.; Larsby, B.; Athalye, S.P.; Lutman, M.E.; Dreschler, W.A.

2013-01-01

Objective: This paper describes the composition and international multi-centre evaluation of a battery of tests termed the preliminary auditory profile. It includes measures of loudness perception, listening effort, speech perception, spectral and temporal resolution, spatial hearing, self-reported
On-site transportation and handling of uranium-233 special nuclear material: Preliminary hazards and accident analysis. Final

International Nuclear Information System (INIS)

Solack, T.; West, D.; Ullman, D.; Coppock, G.; Cox, C.

1995-01-01

U-233 Special Nuclear Material (SNM) currently stored at the T-Building Storage Areas A and B must be transported to the SW/R Tritium Complex for repackaging. This SNM is in the form of oxide powder contained in glass jars which in turn are contained in heat sealed double polyethylene bags. These doubled-bagged glass jars have been primarily stored in structural steel casks and birdcages for approximately 20 years. The three casks, eight birdcages, and one pail/pressure vessel will be loaded onto a transport truck and moved over an eight day period. The Preliminary Hazards and Accident Analysis for the on-site transportation and handling of Uranium-233 Special Nuclear Material, documented herein, was performed in accordance with the format and content guidance of DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, dated July 1994, specifically Chapter Three, Hazard and Accident Analysis. The Preliminary Hazards Analysis involved detailed walkdowns of all areas of the U-233 SNM movement route, including the T-Building Storage Area A and B, T-Building truck tunnel, and the roadway route. Extensive discussions were held with operations personnel from the Nuclear Material Control Group, Nuclear Materials Accountability Group, EG and G Mound Security and the Material Handling Systems Transportation Group. Existing documentation related to the on-site transportation of hazardous materials, T-Building and SW/R Tritium Complex SARs, and emergency preparedness/response documentation were also reviewed and analyzed to identify and develop the complete spectrum of energy source hazards
Power plant site evaluation - Douglas Point site. Volume 1, part 2. Final report

International Nuclear Information System (INIS)

1977-11-01

This is part of a series of reports containing an evaluation of the proposed Douglas Point nuclear generating station site located on the Potomac River in Maryland 30 miles south of Washington, DC. This report contains sections on cooling tower air emissions, noise impacts, transmission line effects, radiation from normal releases, site features affecting radiological accidents, and meteorology
Siting Process for HLW Repository in Japan

International Nuclear Information System (INIS)

Masuda, S.; Kitayama, K.; Umeki, H.; Naito, M.

2002-01-01

In the year 2000, the geological disposal program for high-level radioactive waste in Japan moved from the phase of generic research and development (R and D) into the phase of implementation. Following legislation entitled the ''Specified Radioactive Waste Final Disposal Act'', the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization. The assigned activities of NUMO include selection of the repository site, demonstration of disposal technology at the site, developing relevant licensing applications and construction, operation and closure of the repository. As the first milestone of siting process, NUMO announced to the public an overall procedure for selection of preliminary investigation areas for potential candidate sites on October 29, 2001. The procedure specifies that NUMO will solicit volunteer municipalities for preliminary investigation areas with publishing four documents as an information package. These documents are tentatively entitled ''Instructions for Application'', ''Siting Factors for the Preliminary Investigation Areas'', a ''Repository Concepts'' as well as an ''Site Investigation Community Outreach Scheme''
Ex-vessel core catcher design requirements and preliminary concepts evaluation

International Nuclear Information System (INIS)

Friedland, A.J.; Tilbrook, R.W.

1974-01-01

As part of the overall study of the consequences of a hypothetical failure to scram following loss of pumping power, design requirements and preliminary concepts evaluation of an ex-vessel core catcher (EVCC) were performed. EVCC is the term applied to a class of devices whose primary objective is to provide a stable subcritical and coolable configuration within containment following a postulated accident in which it is assumed that core debris has penetrated the Reactor Vessel and Guard Vessel. Under these assumed conditions a set of functional requirements were developed for an EVCC and several concepts were evaluated. The studies were specifically directed toward the FFTF design considering the restraints imposed by the physical design and construction of the FFTF plant
Site Study Plan for salt, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

The Salt Site Study Plan (SSP) describes a program for characterizing the existing salt environment in the site vicinity. A step-by-step approach is described which proceeds from published data and planned theoretical studies, to planned laboratory studies, and finally to planned field studies, to provide the necessary data to meet program requirements contained in the Salt Repository Project - Requirements Document (SRP-RD). The plan also draws on the results of other SSP's for certain data; for example, soil salinity data are to be provided under the Soils SSP. The salt studies consist of evaluation of control and mitigation measures, salt monitoring studies, emission factors development, air models development and validation, and risk assessment. For each study, its design and design rationale; analysis, management, and use of data; schedule of activities; organization of personnel and sample management; and quality assurance requirements are described. 90 refs., 9 figs., 7 tabs
Preliminary identification of potentially disruptive scenarios at the Greater Confinement Disposal Facility, Area 5 of the Nevada Test Site

International Nuclear Information System (INIS)

Guzowski, R.V.; Newman, G.

1993-12-01

The Greater Confinement Disposal location is being evaluated to determine whether defense-generated transuranic waste buried at this location complies with the Containment Requirements established by the US Environmental Protection Agency. One step in determining compliance is to identify those combinations of events and processes (scenarios) that define possible future states of the disposal system for which performance assessments must be performed. An established scenario-development procedure was used to identify a comprehensive set of mutually exclusive scenarios. To assure completeness, 761 features, events, processes, and other listings (FEPS) were compiled from 11 references. This number was reduced to 205 primarily through the elimination of duplications. The 205 FEPs were screened based on site-specific, goal-specific, and regulatory criteria. Four events survived screening and were used in preliminary scenario development: (1) exploratory drilling penetrates a GCD borehole, (2) drilling of a withdrawal/injection well penetrates a GCD borehole, (3) subsidence occurs at the RWMS, and (4) irrigation occurs at the RWMS. A logic diagram was used to develop 16 scenarios from the four events. No screening of these scenarios was attempted at this time. Additional screening of the currently retained events and processes will be based on additional data and information from site-characterization activities. When screening of the events and processes is completed, a final set of scenarios will be developed and screened based on consequence and probability of occurrence
A Preliminary Evaluation of Reach: Training Early Childhood Teachers to Support Children's Social and Emotional Development

Science.gov (United States)

Conners-Burrow, Nicola A.; Patrick, Terese; Kyzer, Angela; McKelvey, Lorraine

2017-01-01

This paper describes the development, implementation and preliminary evaluation of the Reaching Educators and Children (REACH) program, a training and coaching intervention designed to increase the capacity of early childhood teachers to support children's social and emotional development. We evaluated REACH with 139 teachers of toddler and…
Preliminary fiscal evaluation of Alberta oil sands terms

International Nuclear Information System (INIS)

Van Meurs, P.

2007-01-01

The cost of oil sands projects varies significantly. While costs have escalated considerably over the past few years, oil prices have gone significantly higher. This report provided an economic evaluation of the current fiscal terms applicable to Alberta oil sands. The analysis was done to evaluate the profitability of oil sand projects to investors under current conditions based on the generic royalty regime based on bitumen values. The objective of the royalty review was to determine whether Albertans received a fair share from their oil and gas resources. It discussed the wide variety of oil sands projects in Alberta using five case studies as examples. Cases involving steam assisted gravity drainage (SAGD) operations were assessed for both the Athabasca Mine and Cold Lake. The report provided a discussion of the economic assumptions including economic cases as well as production, costs and price data. It then provided the preliminary results of the economic-fiscal evaluation from the investor perspective including profitability indicators; international comparisons; internal rate of return; and net present value. The government perspective was also discussed with reference to attractiveness indicators; royalties as a percentage of bitumen values; and non-discounted and discounted government take. A royalty and tax feature analysis was also provided. Several issues for possible further review were also presented. tabs
Development and Reliability of a Preliminary Foot Osteoarthritis Magnetic Resonance Imaging Score.

Science.gov (United States)

Halstead, Jill; Martín-Hervás, Carmen; Hensor, Elizabeth M A; McGonagle, Dennis; Keenan, Anne-Maree; Redmond, Anthony C; Conaghan, Philip G

2017-08-01

Foot osteoarthritis (OA) is very common but underinvestigated musculoskeletal condition and there is little consensus as to common magnetic resonance imaging (MRI) features. The aim of this study was to develop a preliminary foot OA MRI score (FOAMRIS) and evaluate its reliability. This preliminary semiquantitative score included the hindfoot, midfoot, and metatarsophalangeal joints. Joints were scored for joint space narrowing (JSN; 0-3), osteophytes (0-3), joint effusion/synovitis, and bone cysts (present/absent). Erosions and bone marrow lesions (BML) were scored (0-3) and BML were evaluated adjacent to entheses and at sub-tendon sites (present/absent). Additionally, tenosynovitis (0-3) and midfoot ligament pathology (present/absent) were scored. Reliability was evaluated in 15 people with foot pain and MRI-detected OA using 3.0T MRI multi-sequence protocols, and assessed using ICC as an overall score and per anatomical site. Intrareader agreement (ICC) was generally good to excellent across the foot in joint features (JSN 0.90, osteophytes 0.90, effusion/synovitis 0.46, cysts 0.87), bone features (BML 0.83, erosion 0.66, BML entheses 0.66, BML sub-tendon 0.60) and soft tissue features (tenosynovitis 0.83, ligaments 0.77). Interreader agreement was lower for joint features (JSN 0.43, osteophytes 0.27, effusion/synovitis 0.02, cysts 0.48), bone features (BML 0.68, erosion 0.00, BML entheses 0.34, BML sub-tendon 0.13), and soft tissue features (tenosynovitis 0.35, ligaments 0.33). This preliminary FOAMRIS demonstrated good intrareader reliability and fair interreader reliability when assessing the total feature scores. Further development is required in cohorts with a range of pathologies and to assess the psychometric measurement properties.
Methods of Identification and Evaluation of Brownfield Sites

Directory of Open Access Journals (Sweden)

Safet Kurtović

2014-04-01

Full Text Available The basic objective of this paper was to determine the importance and potential restoration of brownfield sites in terms of economic prosperity of a particular region or country. In addition, in a theoretical sense, this paper presents the methods used in the identification of brownfield sites such as Smart Growth Network model and Thomas GIS model, and methods for evaluation of brownfield sites or the indexing method, cost-benefit and multivariate analysis.
Preliminary data report of investigations conducted at the Salmon Site, Lamar County, Mississippi

International Nuclear Information System (INIS)

1994-04-01

The US Department of Energy (DOE) conducted ecological studies at the Salmon Site (SS), Lamar County, Mississippi, from the middle of June 1992 to the end of April 1993. The studies are part of the Remedial Investigation and Feasibility Study (RI/FS) being conducted by the DOE. The RI/FS is the methodology under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986 (CERCLA/SARA) for evaluating hazardous waste sites on the National Priorities List (NPL). The Salmon Site is not listed on the NPL but DOE has voluntarily elected to conduct the evaluation of the SS in accordance with CERCLA/SARA. As part of the remedial investigation, baseline human health and ecological risk assessments will be conducted. These baseline risk assessments will evaluate the potential impact on human health and the environment if remedial actions are not conducted, identify locations where additional information needs to be collected, help determine whether remedial actions are necessary, and provide justification for performing remedial actions. This report describes the sampling activities conducted between February and April 1993 to aid in evaluating the possible environmental impacts at the SS tailored to the specific circumstances and conditions found there. The initial investigations included identification of the flora and fauna in and around the SS, with particular emphasis on identifying sensitive environments, endangered species and their habitats, and those species consumed by humans or found in human food chains
Management and Data Management Plan for Remedial Investigation at Fort George G. Meade Landfill and Preliminary Assessment/Site Investigation at the Former Gaithersburg NIKE Control and Launch Areas

National Research Council Canada - National Science Library

Edwards, D

1989-01-01

Work assignments under this contract will include a Preliminary Assessment/Site Investigation at the former Gaithersburg NIKE Control and Launch Areas and a Remedial Investigation at the Fort Meade...
Field Demonstration of Ground-Source Integrated Heat Pump Part I. Technology and Field Demo System/Site Descriptions, and Preliminary Summer/Fall Performance Analysis for One Site

Energy Technology Data Exchange (ETDEWEB)

Baxter, Van D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Munk, Jeffrey D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gehl, Anthony C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-02-01

The field study is planned to continue through the 2016 cooling season with the draft final project report due by September 30, 2016. This report provides a description of both installations and preliminary 2015 cooling and fall season performance results for the Knoxville site. For the August 18 through December 14 period, the Knoxville site GS-IHP provided 53.6% total source energy savings compared to a baseline electric RTU/heat pump and electric WH. Peak demand savings ranged from 33% to 59% per month. Energy cost savings of 53.1% have been achieved to date with more than half of that coming from reduced demand charges. Data on installation and maintenance costs are being collected and will be combined with total test period energy savings data for a payback analysis to be included in the project final report. The GS-IHP also saved a significant amount of carbon emissions. The total emission savings for the Knoxville site for the August-December 2015 period were ~0.8 metric tons. If trading for carbon credits ever becomes a reality, additional cost savings would be realized.
Evaluation of high pressure Freon decontamination. I. Preliminary tests

International Nuclear Information System (INIS)

Rankin, W.N.

1983-01-01

High-pressure Freon blasting techniques are being evaluated for applications involving the removal of non-adherent radioactive particulate contamination at SRP. Very little waste is generated by this technique because the used Freon can be easily distilled and reused. One of the principle advantages of this technique is that decontaminated electrical equipment can be returned to service immediately without drying, unlike high-pressure water blasting techniques. Preliminary scoutin tests evaluating high-pressure Freon blasting for decontamination at SRP were carried out at Quadrex Co., Oak Ridge, TN, October 12 and 13. DWPF-type contamination (raw sludge plus volatiles) and separations area-type contamination (diluted boiling point (47.6 0 C) allow it to rapidly separate from higher boiling contaminants via distillation with filtration to remove particulate material, and distillation with condensation, the solvent may be recovered for indefinite reuse while reducing the radioactive waste to a minimum. 3 references, 5 figures, 6 tables
Intra-site Secure Transport Vehicle test and evaluation

International Nuclear Information System (INIS)

Scott, S.

1995-01-01

In the past many DOE and DoD facilities involved in handling nuclear material realized a need to enhance the safely and security for movement of sensitive materials within their facility, or ''intra-site''. There have been prior efforts to improve on-site transportation; however, there remains a requirement for enhanced on-site transportation at a number of facilities. The requirements for on-site transportation are driven by security, safety, and operational concerns. The Intra-site Secure Transport Vehicle (ISTV) was designed to address these concerns specifically for DOE site applications with a standardized vehicle design. This paper briefly reviews the ISTV design features providing significant enhancement of onsite transportation safety and security, and also describes the test and evaluation activities either complete of underway to validate the vehicle design and operation
Framework for DOE mixed low-level waste disposal: Site fact sheets

Energy Technology Data Exchange (ETDEWEB)

Gruebel, M.M.; Waters, R.D.; Hospelhorn, M.B.; Chu, M.S.Y. [eds.

1994-11-01

The Department of Energy (DOE) is required to prepare and submit Site Treatment Plans (STPS) pursuant to the Federal Facility Compliance Act (FFCAct). Although the FFCAct does not require that disposal be addressed in the STPS, the DOE and the States recognize that treatment of mixed low-level waste will result in residues that will require disposal in either low-level waste or mixed low-level waste disposal facilities. As a result, the DOE is working with the States to define and develop a process for evaluating disposal-site suitability in concert with the FFCAct and development of the STPS. Forty-nine potential disposal sites were screened; preliminary screening criteria reduced the number of sites for consideration to twenty-six. The DOE then prepared fact sheets for the remaining sites. These fact sheets provided additional site-specific information for understanding the strengths and weaknesses of the twenty-six sites as potential disposal sites. The information also provided the basis for discussion among affected States and the DOE in recommending sites for more detailed evaluation.
Preliminary design for a maglev development facility

Energy Technology Data Exchange (ETDEWEB)

Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. (Argonne National Lab., IL (United States)); Zhang, Z.Y. (Polytechnic Univ., Brooklyn, NY (United States)); Myers, G.; Cvercko, A. (Sterling Engineering, Westchester, IL (United States)); Williams, J.R. (Alfred Benesch and Co., Chicago, IL (United States))

1992-04-01

A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.
Site Response Analysis Using DeepSoil: Case Study of Bangka Site, Indonesia

Energy Technology Data Exchange (ETDEWEB)

Iswanto, Eko Rudi; Yee, Eric [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2015-10-15

Indonesia government declared through Act No. 17 year 2007 on the National Long-Term Development Plant Year 2005-2025 and Presidential Decree No. 5 year 2006 on the National Energy Policy (Indonesia 2007; Indonesia 2006), that nuclear energy is stated as a part of the national energy system. In order to undertake the above national policy, National Nuclear Energy Agency of Indonesia, as the promotor for the utilization of nuclear energy will conduct site study, which is a part of infrastructure preparation for NPP construction. Thorough preparation and steps are needed to operate an NPP and it takes between 10 to 15 years from the preliminary study (site selection, financial study, etc.) up to project implementation (manufacturing, construction, commissioning). During project implementation, it is necessary to prepare various documents relevant for permit application such as Safety Evaluation Report for site permit, Preliminary Safety Analysis Report and Environment Impact Assessment Report for construction permit. Considering the continuously increasing electricity energy demand, it is necessary to prepare for alternative NPP sites. The safety requirements of NPP's are stringent; amongst the various requirements is the ability to safely shut down in the wake of a possible earthquake. Ground response analysis of a potential site therefore needs to be carried out, parameter that affect the resistance of an NPP to earthquakes such as peak strain profiles is analysed. The objective of this paper is to analyse the ground response of the selected site for a NPP, using The Mw 7.9 in Sikuai Island, West Sumatra on September 12, 2007 as present input motion. This analysis will be carried out using a ground response analysis program, DeepSoil. In addition to this, an attempt was made to define the site specific input motion characteristics of the selected site for use in DeepSoil (DeepSoil 5.0). A site investigation at the WB site was performed primarily on the PS

Structuring a cost-effective site characterization

International Nuclear Information System (INIS)

Berven, B.A.; Little, C.A.; Swaja, R.E.

1990-01-01

Successful chemical and radiological site characterizations are complex activities which require meticulously detailed planning. Each layer of investigation is based upon previously generated information about the site. Baseline historical, physical, geological, and regulatory information is prerequisite for preliminary studies at a site. Preliminary studies then provide samples and measurements which define the identity of potential contaminants and define boundaries around the area to be investigated. The goal of a full site characterization is to accurately determine the extent and magnitude of contaminants and carefully define the site conditions such that the future movements of site contaminants can be assessed for potential exposure to human occupants and/or environmental impacts. Critical to this process is the selection of appropriate measurement and sampling methodology, selection and use of appropriate instrumentation and management/interpretation of site information. Site investigations require optimization between the need of information to maximize the understanding of site conditions and the cost of acquiring that information. 5 refs., 1 tab
Site Selection for Hvdc Ground Electrodes

Science.gov (United States)

Freire, P. F.; Pereira, S. Y.

2014-12-01

High-Voltage Direct Current (HVDC) transmission systems are composed of a bipole transmission line with a converter substation at each end. Each substation may be equipped with a HVDC ground electrode, which is a wide area (up to 1 km Ø) and deep (from 3 to 100m) electrical grounding. When in normal operation, the ground electrode will dissipate in the soil the unbalance of the bipole (~1.5% of the rated current). When in monopolar operation with ground return, the HVDC electrode will inject in the soil the nominal pole continuous current, of about 2000 to 3000 Amperes, continuously for a period up to a few hours. HVDC ground electrodes site selection is a work based on extensive geophysical and geological surveys, in order to attend the desired design requirements established for the electrodes, considering both its operational conditions (maximum soil temperature, working life, local soil voltage gradients etc.) and the interference effects on the installations located up to 50 km away. This poster presents the geophysical investigations conducted primarily for the electrodes site selection, and subsequently for the development of the crust resistivity model, which will be used for the interference studies. A preliminary site selection is conducted, based on general geographical and geological criteria. Subsequently, the geology of each chosen area is surveyed in detail, by means of electromagnetic/electrical geophysical techniques, such as magnetotelluric (deep), TDEM (near-surface) and electroresistivity (shallow). Other complementary geologic and geotechnical surveys are conducted, such as wells drilling (for geotechnical characterization, measurement of the water table depth and water flow, and electromagnetic profiling), and soil and water sampling (for measurement of thermal parameters and evaluation of electrosmosis risk). The site evaluation is a dynamic process along the surveys, and some sites will be discarded. For the two or three final sites, the
Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-01-01

The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of senior YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document.
Preliminary site description Forsmark area - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Skagius, Kristina [ed.

2005-06-01

The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in
Preliminary site description Forsmark area - version 1.2

International Nuclear Information System (INIS)

Skagius, Kristina

2005-06-01

The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in
Seismic Hazard Assessment in Site Evaluation for Nuclear Installations: Ground Motion Prediction Equations and Site Response

International Nuclear Information System (INIS)

2016-07-01

The objective of this publication is to provide the state-of-the-art practice and detailed technical elements related to ground motion evaluation by ground motion prediction equations (GMPEs) and site response in the context of seismic hazard assessments as recommended in IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations. The publication includes the basics of GMPEs, ground motion simulation, selection and adjustment of GMPEs, site characterization, and modelling of site response in order to improve seismic hazard assessment. The text aims at delineating the most important aspects of these topics (including current practices, criticalities and open problems) within a coherent framework. In particular, attention has been devoted to filling conceptual gaps. It is written as a reference text for trained users who are responsible for planning preparatory seismic hazard analyses for siting of all nuclear installations and/or providing constraints for anti-seismic design and retrofitting of existing structures
Preliminary data evaluation for thermal insulation characterization testing

International Nuclear Information System (INIS)

DeClue, J.F.; Moses, S.D.; Tollefson, D.A.

1991-01-01

The purpose of Thermal Insulation Characterization Testing is to provide physical data to support certain assumptions and calculational techniques used in the criticality safety calculations in Section 6 of the Safety Analysis Reports for Packaging (SARPs) for drum-type packaging for Department of Energy's (DOE) Oak Ridge Y-12 Plant, managed by Martin Marietta Energy Systems, Inc. Results of preliminary data evaluation regarding the fire-test condition reveal that realistic weight loss consideration and residual material characterization in developing calculational models for the hypothetical accident condition is necessary in order to prevent placement of unduly conservative restrictions on shipping requirements as a result of overly conservative modeling. This is particularly important for fast systems. Determination of the geometric arrangement of residual material is of secondary importance. Both the methodology used to determine the minimum thermal insulation mass remaining after the fire test and the treatment of the thermal insulation in the criticality safety calculational models requires additional evaluation. Specific testing to be conducted will provide experimental data with which to validate the mass estimates and calculational modeling techniques for extrapolation to generic drum-type containers
Partitioning planning studies: Preliminary evaluation of metal and radionuclide partitioning the high-temperature thermal treatment systems

International Nuclear Information System (INIS)

Liekhus, K.; Grandy, J.; Chambers, A.

1997-03-01

A preliminary study of toxic metals and radionuclide partitioning during high-temperature processing of mixed waste has been conducted during Fiscal Year 1996 within the Environmental Management Technology Evaluation Project. The study included: (a) identification of relevant partitioning mechanisms that cause feed material to be distributed between the solid, molten, and gas phases within a thermal treatment system; (b) evaluations of existing test data from applicable demonstration test programs as a means to identify and understand elemental and species partitioning; and, (c) evaluation of theoretical or empirical partitioning models for use in predicting elemental or species partitioning in a thermal treatment system. This preliminary study was conducted to identify the need for and the viability of developing the tools capable of describing and predicting toxic metals and radionuclide partitioning in the most applicable mixed waste thermal treatment processes. This document presents the results and recommendations resulting from this study that may serve as an impetus for developing and implementing these predictive tools
Partitioning planning studies: Preliminary evaluation of metal and radionuclide partitioning the high-temperature thermal treatment systems

Energy Technology Data Exchange (ETDEWEB)

Liekhus, K.; Grandy, J.; Chambers, A. [and others

1997-03-01

A preliminary study of toxic metals and radionuclide partitioning during high-temperature processing of mixed waste has been conducted during Fiscal Year 1996 within the Environmental Management Technology Evaluation Project. The study included: (a) identification of relevant partitioning mechanisms that cause feed material to be distributed between the solid, molten, and gas phases within a thermal treatment system; (b) evaluations of existing test data from applicable demonstration test programs as a means to identify and understand elemental and species partitioning; and, (c) evaluation of theoretical or empirical partitioning models for use in predicting elemental or species partitioning in a thermal treatment system. This preliminary study was conducted to identify the need for and the viability of developing the tools capable of describing and predicting toxic metals and radionuclide partitioning in the most applicable mixed waste thermal treatment processes. This document presents the results and recommendations resulting from this study that may serve as an impetus for developing and implementing these predictive tools.
Hanford Site background: Evaluation of existing soil radionuclide data

International Nuclear Information System (INIS)

1995-07-01

This report is an evaluation of the existing data on radiological background for soils in the vicinity of the Hanford Site. The primary purpose of this report is to assess the adequacy of the existing data to serve as a radiological background baseline for use in environmental restoration and remediation activities at the Hanford Site. The soil background data compiled and evaluated in this report were collected by the Pacific Northwest Laboratory (PNL) and Washington State Department of Health (DOH) radiation surveillance programs in southeastern Washington. These two programs provide the largest well-documented, quantitative data sets available to evaluate background conditions at the Hanford Site. The data quality objectives (DQOs) considered in this evaluation include the amount of data, number of sampling localities, spatial coverage, number and types of radionuclides reported, frequency of reporting, documentation and traceability of sampling and laboratory methods used, and comparability between sets of data. Although other data on soil radionuclide abundances around the Hanford Site exist, they are generally limited in scope and lack the DQOs necessary for consideration with the PNL and DOH data sets. Collectively, these two sources provide data on the activities of 25 radionuclides and four other parameters (gross alpha, gross beta, total uranium, and total thorium). These measurements were made on samples from the upper 2.5 cm of soil at over 70 localities within the region
An evaluation of the behaviour-change techniques used on Canadian cancer centre Web sites to support physical activity behaviour for breast cancer survivors.

Science.gov (United States)

Sylvester, B D; Zammit, K; Fong, A J; Sabiston, C M

2017-12-01

Cancer centre Web sites can be a useful tool for distributing information about the benefits of physical activity for breast cancer (bca) survivors, and they hold potential for supporting health behaviour change. However, the extent to which cancer centre Web sites use evidence-based behaviour change techniques to foster physical activity behaviour among bca survivors is currently unknown. The aim of our study was to evaluate the presentation of behaviour-change techniques on Canadian cancer centre Web sites to promote physical activity behaviour for bca survivors. All Canadian cancer centre Web sites ( n = 39) were evaluated by two raters using the Coventry, Aberdeen, and London-Refined (calo-re) taxonomy of behaviour change techniques and the eEurope 2002 Quality Criteria for Health Related Websites. Descriptive statistics were calculated. The most common behaviour change techniques used on Web sites were providing information about consequences in general (80%), suggesting goal-setting behaviour (56%), and planning social support or social change (46%). Overall, Canadian cancer centre Web sites presented an average of M = 6.31 behaviour change techniques (of 40 that were coded) to help bca survivors increase their physical activity behaviour. Evidence of quality factors ranged from 90% (sites that provided evidence of readability) to 0% (sites that provided an editorial policy). Our results provide preliminary evidence that, of 40 behaviour-change techniques that were coded, fewer than 20% were used to promote physical activity behaviour to bca survivors on cancer centre Web sites, and that the most effective techniques were inconsistently used. On cancer centre Web sites, health promotion specialists could focus on emphasizing knowledge mobilization efforts using available research into behaviour-change techniques to help bca survivors increase their physical activity.
Evaluating biological transport of radionuclides at low-level waste burial sites

International Nuclear Information System (INIS)

Cadwell, L.L.; Kennedy, W.E.; McKenzie, D.H.

1983-08-01

The purpose of the work reported here is to develop and demonstrate methods for evaluating the long-term impact of biological processes at low-level waste (LLW) disposal sites. As part of this effort, we developed order-of-magnitude estimates of dose-to-man resulting from animal burrowing activity and plant translocation of radionuclides. Reference low-level waste sites in both arid and humid areas of the United States were examined. The results of our evaluation for generalized arid LLW burial site are presented here. Dose-to-man estimates resulting from biotic transport are compared with doses calculated from human intrusion exposure scenarios. Dose-to-man estimates, as a result of biotic transport, are of the same order of magnitude as those resulting from a more commonly evaluated human intrusion scenario. The reported lack of potential importance of biotic transport at LLW sites in earlier assessment studies is not confirmed by our findings. These results indicate that biotic transport has the long-term potential to mobilize radionuclides. Therefore, biotic transport should be carefully evaluated during burial site assessment
Preliminary safety evaluation for the spent nuclear fuel project`s cold vacuum drying system

Energy Technology Data Exchange (ETDEWEB)

Garvin, L.J., Westinghouse Hanford

1996-07-01

This preliminary safety evaluation (PSE) considers only the Cold Vacuum Drying System (CVDS) facility and its mission as it relates to the integrated process strategy (WHC 1995). The purpose of the PSE is to identify those CBDS design functions that may require safety- class and safety-significant accident prevention and mitigation features.
A multimedia interactive education system for prostate cancer patients: development and preliminary evaluation.

Science.gov (United States)

Diefenbach, Michael A; Butz, Brian P

2004-01-21

A cancer diagnosis is highly distressing. Yet, to make informed treatment choices patients have to learn complicated disease and treatment information that is often fraught with medical and statistical terminology. Thus, patients need accurate and easy-to-understand information. To introduce the development and preliminary evaluation through focus groups of a novel highly-interactive multimedia-education software program for patients diagnosed with localized prostate cancer. The prostate interactive education system uses the metaphor of rooms in a virtual health center (ie, reception area, a library, physician offices, group meeting room) to organize information. Text information contained in the library is tailored to a person's information-seeking preference (ie, high versus low information seeker). We conducted a preliminary evaluation through 5 separate focus groups with prostate cancer survivors (N = 18) and their spouses (N = 15). Focus group results point to the timeliness and high acceptability of the software among the target audience. Results also underscore the importance of a guide or tutor who assists in navigating the program and who responds to queries to facilitate information retrieval. Focus groups have established the validity of our approach and point to new directions to further enhance the user interface.
Barrier analogs: Long-term performance issues, preliminary studies, and recommendations

Energy Technology Data Exchange (ETDEWEB)

Waugh, W.J. [Rust Geotech, Inc., Grand Junction, CO (United States). Environmental Sciences Lab.; Chatters, J.C.; Last, G.V.; Bjornstad, B.N.; Link, S.O. [Pacific Northwest Lab., Richland, WA (United States); Hunter, C.R. [Cascade Earth Sciences, La Grande, OR (United States)

1994-02-01

The US Department of Energy`s Hanford Protective Barrier Development Program is funding studies of natural analogs of the long-term performance of waste site covers. Natural-analog studies examine past environments as evidence for projecting the future performance of engineered structures. The information generated by analog studies is needed to (1) evaluate the designs and results of short term experiments and demonstrations, (2) formulate performance-modeling problems that bound expected changes in waste site environments, and (3) understand emergent system attributes that cannot be evaluated with short-term experiments or computer models. Waste site covers will be part of dynamic environmental systems with attributes that transcend the traits of engineered components. This report discusses results of the previously unreported preliminary studies conducted in 1983 and 1984. These results indicate that analogs could play an important role in predicting the long-term behavior of engineered waste covers. Layered exposures of glacial-flood-deposited gravels mantled with silt or sand that resemble contemporary barrier designs were examined. Bergmounds, another anomaly left by cataclysmic glacial floods, were also examined as analogs of surface gravel.
Hanford performance evaluation program for Hanford site analytical services

International Nuclear Information System (INIS)

Markel, L.P.

1995-09-01

The U.S. Department of Energy (DOE) Order 5700.6C, Quality Assurance, and Title 10 of the Code of Federal Regulations, Part 830.120, Quality Assurance Requirements, states that it is the responsibility of DOE contractors to ensure that ''quality is achieved and maintained by those who have been assigned the responsibility for performing the work.'' Hanford Analytical Services Quality Assurance Plan (HASQAP) is designed to meet the needs of the Richland Operations Office (RL) for maintaining a consistent level of quality for the analytical chemistry services provided by contractor and commmercial analytical laboratory operations. Therefore, services supporting Hanford environmental monitoring, environmental restoration, and waste management analytical services shall meet appropriate quality standards. This performance evaluation program will monitor the quality standards of all analytical laboratories supporting the Hanforad Site including on-site and off-site laboratories. The monitoring and evaluation of laboratory performance can be completed by the use of several tools. This program will discuss the tools that will be utilized for laboratory performance evaluations. Revision 0 will primarily focus on presently available programs using readily available performance evaluation materials provided by DOE, EPA or commercial sources. Discussion of project specific PE materials and evaluations will be described in section 9.0 and Appendix A
Evaluation of dynamic properties, local site effects and design ground motions: recent advances

International Nuclear Information System (INIS)

Sitharam, T.G.; Vipin, K.S.; James, Naveen

2011-01-01

Evidences from past earthquakes clearly shows that the damages due to an earthquake and its severity at a site are controlled mainly by three factors i.e., earthquake source and path characteristics, local geological and geotechnical characteristics, structural design and quality of the construction. Seismic ground response at a site is strongly influenced by local geological and soil conditions. The exact information of the geological, geomorphological and geotechnical data along with seismotectonic details are necessary to evaluate the ground response. The geometry of the subsoil structure, the soil type, the lateral discontinuities and the surface topography will also influence the site response at a particular location. In the case of a nuclear power plant, the details obtained from the site investigation will have multiple objectives: (i) for the effective design of the foundation (ii) assessment of site amplification (iii) for liquefaction potential evaluation. Since the seismic effects on the structure depend fully on the site conditions and assessment of site amplification. The first input required in evaluation of geotechnical aspect of seismic hazard is the rock level peak horizontal acceleration (PHA) values. The surface level acceleration values need to be calculated based on the site conditions and site amplification values. This paper discusses various methods for evaluating the site amplification values, dynamic soil properties, different field and laboratory tests required and various site classification schemes. In addition to these aspects, the evaluation of liquefaction potential of the site is also presented. The paper highlights on the latest testing methods to evaluate dynamic properties (shear modulus and damping ratio) of soils and techniques for estimating local site effects. (author)
Preliminary Evaluation of Probiotic Properties of Lactobacillus Strains Isolated from Sardinian Dairy Products

OpenAIRE

Pisano, Maria Barbara; Viale, Silvia; Conti, Stefania; Fadda, Maria Elisabetta; Deplano, Maura; Melis, Maria Paola; Deiana, Monica; Cosentino, Sofia

2014-01-01

Twenty-three Lactobacillus strains of dairy origin were evaluated for some functional properties relevant to their use as probiotics. A preliminary subtractive screening based on the abilities to inhibit the growth of microbial pathogens and hydrolyze conjugated bile salts was applied, and six strains were selected for further characterization including survival under gastrointestinal environmental conditions, adhesion to gut epithelial tissue, enzymatic activity, and some safety properties. ...
Evaluating Potential Human Health Risks Associated with the Development of Utility-Scale Solar Energy Facilities on Contaminated Sites

Energy Technology Data Exchange (ETDEWEB)

Cheng, J. -J. [Argonne National Lab. (ANL), Argonne, IL (United States); Chang, Y. -S. [Argonne National Lab. (ANL), Argonne, IL (United States); Hartmann, H. [Argonne National Lab. (ANL), Argonne, IL (United States); Wescott, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Kygeris, C. [Indiana Univ. of Pennsylvania, PA (United States)

2013-09-01

This report presents a general methodology for obtaining preliminary estimates of the potential human health risks associated with developing a utility-scale solar energy facility on a contaminated site, based on potential exposures to contaminants in soils (including transport of those contaminants into the air).
Evaluative Testing of 5LA3421: A Multicomponent Prehistoric and Historic Site, Pinon Canyon Maneuver Site, Las Animas County, Colorado

National Research Council Canada - National Science Library

Charles, Mona; Baker, Thann; Markussen, Christine; Nathan, Randy; Duke, Philip

2004-01-01

In the summer of 2002, evaluative testing was undertaken at a large multicomponent site for the purpose of evaluating the potential of this site to yield significant information about the prehistory...

Potential of ricehull communal power generation in the Philippines - a preliminary study

International Nuclear Information System (INIS)

Bernardo, J.Y.; Navarro, L.B.; Abito, G.F.; Lim, B.P.

1992-01-01

The preliminary feasibility study of utilizing ricehulls as fuel for power generation in a communal set-up involving ricemills was completed by PNOC-ERDC for the EC-AIT COGEN Programme. The study assessed the market, evaluated the patterns and level of ricehull availability, and their implications on plant operation characteristics and financial viability. Ten potential areas were studied more closely for their suitability as pilot demonstration sites. (auth.). 8 tabs.; 4 figs.; 1 ref
Risk evaluation of remedial alternatives for the Hanford Site

International Nuclear Information System (INIS)

Clark, S.W.; Lane, N.K.; Swenson, L.

1994-01-01

Risk assessment is one of the many tools used to evaluate and select remedial alternatives and evaluate the risk associated with selected remedial alternatives during and after implementation. The risk evaluation of remedial alternatives (RERA) is performed to ensure selected alternatives are protective of human health and the environment. Final remedy selection is promulgated in a record of decision (ROD) and risks of the selected alternatives are documented. Included in the ROD documentation are the risk-related analyses for long-term effectiveness, short-term effectiveness, and overall protection of human health and the environment including how a remedy will eliminate, reduce or control risks and whether exposure will be reduced to acceptable levels. A major goal of RERA in the process leading to a ROD is to provide decision-makers with specific risk information that may be needed to choose among alternatives. For the Hanford Site, there are many considerations that must be addressed from a risk perspective. These include the large size of the Hanford Site, the presence of both chemical and radionuclide contamination, one likelihood of many analogues sites, public and worker health and safety, and stakeholder concern with ecological impacts from site contamination and remedial actions. A RERA methodology has been promulgated to (1) identify the points in the process leading to a ROD where risk assessment input is either required or desirable and (2) provide guidance on how to evaluate risks associated with remedial alternatives under consideration. The methodology and evaluations parallel EPA guidance requiring consideration of short-term impacts and the overall protectiveness of remedial actions for evaluating potential human health and ecological risks during selection of remedial alternatives, implementation of remedial measures, and following completion of remedial action
Analysis for preliminary evaluation of discrete fracture flow and large-scale permeability in sedimentary rocks

International Nuclear Information System (INIS)

Kanehiro, B.Y.; Lai, C.H.; Stow, S.H.

1987-05-01

Conceptual models for sedimentary rock settings that could be used in future evaluation and suitability studies are being examined through the DOE Repository Technology Program. One area of concern for the hydrologic aspects of these models is discrete fracture flow analysis as related to the estimation of the size of the representative elementary volume, evaluation of the appropriateness of continuum assumptions and estimation of the large-scale permeabilities of sedimentary rocks. A basis for preliminary analysis of flow in fracture systems of the types that might be expected to occur in low permeability sedimentary rocks is presented. The approach used involves numerical modeling of discrete fracture flow for the configuration of a large-scale hydrologic field test directed at estimation of the size of the representative elementary volume and large-scale permeability. Analysis of fracture data on the basis of this configuration is expected to provide a preliminary indication of the scale at which continuum assumptions can be made
Engineering evaluation of a formerly utilized MED/AEC site. Site A and Plot M, Palos Forest Preserve, Palos Park, Illinois

International Nuclear Information System (INIS)

1979-09-01

This engineering evaluation report (EER) addresses one of these MED/AEC sites known as Site A/Plot M, located in Palos Park, Illinois. The EER describes in technical detail a number of options for remedial action that could be taken with respect to the contamination at Site A/Plot M and presents estimates of the costs associated with these options. A companion document, Environmental Analysis Report on a Formerly Utilized MED/AEC Site, Site A and Plot M, Palos Forest Preserve, Palos Park, Illinois (ANL/ES-79), has also been prepared. It describes in detail the existing site environment and evaluates the environmental impacts of the various remedial options discussed in this report. This EER contributes to a better understanding of the mitigation or resolution of environmental problems posed by the subject MED/AEC site and serves as a basis for determining whether or not remedial actions are warranted. The knowledge derived from the evaluation of a number of remedial options should be helpful in the final disposition of other MED/AEC sites located elsewhere
Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

1982-08-01

An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables
Work plan for preliminary investigation of organic constituents in ground water at the New Rifle site, Rifle, Colorado. Revision 2

International Nuclear Information System (INIS)

1996-01-01

A special study screening for Appendix 9 (40 CFR Part 264) analytes identified the New Rifle site as a target for additional screening for organic constituents. Because of this recommendation and the findings in a recent independent technical review, the US Department of Energy (DOE) has requested that the Technical Assistance Contractor (TAC) perform a preliminary investigation of the potential presence of organic compounds in the ground water at the New Rifle Uranium Mill Tailings Remedial Action (UMTRA) Project site, Rifle, Colorado. From 1958 to 1972, organic chemicals were used in large quantities during ore processing at the New Rifle site, and it is possible that some fraction was released to the environment. Therefore, the primary objective of this investigation is to determine whether organic chemicals used at the milling facility are present in the ground water. The purpose of this document is to describe the work that will be performed and the procedures that will be followed during installation of ground water well points at the New Rifle site. The selection of analytes and the procedures for collecting ground water samples for analysis of organic constituents are also described
Draft environmental assessment: Swisher County site, Texas. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy (DOE) identified a location in Swisher County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Swisher site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Swisher site is not disqualified under the guidelines. The site is contained in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Deaf Smith site. Although the Swisher site appears to be suitable for site characterization, the DOE has concluded that the Deaf Smith site is the preferred site in the Permian Basin and is proposing to nominate the Deaf Smith site rather than the Swisher site as one of the five sites suitable for characterization
Draft environmental assessment: Lavender Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy (DOE) identified the Lavender Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Lavender Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Lavender Canyon site is not disqualified under the guidelines. The site is contained in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Davis Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site rather than the Lavender Canyon site as one of the five sites suitable for characterization
Technetium removal: preliminary flowsheet options

International Nuclear Information System (INIS)

Eager, K.M.

1995-01-01

This document presents the results of a preliminary investigation into options for preliminary flowsheets for 99Tc removal from Hanford Site tank waste. A model is created to show the path of 99Tc through pretreatment to disposal. The Tank Waste Remediation (TWRS) flowsheet (Orme 1995) is used as a baseline. Ranges of important inputs to the model are developed, such as 99Tc inventory in the tanks and important splits through the TWRS flowsheet. Several technetium removal options are discussed along with sensitivities of the removal schemes to important model parameters
The influence of evaluation recommendations on instrumental and conceptual uses: A preliminary analysis.

Science.gov (United States)

Bourgeois, Isabelle; Whynot, Jane

2018-06-01

Evaluation recommendations are sometimes included in evaluation reports to highlight specific actions to be taken to improve a program or to make other changes to its operational context. This preliminary study sought to examine evaluation recommendations drawn from 25 evaluation reports published by Canadian federal government departments and agencies, in order to examine the evaluation issues covered and the focus of the recommendations. Our results show that in keeping with policy requirements, the evaluation recommendations focused on program relevance, effectiveness and efficiency and economy. Furthermore, a significant number of recommendations also focused on the implementation of more rigorous performance measurement strategies. The focus of the recommendations did not vary by publication date, recommendation type, and organizational sector. The findings also show that for the most part, the management responses produced as part of the broader evaluation process support the recommendations included in the report and identify specific timelines for implementation. Copyright © 2018 Elsevier Ltd. All rights reserved.
Plans for characterization of the potential geologic repository site at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Dobson, D.C.; Blanchard, M.B.; Voegele, M.D.; Younker, J.L.

1990-01-01

Site investigations in the vicinity of the potential repository site at Yucca Mountain, Nevada, have occurred for many years. Although information from previous site investigations was adequate to support preliminary evaluations by the US Department of Energy (DOE) in the Environmental Assessment and to develop conceptual repository and waste package designs, this information is insufficient to proceed to the advanced designs and performance assessments required for the license application to the US Nuclear Regulatory Commission (NRC). Therefore, intensive site characterization is planned, as described in the December 1988 Site Characterization Plan (SCP). The data acquisition activities described in the SCP are focused on obtaining information to allow evaluations of the natural and engineered barriers considered potentially relevant to repository performance. The site data base must be adequate to allow predictions of the range of expected variation in geologic conditions over the next 10,000 years, as well as predictions of the probabilities for catastrophic geologic events that could affect repository performance. 4 refs., 4 figs
Siting Evaluation for Biomass-Ethanol Production in Hawaii

Energy Technology Data Exchange (ETDEWEB)

Kinoshita, C.M.; Zhou, J.

2000-10-15

This report examines four Hawaiian islands, Oahu, Hawaii, Maui, and Kauai, to identify three best combinations of potential sites and crops for producing dedicated supplies of biomass for conversion to ethanol. Key technical and economic factors considered in the siting evaluation include land availability (zoning and use), land suitability (agronomic conditions), potential quantities and costs of producing biomass feedstocks, infrastructure (including water and power supplies), transportation, and potential bioresidues to supplement dedicated energy crops.
Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

1992-01-01

The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T ampersand MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of senior YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document
Preliminary evaluation of ground-water contamination by coal-tar derivatives, St. Louis Park area, Minnesota

Science.gov (United States)

Hult, Marc F.; Schoenberg, Michael E.

1984-01-01

Operation of a coal-tar distillation and wood-preserving plant from 1918 to 1972 in St. Louis Park, a suburb of Minneapolis, Minn., resulted in ground-water contamination. This preliminary evaluation presents an overview of the problem based on the results of the first year (1979) of an ongoing study.
Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

International Nuclear Information System (INIS)

WESTRA, A.G.

1999-01-01

This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility
Tritium removal: a preliminary evaluation of several getters

International Nuclear Information System (INIS)

Schoenfelder, C.W.; West, L.A.

1975-11-01

The removal of hydrogen isotopes from flowing gas streams is an important aspect of CTR technology for both decontamination and tritium recovery from plasma exhausts. Several getters have been evaluated for their tritium scrubbing potential at the parts per billion level. Measurements of total capacity and dynamic response have been made for barium, erbium, palladium dispersed on molecular sieve, General Electric H-36 (zirconium alloy), Union Carbide Y-993 (PdMnO 2 ), Societa Apparecchi Electtrici e Scientifici Getters ST101 (Zr--Al), ST171, and ST181, and a Sandia developed organic material, dimerized phenyl propargyl ether (DPPE). Preliminary flow studies were conducted by passing mixtures of either hydrogen or deuterium diluted with argon through packed beds containing the getter and periodically sampling the effluent with a gas chromatograph sensitive to 500 ppB H 2 . The results of this work, similar flow experiments using tritium and total capacity measurements are presented in the text
Preliminary remediation goals for ecological endpoints

International Nuclear Information System (INIS)

Efroymson, R.A.; Suter, G.W. II; Sample, B.E.; Jones, D.S.

1996-07-01

Preliminary remediation goals (PRGs) are useful for risk assessment and decision making at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites. PRGs are upper concentration limits for specific chemicals in specific environmental media that are anticipated to protect human health or the environment. They can be used for multiple remedial investigations at multiple facilities. In addition to media and chemicals of potential concern, the development of PRGs generally requires some knowledge or anticipation of future land use. In Preliminary Remediation Goals for Use at the U.S. Department of Energy Oak Ridge Operations Office (Energy Systems 1995), PRGs intended to protect human health were developed with guidance from Risk Assessment Guidance for Superfund: Volume I - Human Health Evaluation Manual, Part B (RAGS) (EPA 1991). However, no guidance was given for PRGs based on ecological risk. The numbers that appear in this volume have, for the most part, been extracted from toxicological benchmarks documents for Oak Ridge National Laboratory (ORNL) and have previously been developed by ORNL. The sources of the quantities, and many of the uncertainties associated with their derivation, are described in this technical memorandum
Preliminary remediation goals for ecological endpoints

International Nuclear Information System (INIS)

Efroymson, R.A.; Suter, G.W. II.

1995-09-01

Preliminary remediation goals (PRGs) are useful for risk assessment and decision making at Comprehensive Environmental Response, compensation, and Liability Act (CERCLA) sites. PRGs are upper concentration limits for specific chemicals in specific environmental media that are anticipated to protect human health or the environment. They can be used for multiple remedial investigations at multiple facilities. In addition to media and chemicals of potential concern, the development of PRGs generally requires some knowledge or anticipation of future land use. In Preliminary Remediation Goals for Use at the US Department of Energy Oak Ridge Operations Office (Energy Systems 1995), PRGs intended to protect human health were developed with guidance from Risk Assessment Guidance for Superfund: Volume I-Human Health Evaluation Manual, Part B (RAGS) (EPA 1991). However, no guidance was given for PRGs based on ecological risk. The numbers that appear in this volume have, for the most part, been extracted from toxicological benchmarks documents for Oak Ridge National Laboratory (ORNL) and have previously been developed by ORNL. The sources of the quantities, and many of the uncertainties associated with their derivation, are described in this technical memorandum
Preliminary analysis of the cost and risk of transporting nuclear waste to potential candidate commercial repository sites

International Nuclear Information System (INIS)

Wilmot, E.L.; Madsen, M.M.; Cashwell, J.W.; Joy, D.S.

1983-06-01

This report documents preliminary cost and risk analyses that were performed in support of the Nuclear Waste Terminal Storage (NWTS) program. The analyses compare the costs and hazards of transporting wastes to each of five regions that contain potential candidate nuclear waste repository sites being considered by the NWTS program. These regions are: the Gulf Interior Region, the Permian Basin, the Paradox Basin, Yucca Mountain, and Hanford. Two fuel-cycle scenarios were analyzed: once-through and reprocessing. Transportation was assumed to be either entirely by truck or entirely by rail for each of the scenarios. The results from the risk analyses include those attributable to nonradiological causes and those attributable to the radioactive character of the wastes being transported. 17 references
Volcanic Hazards in Site Evaluation for Nuclear Installations

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-10-15

This publication provides comprehensive and updated guidance for site evaluation in relation to volcanic hazards. It includes recommendations on assessing the volcanic hazards at a nuclear installation site, in order to identify and characterize, in a comprehensive manner, all potentially hazardous phenomena that may be associated with future volcanic events. It describes how some of these volcanic phenomena may affect the acceptability of the selected site, resulting in exclusion of a site or determining the corresponding design basis parameters for the installation. This Safety Guide is applicable to both existing and new sites, and a graded approach is recommended to cater for all types of nuclear installations. Contents: 1. Introduction; 2. Overview of volcanic hazard assessment; 3. General recommendations; 4. Necessary information and investigations (database); 5. Screening of volcanic hazards; 6. Site specific volcanic hazard assessment; 7. Nuclear installations other than nuclear power plants; 8. Monitoring and preparation for response; 9. Management system for volcanic hazard assessment; Annex I: Volcanic hazard scenarios; Annex II: Worldwide sources of information.

Technical procedures for the implementation of cultural resource site studies, Deaf Smith County, Texas: Preliminary draft

International Nuclear Information System (INIS)

1987-01-01

Cultural resources at the Deaf Smith County site will be identified, evaluated and managed through the implementation of studies detailed in the Site Study Plan for Cultural Resources. This technical procedure outlines the conduct of pedestrian survey and the documentation of identified cultural resources. The purpose of the field surveys is to identify and document cultural resources in the areas that will be affected by site characterization activities and to record the environmental setting of identified cultural resources. Three pedestrian surveys will cover 100 percent of the on-site and off-site project areas. Survey 1 will provide coverage of the Repository Surface Facility (RSF) area, which includes the Exploratory Shaft Facility (ESF) and two linear engineering design borehole (EDBH) seismic survey corridors. Survey 2 will provide coverage of a 39 km 2 (15 mi 2 ) area that includes the 23 km 2 (9 mi 2 ) Deaf Smith County site plus a 0.4 to 0.8 kM (1/4 to 1/2 mi) border area but excludes the area covered by Survey 1. Survey 3 will cover offsite geotechnical test areas, such as the locations of playa boreholes, deep playa wells, hydrologic tests, site foundation borings, and their access routes. The purpose of site documentation or recording is to address the project information needs for land use permits and approvals, engineering design support, and cultural resource evaluation for National Register of Historic Places eligibility. Site documentation will consist of gathering sufficient data on identified resources to complete Texas Natural Resource Information System (TNRIS). 7 refs., 3 figs
Evaluation of remedial alternatives for the Solar Ponds Plume, Rocky Flats Environmental Technology Site

International Nuclear Information System (INIS)

Hranac, K.C.

1998-01-01

This paper describes the process used to select a remedial alternative for handling contaminated groundwater emanating from the Solar Evaporation Ponds (Solar Ponds) at the Rocky Flats Environmental Technology Site (RFETS) and prevent it from reaching the nearest surface water body, North Walnut Creek. Preliminary results of field investigations conducted to provide additional information for the alternatives analysis are also presented. The contaminated groundwater is referred to as the Solar Ponds Plume (SPP). The primary contaminants in the SPP are nitrate and uranium; however, some metals exceed the site action levels at several locations and volatile organic compounds, originating from other sources, also have been detected. Currently the SPP, local surface water runoff, and infiltrated precipitation are collected by a trench system located downgradient of the Solar Ponds and pumped to three storage tanks. The water (two to three million gallons annually) is then pumped to an on-site treatment plant for evaporation at an approximate cost of $7.57 per liter
The role of geology in the evaluation of waste disposal sites

International Nuclear Information System (INIS)

Ogunsanwo, O.; Mands, E.

1999-01-01

The construction of waste disposal sites demonstrates the awareness of the need to protect the environment against pollution. The site are constructed on foundations of soils and rocks. Photo geological studies, geophysical investigations and geological field mapping are indispensable in the selection of suitable sites. Most of the construction materials (in the case of landfills) are of geologic origin and their suitability can only be ascertained after some geological assessments. Furthermore, the hydrogeological conditions within the adjoining terrains and the flow of leachates from and within the wastes must be monitored so as to prevent pollution (radiation, in the case of radioactive wastes, can be monitored with the aid of geochemistry). Several models/systems are available for the hydrogeological/geochemical evaluation of waste disposal sites. The selection of the site and the construction materials as well as the hydrogeological/ /geochemical studies are very critical as the performance of the disposal site depends solely on these aspects. These aspects are basically within the realms of geology. It is thus obvious that geology plays a leading role in the evaluation of waste disposal sites right from the site selection stage until the site is done with
Water-quality monitoring at the Hoe Creek test site: review and preliminary conclusions

Energy Technology Data Exchange (ETDEWEB)

Wang, F T; Mead, S W; Stuermer, D H

1982-05-20

It has been shown that underground coal gasification (UCG) may introduce a broad range of residual gasification products into the groundwater of a coal aquifer. Sorption of many contaminants by the coal itself is an important factor in restricting the migration of these contaminants in the ground water. However, field studies, conducted at Lawrence Livermore National Laboratory's Hoe Creek site, have shown that sorption of organic compounds by coal is not as effective as expected, perhaps because the coal surface area is limited. Furthermore, if severe roof collapse has taken place during gasification, non-coal aquifers located above the gasified coal seam may be interconnected with the coal aquifer, and contaminants may enter these non-coal aquifers, in which sorption is even less effective. The Hoe Creek II and III experiments have provided opportunities to study the contamination of a sand aquifer located above a gasified coal seam in a hydrological recharge area. Preliminary results indicate that the water in the overlying sand aquifer is much less contaminated with organic compounds than the water in the gasified coal aquifer. In conducting these field investigations, valuable lessons ere learned concerning groundwater monitoring. A suggested monitoring strategy is discussed.
Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities

International Nuclear Information System (INIS)

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-09-01

This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km 2 (570-mi 2 ) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation
Preliminary evaluation of FY98 KALIMER shielding design

Energy Technology Data Exchange (ETDEWEB)

Yoo, Jae Woon; Kang, Chang Mu; Kim, Young Jin [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-01-01

This report describes a preliminary evaluation of the shielding design of FY98 KALIMER. The KALIMER shielding design includes the Inner Fixed Shield of a stainless cylinder located inside the support barrel; the Radial PSDRS Shields which are three B{sub 4}C cylinders located outside the support barrel at core level; the Lower IHX shield of a cylindrical B{sub 4}C plate located above the flow guide; and Inner and Outer IHX shields of B{sub 4}C cylinders located inside and outside of the support barrel, respectively. The DORT3.1 two-dimensional transport code was used to evaluate the KALIMER shielding design. The reactor system was represented by four axial zones, each of which was modeled in the R-Z geometry. The KAFAX-F22 library was used in the analyses, which was generated from the JEF-2.2 of OECD/NEA files for LMR applications by KAERI. The performance of the KALIMER shielding design is compared against the shielding design criteria. The results indicate that the support barrel, upper grid plate, and other reactor structures meet the maximum neutron fluence and DPA limits established in the shielding design criteria. Activities of the air effluent in the PSDRS were also evaluated and are shown to satisfy the maximum permissible concentration (MPC) limits in 10 CFR Part 20. In the future, the validation of the DORT model by a detailed three dimensional calculation such as MCNP and the justification of the current shielding design limits are needed. (author). 13 refs., 23 figs., 31 tabs.
How tolerable is delay? : Consumers' evaluations of internet web sites after waiting

NARCIS (Netherlands)

B.G.C. Dellaert (Benedict); B.E. Kahn

1998-01-01

textabstractHow consumer's waiting times affect their retrospective evaluations of Internet Web Sites is investigated in four computer-based experiments. Results show that waiting can but does not always negatively affect evaluations of Web Sites. Results also show that the potential negative
Nuclear site selection studies

International Nuclear Information System (INIS)

Gharib, A.; Zohoorian Izadpanah, A.A.; Iranmanesh, H.

2000-01-01

It is of special importance, especially from the nuclear safety viewpoint, to select suitable sites for different nuclear structures with the considered future activities. Site selection sometimes involves high costs not necessarily for merely selecting of site but for some preliminary measures to be taken so as the site may have the necessary characteristics. The more suitable the natural characteristics of the site for the considered project, the more successful and efficient the project, the lower the project costs and the longer the project operation period. If so, the project will cause the growth of public culture and sustainable socioeconomic development. This paper is the result of the conclusion of numerous massive reports of this activity in the preliminary phase based on theories, practices and the related safety principles on this ground as well as the application of data and information of the past and a glance to the future. The conception of need for a site for medium structures and nuclear research projects and how to perform this process are presented step by step here with a scientific approach to its selection during the investigations. In this study, it is practically described how the site is selected, by determining and defining the characteristics of research and nuclear projects with medium structures and also its fitting to the optimum site. The discovered sites typically involve the best advantages in technical and economic aspects and no particular contrast with the concerned structures
Tsunami hazard assessment on nuclear power plant site evaluation accordance on DS 417

International Nuclear Information System (INIS)

Akhmad Khusyairi

2011-01-01

Nuclear power plant site evaluation should conduct the hazard evaluation on tsunami. Global climate changes and particularly extreme meteorology and hydrology phenomena have an impact on the structure, systems and important components related to safety. Therefore, IAEA makes efforts to revise the IAEA Safety Standard Series NS-G 3.4, Meteorological Events in Site Evaluation for Nuclear Power Plants and IAEA safety standard series NS-G 3.5 Flood Hazard For Nuclear Power Plants On Coastal And River Sites, in order to provide protection against the public and the environment safety due to operation of nuclear power plants. There are two methods used in assessing tsunami hazard, probabilistic and deterministic methods. In the tsunami hazard assessment, some necessary information and data should be obtained to determine the basic design of tsunami hazard during designing nuclear power plants, especially the cooling system design. Flooding caused tsunami must be evaluated to determine the site protection system. Furthermore, There must be an evaluation on either coincident event or meteorological simultaneously tsunami event that caused the worst effect on the site. Therefore, the protection of the site from extreme tsunami can be planned. (author)
Draft environmental assessment: Vacherie Dome site, Louisiana. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy (DOE) identified the Vacherie dome in Louisiana as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Vacherie dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Vacherie dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Richton dome site. Although the Vacherie dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. On the basis of these findings, the DOE is proposing to nominate the Richton dome site rather than the Vacherie dome site as one of the five sites suitable for characterization
Application of the preliminary Geosite Assessment Model (GAM: The case of the Bela Crkva municipality (Vojvodina, north Serbia

Directory of Open Access Journals (Sweden)

Boškov Jovana

2015-01-01

Full Text Available Bela Crkva municipality is located in the northeastern part of Serbia, in the Southeast of the Autonomous Province of Vojvodina. This Municipality has a high concentration of geo sites which are of a great importance, and providing a good basis for the geo tourism development in this area. This paper proposes an inventory of geo sites in the Bela Crkva municipality. One of the aims of the paper is to evaluate different values of geo sites using preliminary Geosite Assessment Model (GAM in order to determine whether this area has the potential for geo tourism development.
How Tolerable is Delay? Consumers' Evaluations of Internet Web Sites After Waiting

NARCIS (Netherlands)

Dellaert, B.G.C.; Kahn, B.

1998-01-01

How consumers’ waiting times affect their retrospective evaluations of Internet Web Sites is investigated in four computer-based experiments. Results show that waiting can but does not always negatively affect evaluations of Web Sites. Results also show that the potential negative effects of waiting
Final report of fugitive and diffuse emissions evaluations at the Hanford Site, CY 1994

International Nuclear Information System (INIS)

Gleckler, B.P.; Schmidt, J.W.

1995-01-01

The objective of this study was to evaluate several of Hanford's major diffuse emission sources and evaluate the effectiveness of monitoring these sources individually versus collectively. The results from this evaluation may also be utilized to demonstrate Westinghouse's compliance status with the applicable air emissions regulations and determine if additional studies and/or evaluations are necessary. Air sampling results from four waste handling and storage facilities were collected for a one week period and analyzed. The following is a list of the selected sampling sites: Plutonium Finishing Plant; 241-BY Tank Farm; 1301-N Trench; 300 Area Trenches and North Ponds. These sites were chosen as being representative of most of the Hanford waste sites, which are known to be diffuse emission sites. The sites were evaluated on the following criteria: physical size, surface contamination levels, geology, vegetation density, surface cover, potential for occupational exposure, and potential for public exposure. The selected sites vary greatly with the selection criteria parameters, and as a result should provide representative data for most of Hanford's waste sites
Phytochemical Screening and Preliminary Evaluation of Analgesic ...

African Journals Online (AJOL)

In this study, the methanolic root extract of Cissus polyantha was subjected to preliminary phytochemical screening, analgesic and anti-inflammatory studies. Phytochemical studies was carried out using standard phytochemical protocol while the analgesic studies was carried out using acetic acid-induced writhing tests in ...
A Preliminary Evaluation of Fast ForWord-Language as an Adjuvant Treatment in Language Intervention

Science.gov (United States)

Fey, Marc E.; Finestack, Lizbeth H.; Gajewski, Byron J.; Popescu, Mihai; Lewine, Jeffrey D.

2010-01-01

Purpose: Fast ForWord-Language (FFW-L) is designed to enhance children's processing of auditory-verbal signals and, thus, their ability to learn language. As a preliminary evaluation of this claim, we examined the effects of a 5-week course of FFW-L as an adjuvant treatment with a subsequent 5-week conventional narrative-based language…
In situ vitrification: Preliminary results from the first large-scale radioactive test

International Nuclear Information System (INIS)

Buelt, J.L.; Westsik, J.H.

1988-02-01

The first large-scale radioactive test (LSRT) of In Situ Vitrification (ISV) has been completed. In Situ Vitrification is a process whereby joule heating immobilizes contaminated soil in place by converting it to a durable glass and crystalline waste form. The LSRT was conducted at an actual transuranic contaminated soil site on the Department of Energy's Hanford Site. The test had two objectives: (1) determine large-scale processing performance and (2) produce a waste form that can be fully evaluated as a potential technique for the final disposal of transuranic-contaminated soil sites at Hanford. This accomplishment has provided technical data to evaluate the ISV process for its potential in the final disposition of transuranic-contaminated soil sites at Hanford. Because of the test's successful completion, within a year technical data on the vitrified soil will be available to determine how well the process incorporates transuranics into the waste form and how well the form resists leaching of transuranics. Preliminary results available include retention of transuranics and other elements within the waste form during processing and the efficiency of the off-gas treatment system in removing contaminants from the gaseous effluents. 13 refs., 10 figs., 5 tabs
A preliminary evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

International Nuclear Information System (INIS)

Smith, T.H.; Roesener, W.S.; Jorgenson-Waters, M.J.

1993-07-01

The Mixed and Low-Level Waste Disposal Facility (MLLWDF) project was established in 1992 by the US Department of Energy Idaho Operations Office to provide enhanced disposal capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This Preliminary Evaluation of Alternatives for Disposal of INEL Low-Level Waste and Low-Level Mixed Waste identifies and evaluates-on a preliminary, overview basis-the alternatives for disposal of that waste. Five disposal alternatives, ranging from of no-action'' to constructing and operating the MLLWDF, are identified and evaluated. Several subalternatives are formulated within the MLLWDF alternative. The subalternatives involve various disposal technologies as well as various scenarios related to the waste volumes and waste forms to be received for disposal. The evaluations include qualitative comparisons of the projected isolation performance for each alternative, and facility, health and safety, environmental, institutional, schedule, and rough order-of-magnitude life-cycle cost comparisons. The performance of each alternative is evaluated against lists of ''musts'' and ''wants.'' Also included is a discussion of other key considerations for decisionmaking. The analysis of results indicated further study is necessary to obtain the best estimate of long-term future waste volume and characteristics from the INEL Environmental Restoration activities and the expanded INEL Decontamination and Decommissioning Program
Evaluation of Landfill Site Candidate for Naturally Occurring Radioactive Materials (Norm) and Hazardous Waste

International Nuclear Information System (INIS)

Sucipta; Hadi Suntoko; Bunawas

2007-01-01

Refers to co-location concept, Kabil site, where located at the southeast end of low hills in Batam Island, will be sited as an integrated industrial waste management center including landfill. So that, it is necessary an evaluation of the landfill site candidate for NORM and hazardous waste. The evaluation includes geological and non-geological aspects, to determine the suitability or capability in supporting the function as landfill facility. The site candidate was evaluated by serial sreps as follows: 1) criteria formulation; 2) selecting the parameter for evaluation; 3) Positive screening or evaluation of the land having potentiality for landfill site by descriptive method: and 4) determine the land suitability or capability for landfill site. The evaluation of geological and non- geological aspects include topography, litology, seismicity, groundwater and surface water, climate, hydro-oceanography, flora and fauna, spatial pattern and transportation system. The most of the parameters evaluated show the fulfilling to the site criteria, and can be mentioned that the land is suitable for landfill site. Some parameters are not so suitable for that purpose, especially on permeability and homogeneity of the rocks/soils, distance to surface water body, depth of groundwater, the flow rate of groundwater, precipitation, and humidity of the air. The lack of suitability showed by some parameters can be compensated by improving the appropriate engineered barrier in order to fulfill the landfill performance in providing the supporting capacity, long live stability and waste containment. (author)
Design aspects of the Alpha Repository. I. Preliminary results of facility layout, room stability, and equipment selection efforts. Summary progress report RSI-0024

International Nuclear Information System (INIS)

Gnirk, P.F.; Grams, W.H.; Zeller, T.J.; Ellis, D.B.; Pariseau, W.G.; Fossum, A.F.; Ratigan, J.L.; Hansen, F.D.

1975-01-01

Results of preliminary analysis of the stability of mines in salt formations underlying Eddy and Lea Counties in New Mexico are presented. Methods and equipment for drilling canister emplacement holes in these formations were evaluated along with methods for excavating storage areas and transport of the excavated salt. Progress during the period is reported in chapters on geological and rock properties at the repository site, preliminary mine layout, basic requirements for repository usage, excavation geometries, drill selection, excavation systems, and safety requirements
Integrated methodology for the evaluation of the vulnerability of archaeological sites: the Roman Theater of Verona

International Nuclear Information System (INIS)

Cescatti, Elvis; Lorenzoni, Filippo; Caldon, Mauro; Modena, Claudio; Da Porto, Francesca

2016-01-01

The knowledge-based methodologies for assessing the structural safety and vulnerability of historical buildings are based on the application of an operational approach that is divided into several phases including historical research, the execution of non-destructive or moderately destructive investigations, monitoring and structural analysis. Monitoring is a useful tool to be used throughout the whole process of knowledge not only in the preliminary diagnosis, but also for the control of the quality and effectiveness of the interventions, in the context of appropriate conservation programs e protection of the object being studied. From this point of view, monitoring becomes essential for: (i) the evaluation of the real structural behavior and the identification of vulnerabilities, prior to the execution of any intervention; (ii) minimization and optimization of interventions, firstly by providing indications regarding those that are not necessary and / or invasive. This methodology has been recently applied and valid from the authors to an archaeological site of particular relevance: the Roman Theater of Verona. The deepening of the knowledge phase (historical analysis, survey, study of the subsoil, properties of materials), combined with the installation of a permanent monitoring system and the structural modeling, allowed to obtain a reliable assessment of the site's vulnerabilities with the aim of guaranteeing in an effective and careful protection and enhancement.

Site characterization report for the Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1982-11-01

This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues
Risk of surgical site infection in paediatric herniotomies without any prophylactic antibiotics: A preliminary experience

Directory of Open Access Journals (Sweden)

Dhananjay Vaze

2014-01-01

Full Text Available Background: Different studies underline the use of pre-operative antibiotic prophylaxis in clean surgeries like herniotomy and inguinal orchiopexy. But, the meta-analyses do not recommend nor discard the use of prophylactic pre-operative antibiotics. The scarcity of controlled clinical trials in paediatric population further vitiates the matter. This study assessed the difference in the rate of early post-operative wound infection cases in children who received single dose of pre-operative antibiotics and children who did not receive antibiotics after inguinal herniotomy and orchiopexy. Materials and Methods: This randomised prospective study was conducted in Paediatric Surgery department of PGIMER Chandigarh. Out of 251 patients, 112 patients were randomised to the case group and 139 were ascribed to the control group. The patients in control group were given a standard regimen of single dose of intravenous antibiotic at the time of induction followed by 3-4 days of oral antibiotic. Case group patients underwent the surgical procedure in similar manner with no antibiotic either at the time of induction or post-operatively. Results: The incidence of surgical site infection in case group was 3.73 % and that in control group was 2.22%. The observed difference in the incidence of surgical site infection was statistically insignificant (P value = 0.7027. The overall infection rate in case and control group was 2.89%. Conclusions: Our preliminary experience suggests that there is no statistically significant difference in the proportion of early post-operative wound infection between the patients who received single dose of pre-operative antibiotics and the patients who received no antibiotics after inguinal herniotomy and orchiopexy. The risk of surgical site infection in paediatric heriotomies does not increase even if the child′s weight is less than his/her expected weight for age.
Draft environmental assessment: Cypress Creek Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy (DOE) identified the Cypress Creek dome site in Mississippi as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Cypress Creek dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Cypress Creek dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Richton dome site and the Vacherie dome site. Although the Cypress Creek dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region and is proposing to nominate the Richton dome site rather than the Cypress Creek dome site as one of the three sites suitable for characterization
Meteorology in site operations

International Nuclear Information System (INIS)

Anon.

1986-01-01

During the site selection and design phases of a plant, meteorological assistance must be based on past records, usually accumulated at stations not actually on the site. These preliminary atadvices will be averages and extremes that might be expected. After a location has been chosen and work has begun, current and forecast weather conditions become of immediate concern. On-site meteorological observations and forecasts have many applications to the operating program of an atomic energy site. Requirements may range from observations of the daily minimum temperatures to forecasts of radiation dosages from airborne clouds
Preliminary site description Simpevarp subarea - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Winberg, Anders [ed.

2005-04-01

The objectives of the version 1.2 site descriptive modelling (SDM) of the Simpevarp subarea are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations on a continuous basis. The modelling work is based on primary data available at the time of the data freeze for Simpevarp 1.2, April 1, 2004. The local scale model area (24 km{sup 2}) for the Simpevarp 1.2 modelling encompasses both the Simpevarp and Laxemar subareas. The local model area is located in the centre of a regional scale model area (273 km{sup 2}). Surface ecosystem models in terms of pools and fluxes of carbon have been developed for the terrestrial (e.g. plants and animals) and limnic (e.g. algae and fish) systems using the Lake Frisksjoen drainage area. Furthermore, a first marine ecosystem model has been developed for the Basin Borholmsfjaerden. Three principal lithological domains have been defined in the subarea, an A domain that is dominated by the Aevroe granite, a domain B that is dominated by the fine-grained dioritoid, a C domain that is characterised by a mixture of of Aevroe granite and quartz monzodiorite. A fourth domain is made up a few scattered domains of diorite to gabbro. In total, 22 deformation zones with high confidence of occurrence have been interpreted in the local scale model area. The understanding of the interpreted deformation zones of the Simpevarp subarea is considered adequate to make a preliminary assessment of available storage volumes for a deep repository. High rock stresses do not appear to be a major concern for the Simpevarp subarea. The magnitude of the maximum principal stress at 500 m in the Simpevarp subarea is estimated at 10-22 MPa. The analysis of the thermal conductivity has developed considerably since Simpevarp 1.1. In terms of interpreted mean values for the identified lithological
Preliminary site description Simpevarp subarea - version 1.2

International Nuclear Information System (INIS)

Winberg, Anders

2005-04-01

The objectives of the version 1.2 site descriptive modelling (SDM) of the Simpevarp subarea are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations on a continuous basis. The modelling work is based on primary data available at the time of the data freeze for Simpevarp 1.2, April 1, 2004. The local scale model area (24 km 2 ) for the Simpevarp 1.2 modelling encompasses both the Simpevarp and Laxemar subareas. The local model area is located in the centre of a regional scale model area (273 km 2 ). Surface ecosystem models in terms of pools and fluxes of carbon have been developed for the terrestrial (e.g. plants and animals) and limnic (e.g. algae and fish) systems using the Lake Frisksjoen drainage area. Furthermore, a first marine ecosystem model has been developed for the Basin Borholmsfjaerden. Three principal lithological domains have been defined in the subarea, an A domain that is dominated by the Aevroe granite, a domain B that is dominated by the fine-grained dioritoid, a C domain that is characterised by a mixture of of Aevroe granite and quartz monzodiorite. A fourth domain is made up a few scattered domains of diorite to gabbro. In total, 22 deformation zones with high confidence of occurrence have been interpreted in the local scale model area. The understanding of the interpreted deformation zones of the Simpevarp subarea is considered adequate to make a preliminary assessment of available storage volumes for a deep repository. High rock stresses do not appear to be a major concern for the Simpevarp subarea. The magnitude of the maximum principal stress at 500 m in the Simpevarp subarea is estimated at 10-22 MPa. The analysis of the thermal conductivity has developed considerably since Simpevarp 1.1. In terms of interpreted mean values for the identified lithological domains, the
Communication activities for NUMO's site selection process

International Nuclear Information System (INIS)

Takeuchi, Mitsuo; Okuyama, Shigeru; Kitayama, Kazumi; Kuba, Michiyoshi

2004-01-01

A siting program for geological disposal of high-level radioactive waste (HLW) in Japan has just started and is moving into a new stage of communication with the public. A final repository site will be selected via a stepwise process, as stipulated in the Specified Radioactive Waste Final Disposal Act promulgated in June 2000. Based on the Act, the site selection process of the Nuclear Waste Management Organization of Japan (NUMO, established in October 2000) will be carried out in the three steps: selection of Preliminary Investigation Areas (PIAs), selection of Detailed Investigation Areas (DIAs) and selection of the Repository Site. The Act also defines NUMO's responsibilities in terms of implementing the HLW disposal program in an open and transparent manner. NUMO fully understands the importance of public participation in its activities and is aiming to promote public involvement in the process of site selection based on a fundamental policy, which consists of 'adopting a stepwise approach', 'respecting the initiative of municipalities' and 'ensuring transparency in information disclosure'. This policy is clearly reflected in the adoption of an open solicitation approach for volunteer municipalities for Preliminary Investigation Areas (PIAs). NUMO made the official announcement of the start of its open solicitation program on 19 December 2002. This paper outlines how NUMO's activities are currently carried out with a view to encouraging municipalities to volunteer as PIAs and how public awareness of the safety of the HLW disposal is evaluated at this stage
Radiological consequence analysis. Report on the work package 10. Preliminary safety analysis for the site Gorleben; Radiologische Konsequenzanalyse. Bericht zum Arbeitspaket 10. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

Energy Technology Data Exchange (ETDEWEB)

Larue, Juergen; Baltes, Bruno; Fischer, Heidemarie; Frieling, Gerd; Kock, Ingo; Navarro, Martin; Seher, Holger

2013-02-15

Work package 10 of the preliminary safety analysis for the site Gorleben concerns the analysis of release scenarios and the radiological consequences. The report includes the description of the applied methodology, the concept for the mathematical description of scenarios, the variety of scenarios for the radiological consequence analysis with the definition of the reference scenario. The database for the calculation covers geology and hydrology, the final repository concept and the process of the final disposal system. The used models were the one-phase transport model MARINE and the two-phase transport model TOUGH2. The report summarizes the results including an evaluation of the realization of the demonstration concept with respect to solution transport, fluid transport, robustness of the modeling results and analogy discussion to other disposal variants (i.e. borehole disposal and storage of transport or storage casks).
Non-Operational Property Evaluation for the Hanford Site River Corridor - 12409

Energy Technology Data Exchange (ETDEWEB)

Lowe, John [CH2M HILL, Richland, Washington 99354 (United States); Aly, Alaa [CH2M HILL Plateau Remediation Company and INTERA Incorporated, Richland, Washington 99354 (United States)

2012-07-01

The Hanford Site River Corridor consists of the former reactor areas of the 100 Areas and the former industrial (fuel processing) area in the 300 Area. Most of the waste sites are located close to the decommissioned reactors or former industrial facilities along the Columbia River. Most of the surface area of the River Corridor consists of land with little or no subsurface infrastructure or indication of past or present releases of hazardous constituents, and is referred to as non-operational property or non-operational area. Multiple lines of evidence have been developed to assess identified fate and transport mechanisms and to evaluate the potential magnitude and significance of waste site-related contaminants in the non-operational area. Predictive modeling was used for determining the likelihood of locating waste sites and evaluating the distribution of radionuclides in soil based on available soil concentration data and aerial radiological surveys. The results of this evaluation indicated: 1) With the exception of stack emissions, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas, 2) Stack emissions that may have been associated with Hanford Site operations generally emitted short-lived and/or gaseous radionuclides, and (3) the likelihood of detecting elevated radionuclide concentrations or other waste sites in non-operational area soils is very small. The overall conclusions from the NPE evaluation of the River Corridor are: - With the exception of stack emissions to the air, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas. While pathways such as windblown dust, overland transport and biointrusion have the potential for dispersing waste site contaminants, the resulting transport is unlikely to result in substantial contamination in non-operational areas. - Stack
Preliminary safety evaluation of the Gas Turbine-Modular Helium Reactor (GT-MHR)

International Nuclear Information System (INIS)

Dunn, T.D.; Lommers, L.J.; Tangirala, V.E.

1994-04-01

A qualitative comparison between the safety characteristics of the Gas Turbine-Modular Helium Reactor (GT-MHR) and those of the steam cycle shows that the two designs achieve equivalent levels of overall safety performance. This comparison is obtained by applying the scaling laws to detailed steam-cycle computations as well as the conclusions obtained from preliminary GT-MHR model simulations. The gas turbine design is predicted to be superior for some event categories, while the steam cycle design is better for others. From a safety perspective, the GT-MHR has a modest advantage for pressurized conduction cooldown events. Recent computational simulations of 102 column, 550 MW(t) GT-MHR during a depressurized conduction cooldown show that peak fuel temperatures are within the limits. The GT-MHR has a significantly lower risk due to water ingress events under operating conditions. Two additional scenarios, namely loss of load event and turbine deblading event that are specific to the GT-MHR design are discussed. Preliminary evaluation of the GT-MHR's safety characteristics indicate that the GT-MHR can be expected to satisfy or exceed its safety requirements
Evaluating the adequacy of a reference site pool for ecological assessments in environmentally complex regions

Science.gov (United States)

Ode, Peter R.; Rehn, Andrew C.; Mazor, Raphael D.; Schiff, Kenneth C.; Stein, Eric D.; May, Jason; Brown, Larry R.; Herbst, David B.; Gillette, D.D.; Lunde, Kevin; Hawkins, Charles P.

2016-01-01

Many advances in the field of bioassessment have focused on approaches for objectively selecting the pool of reference sites used to establish expectations for healthy waterbodies, but little emphasis has been placed on ways to evaluate the suitability of the reference-site pool for its intended applications (e.g., compliance assessment vs ambient monitoring). These evaluations are critical because an inadequately evaluated reference pool may bias assessments in some settings. We present an approach for evaluating the adequacy of a reference-site pool for supporting biotic-index development in environmentally heterogeneous and pervasively altered regions. We followed common approaches for selecting sites with low levels of anthropogenic stress to screen 1985 candidate stream reaches to create a pool of 590 reference sites for assessing the biological integrity of streams in California, USA. We assessed the resulting pool of reference sites against 2 performance criteria. First, we evaluated how well the reference-site pool represented the range of natural gradients present in the entire population of streams as estimated by sites sampled through probabilistic surveys. Second, we evaluated the degree to which we were successful in rejecting sites influenced by anthropogenic stress by comparing biological metric scores at reference sites with the most vs fewest potential sources of stress. Using this approach, we established a reference-site pool with low levels of human-associated stress and broad coverage of environmental heterogeneity. This approach should be widely applicable and customizable to particular regional or programmatic needs.
Towards a Tissue-Engineered Ligament: Design and Preliminary Evaluation of a Dedicated Multi-Chamber Tension-Torsion Bioreactor

Directory of Open Access Journals (Sweden)

Cédric P. Laurent

2014-02-01

Full Text Available Tissue engineering may constitute a promising alternative to current strategies in ligament repair, providing that suitable scaffolds and culture conditions are proposed. The objective of the present contribution is to present the design and instrumentation of a novel multi-chamber tension-torsion bioreactor dedicated to ligament tissue engineering. A preliminary biological evaluation of a new braided scaffold within this bioreactor under dynamic loading is reported, starting with the development of a dedicated seeding protocol validated from static cultures. The results of these preliminary biological characterizations confirm that the present combination of scaffold, seeding protocol and bioreactor may enable us to head towards a suitable ligament tissue-engineered construct.
Draft environmental assessment: Richton Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy identified the Richton dome site as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Richton dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Richton dome site is not disqualified under the guidelines. The site is in the Gulf Interior Region of the Gulf Coastal Plain. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Vacherie dome site. Although these other two sites appear to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Richton dome site as one of five sites suitable for characterization. Having compared the Richton dome site with the other four sites proposed for nomination, the DOE has determined that the Richton dome site is not one of the three preferred sites for recommendation to the President as candidates for characterization
Criteria and evaluation of shallow land burial sites

International Nuclear Information System (INIS)

Chandra, U.

1986-01-01

The criteria for shallow ground disposal of radioactive wastes as developed by Nuclear Regulatory Commission-US and International Atomic Energy Agency are discussed. Emphasis has been given to: elaboration of various basic components of a national Strategy for radioactive waste disposal; development of technical requirements; environmental standards, consensus among scientific community and public confidence. Aspects of site selection, evaluation/characterization and site suitability are dealt with. Some results of characterization of a site for tempory storage of low level solid radioactive wastes in Instituto de Pesquisas Energeticas e Nucleares-IPEN-CNEN/Sao Paulo are described. The methods used for hydrological characterization include use of artificial tritium for unsaturated zone and radioactive tracers like I-131, Cr 51 Cl 3 , Cr 51 EDTA, Br 82 for the saturated zone. (Author) [pt
Criteria and evaluation of shallow land burial sites

International Nuclear Information System (INIS)

Chandra, U.

1987-01-01

The criteria for shallow ground disposal of radioactive wastes as developed by Nuclear Regulatory Comission-US and International Atomic Energy Agency are discussed. Emphasis has been given to: elaboration of various basic components of a national strategy for radioactive waste disposal; development of technical requirements; environmental standards, consensus among scientific community and public confidence. Aspects of site selection, evaluation/characterization and site suitability are dealt with. Some results of characterization of a site for temporary storage of low level solid radioactive wastes in Instituto de Pesquisas Energeticas e Nucleares - IPEN - CNEN/Sao Paulo are described. The methods used for hydrological characterization include use of artificial tritium for unsaturated zone and radioactive tracers like I - 131, Cr 51 Cl 3 , Cr 51 EDTA, Br 82 for the saturated zone. (Author) [pt
Geologic evaluation of six nonwelded tuff sites in the vicinity of Yucca Mountain, Nevada for a surface-based test facility for the Yucca Mountain Project

International Nuclear Information System (INIS)

Broxton, D.E.; Chipera, S.J.; Byers, F.M. Jr.; Rautman, C.A.

1993-10-01

Outcrops of nonwelded tuff at six locations in the vicinity of Yucca Mountain, Nevada, were examined to determine their suitability for hosting a surface-based test facility for the Yucca Mountain Project. Investigators will use this facility to test equipment and procedures for the Exploratory Studies Facility and to conduct site characterization field experiments. The outcrops investigated contain rocks that include or are similar to the tuffaceous beds of Calico Hills, an important geologic and hydrologic barrier between the potential repository and the water table. The tuffaceous beds of Calico Hills at the site of the potential repository consist of both vitric and zeolitic tuffs, thus three of the outcrops examined are vitric tuffs and three are zeolitic tuffs. New data were collected to determine the lithology, chemistry, mineralogy, and modal petrography of the outcrops. Some preliminary data on hydrologic properties are also presented. Evaluation of suitability of the six sites is based on a comparison of their geologic characteristics to those found in the tuffaceous beds of Calico Hills within the exploration block
Preliminary evaluation of rotational Vol-oxidizer for hot cell operation - 5320

International Nuclear Information System (INIS)

Kim, Y.H.; Lee, J.W.; Cho, Y.Z.; Ahn, D.H.; Song, K.C.

2015-01-01

KAERI is developing a mechanical head-end process for pyro-processing. As a piece of the processing equipment, a vol-oxidizer that can handle several tens of kg of HM/batch is under development to supply U 3 O 8 powders to an electrolytic reduction (ER) reactor. To operate a vol-oxidizer in a hot cell, the reactor should be optimized by the mechanical design, and the vol-oxidizer should have a high hull recovery rate. In addition, a vol-oxidizer for hot cell demonstrations that handles the spent fuel of high radiation virulence in a limited space should have a small size and not scatter in its outlet. In this paper, we aim at a preliminary evaluation of a rotational vol-oxidizer for hot cell operation. To evaluate the preliminary situation, we produced a theoretical equation of an optimum reactor size, and verification tests were conducted using an acryl vessel and zircaloy-4 tube according to various weights and lengths. In addition, we predicted the terminal velocity of U 3 O 8 using the terminal velocity of SiO 2 , which will determine the optimum air flux, and through an oxidation experiment, we verified the theory form to detect the existence of U 3 O 8 powder in a discharge filter. In addition, hull separation tests were conducted using a reactor and hulls with a 50 kg HM/batch for the recovery rate of the hulls. The results indicate that we obtained an appropriate air flux so as to not cause U 3 O 8 powder dispersion from using a Stokes equation and density ratio equation prior to the demonstration. The optimum flow and experimental results of the hull separation test have been applied for the design of the demonstration oxidizer, and the operation conditions of the oxidizer were produced. (authors)
An Evaluation of the Servicemen's Opportunity College.

Science.gov (United States)

Nolan, David M.; Casserly, Patricia Lund

This study presents a preliminary evaluation of the Servicemen's Opportunity College (SOC) program. Data were obtained from the site visits and a mailed survey. Results indicated: (1) The college personnel accepted the military students as a natural part of their constituency and often commented about them as being superior to the civilian…
Draft environmental assessment: Davis Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. The site is in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Lavender Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site as one of five sites suitable for characterization. Having compared the Davis Canyon site with the other four sites proposed for nomination, the DOE has determined that the Davis Canyon site is not one of the three preferred sites for recommendation to the President as candidates for characterization
Cover technology demonstration for low-level radioactive sites

International Nuclear Information System (INIS)

Barnes, F.J.; Warren, J.L.

1988-01-01

The performance of a shallow land burial site in isolating low-level radioactive and mixed waste is strongly influenced by the behavior of the precipitation falling on the site. Predicting the long-term integrity of a cover design requires a knowledge of the water balance dynamics, and the use of predictive models. The multiplicity of factors operating on a site in the years post-closure (precipitation intensity and duration, soil conditions, vegetation seasonality and variability) have made it extremely difficult to predict the effects of natural precipitation with accuracy. Preliminary results are presented on a three-year field demonstration at Los Alamos National Laboratory to evaluate the influence of different waste trench cap designs on water balance under natural precipitation. Erosion plots having two different vegetative covers (shrubs and grasses) and with either gravel-mulched or unmulched soil surface treatments have been established on three different soil profiles on an inactive waste site. Total runoff and soil loss from each plot are measured biweekly while plant canopy cover is measured seasonally. Preliminary results from the first year show that the application of a gravel mulch reduced runoff by 73 to 90%. Total soil loss was reduced by 83 to 93% by the mulch treatment. On unmulched plots, grass cover reduced both runoff and soil loss by about 50% compared to the shrub plots. Soil moisture reduction during the growing season was more pronounced on the shrub plots. This indicates that a more complex vegetative cover provides greater soil moisture storage capacity for winter precipitation than the usual grass cover

Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-08-15

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at
Preliminary geotechnical evaluation of deep borehole facilities for nuclear waste disposal in shales

International Nuclear Information System (INIS)

Nataraj, M.S.; New Orleans Univ., LA

1991-01-01

This study is concerned with a preliminary engineering evaluation of borehole facilities for nuclear waste disposal in shales. Some of the geotechnical properties of Pierre, Rhinestreet, and typical illite shale have been collected. The influence of a few geotechnical properties on strength and deformation of host material is briefly examined. It appears that Pierre shale is very unstable and requires support to prevent collapse. Typical illite shale is more stable than Rhinestreet shale, although it undergoes relatively more deformation. 16 refs., 5 figs., 3 tabs
The evaluation of site characteristics for Guangdong nuclear power plant

International Nuclear Information System (INIS)

Zhou Ruming; Wu Dizhong; Yan Zhongmin

1987-01-01

This paper gives an account of the features of the site of Guangdong Nuclear Power Plant (GNPP) in general and in particular evaluates the outstanding site characteristics related to nuclear safety and public health. It is composed of two parts: the first part describes the seismo-geologic conditions of the site and the other treats the atmospheric dispersion conditions. It also contains the discussion why the possibility of inhabitancy within 5 km from the exclusion ares boundary would not be affected. (author)
Alaska Open-File Report 127 Assessment of Thermal Springs Sites in Southern Southeastern Alaska - Preliminary Results and Evaluation

Energy Technology Data Exchange (ETDEWEB)

Motyka, Roman J.; Moorman, Mary A.; Reeder, John W.

1980-06-01

Information has been gathered on 13 reported thermal-spring sites, 12 in southern Southeastern Alaska and one in western British Columbia. Five of the reported sites could not be substantiated by DGGS. The eight known thermal spring sites are associated with grainitic terrain and, except for Baker Island Hot Springs, occur within or near intensively fractured Cretaceous-age pluons of the Coast Range Batholith. Thermal-spring surface temperatures range from 21 C (Twin Lakes) to 91.5 C (Bailey Bay). The greatest discharge occurs at Chief Shakes hot springs (450 1pm). Bell Island Hot Springs, which has about a 100-1 pm discharge and a 70 C temperature, has had the most development. Two previously unreported thermal-spring sites, Barnes Lake warm springs and Bradfield hot springs, have a low rate of discharge and respective surface temperatures of about 25 and 54 C. The known thermal springs probably originate from circulation of meteoric waters through deep-seated fracture and fault systems. The chemical constituents of the alkali-sulfate to alkali-chloride thermal waters are probably derived from interaction of the deeply circulating meteoric waters with the granitic wall rocks. Chemical geothermometry suggests subsurface temperatures of 55 to 151 C. If waters are being heated solely by conduction from wall rocks, circulation depths must be about 1.5 to 5 km, assuming geothermal gradients of 30 to 50 C/km. Variations in temperature, discharge, and chemistry were noted at several thermal springs for which previous records are available. A major decrease in silica and potassium concentrations at Chief Shakes hot springs is suggested by comparing recent analyses of water chemistry to Waring's (1917) original analysis. The rate of discharge at Bell Island Hot Springs may have increased by a factor of two since Waring's visit to the springs. Subsurface reservoirs associated with thermal springs in southern Southeastern Alaska are of low temperature and are
Preliminary evaluation of the gaseous effluent sampling and monitoring systems at the 291-Z-1 and 296-Z-3 stacks

International Nuclear Information System (INIS)

Schwendiman, L.C.; Glissmeyer, J.A.

1992-04-01

The 291-Z-1 and 296-Z-3 stack effluent particulate sampling and monitoring systems are being evaluated for compliance with Atlantic Richfield Hanford Company's Interim Criteria for such systems. This evaluation is part of a study by Battelle-Northwest of gaseous effluent sampling systems in ARHCO facilities. This letter report presents a preliminary evaluation of the mentioned facilities and the indicated improvements needed to meet the Interim Criteria so that conceptual design work for improved systems can be initiated. There is currently underway a detailed study at the two stacks including a series of sampling experiments, the findings of which will not be included in this report. The gaseous effluent sampling system at the 291-Z-1 and 296-Z-3 stacks are very dissimilar and will be treated in separate sections of this report. The discussions for each sampling system will include a brief description and a preliminary evaluation of the systems
Evaluation of vibratory ground motion at nuclear power plant sites

International Nuclear Information System (INIS)

Hofmann, R.B.; Greeves, J.T.

1978-01-01

The evaluation of vibratory ground motion at nuclear power plant sites requires the cooperative effort of scientists and engineers in several disciplines. These include seismology, geology, geotechnical engineering and structural engineering. The Geosciences Branch of the NRC Division of Site Safety and Environmental Analysis includes two sections, the Geology/Seismology Section and the Geotechnical Engineering Section
Understanding the evolution of the repository and the olkiluoto site

International Nuclear Information System (INIS)

Koskinen, K.; Pastina, B.

2008-01-01

Posiva Safety Case is organised in a portfolio including ten main reports: Site, Spent Fuel Characteristics and Inventories, Canister Design, Repository Design, Process, Evolution of the Repository and the Site, Biosphere Assessment, Radionuclide Transport, Complementary Evaluations of Safety, and Summary. This portfolio constitutes the basis of the Preliminary Safety Assessment Report, which will be presented to the authorities in 2012 as part of the repository construction license application. The Evolution report [1], which is the focus of this paper, is the main advance in the Safety Case portfolio since the implementation of the Safety Case plan [2] in 2005. The report provides the status of current knowledge with respect to the evolution of the site and the engineered barrier system and highlights areas where better understanding is needed. (authors)
A new approach to the nuclear power plant site licensing

Energy Technology Data Exchange (ETDEWEB)

Kidron, A A [Israel Electric Corp. Ltd., Haifa (Israel)

1996-12-01

The Israel Electric Corporation Ltd.(IEC) conducted a survey to determine the geotechnical suitability of the Shivta Site for the purpose of erecting a Nuclear Power Station and presented the results in a Preliminary Safety Analysis Report (PSAR) to the Licensing Division of the Israel Atomic Energy Commission (LD). The studies for selecting a site in the NW Negev were conducted by multi-disciplinary teams of Israeli and US professionals, beginning in 1982, over a twelve-year period. The investigations involved comprehensive geological, geophysical, geotechnical, hydrological, as well as geomorphic and pedologic evaluations of the region and the then- proposed site locale. The prior studies were completed using highly advanced and modern tools and approaches and provided a significant amount of information related to the tectonic and seismic characteristics of the NW Negev region. (author).
Preliminary Evaluation of an Aviation Safety Thesaurus' Utility for Enhancing Automated Processing of Incident Reports

Science.gov (United States)

Barrientos, Francesca; Castle, Joseph; McIntosh, Dawn; Srivastava, Ashok

2007-01-01

This document presents a preliminary evaluation the utility of the FAA Safety Analytics Thesaurus (SAT) utility in enhancing automated document processing applications under development at NASA Ames Research Center (ARC). Current development efforts at ARC are described, including overviews of the statistical machine learning techniques that have been investigated. An analysis of opportunities for applying thesaurus knowledge to improving algorithm performance is then presented.
Dry-run of site investigation planning using the manual for preliminary investigation in Japan

International Nuclear Information System (INIS)

Akamura, Shigeki; Miwa, Tadashi; Tanaka, Tatsuya; Shiratsuchi, Hiroshi; Horio, Atsushi

2011-01-01

A stepwise site selection process has been adopted for geological disposal of HLW in Japan. Literature surveys, followed by preliminary investigations (PI) and, finally, detailed investigations in underground facilities will be carried out in the successive selection stages. In the PI stage, surface-based investigations such as borehole surveys and geophysical prospecting will be implemented. In order to conduct the PI appropriately and efficiently within a restricted timeframe and budget, planning and management of PI are very important. NUMO therefore compiled existing knowledge and experience in the planning and managing of investigations in the form of manuals to be used to improve and maintain internal expertise. The first editions of the two manuals were prepared on the basis of experience overseas, and then they were revised by taking technological environment, laws and regulation in Japan into consideration. This paper introduces the procedure of PI planning using manual as well as the results of the dry-run, with the Yokosuka area as a hypothetical PI area, where the monstraction study is under way. Based on the dry-run, applicability of the manual is checked and, at the same time, further revisions are made to improve the content. (author)
Shaft Siting and Configuration for Flexible Operating Mode

International Nuclear Information System (INIS)

Robert Boutin

2001-01-01

The purpose of this document as stated in the ''Technical Work Plan for Subsurface Design Section FY 01 Work Activities'' (CRWMS M and O 2001a, pg. 14) is to review and evaluate the most current concepts for shaft siting and configuration. The locations of the shaft sites will be evaluated in reference to the overall subsurface ventilation layout shown in Figure 1. The scope will include discussions on pad size requirements, shaft construction components such as collars, shaft stations, sumps, ground support and linings, head frames, fan ducting and facility equipping. In addition to these, shaft excavation methodologies and integration with the overall subsurface construction schedule will be described. The Technical Work Plan (TWP), (CRWMS M and O 2001a), for this document has been prepared in accordance with AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering and Regulatory Compliance Activities''. This document will be prepared in accordance with AP-3.10Q, ''Analysis and Models''. This document contributes to Site Recommendation (SR). The intended use of this document is to provide an analysis for shaft siting and configuration criteria for subsequent construction. This document identifies preliminary design concepts that should not be used for procurement, fabrication, or construction
The geology of the Vaalputs radioactive waste disposal site, with implications for granite-charnockite relationships and crustal evolution in western Namaqualand

International Nuclear Information System (INIS)

Andreoli, M.A.G.; Brynard, H.J.; Anderson, N.J.B.; Hart, R.J.; Moore, J.M.; Welke, H.

1990-01-01

The Precambrian geology of the Valputs site is characterized by extensive sheets of Spektakel Suite syntectonic granite gneisses. Experimental methods used for the geological evaluation of the Vaalputs site included semi-regional and site-specific mapping. All main rock types were petrologically and geochemically classified. In addition, preliminary Rb-Sr whole-rock ages were calculated for the main lithotypes, together with Sm-Nd dating. The investigations for the licensing of the Vaalputs site have revealed numerous intriguing aspects of the crustal history in southwestern Namaqualand. 10 refs
Implementing national nuclear safety plan at the preliminary stage of nuclear power project development

International Nuclear Information System (INIS)

Xue Yabin; Cui Shaozhang; Pan Fengguo; Zhang Lizhen; Shi Yonggang

2014-01-01

This study discusses the importance of nuclear power project design and engineering methods at the preliminary stage of its development on nuclear power plant's operational safety from the professional view. Specifically, we share our understanding of national nuclear safety plan's requirement on new reactor accident probability, technology, site selection, as well as building and improving nuclear safety culture and strengthening public participation, with a focus on plan's implications on preliminary stage of nuclear power project development. Last, we introduce China Huaneng Group's work on nuclear power project preliminary development and the experience accumulated during the process. By analyzing the siting philosophy of nuclear power plant and the necessity of building nuclear safety culture at the preliminary stage of nuclear power project development, this study explicates how to fully implement the nuclear safety plan's requirements at the preliminary stage of nuclear power project development. (authors)
Riel Converter Station, Winnipeg: Site selection and environmental assessment status report

International Nuclear Information System (INIS)

1991-01-01

As part of its expansion plans, Manitoba Hydro is planning to construct a converter station east of Winnipeg to receive power from a 850-km dc transmission line which will be constructed to bring power from a new generating station in the north of the province. Work performed to date on site selection and preliminary environmental assessment of the converter station is reviewed. The role of the converter station is described and the potential impacts are summarized in such areas as employment opportunities, pollution and noise during construction, electric and magnetic field effects, and land use impacts. Site selection criteria are outlined and potential sites are identified and evaluated. The Deacon site has been chosen as the preferred site since it has a number of inherent advantages including existing ownership by Manitoba Hydro, proximity to existing transmission rights-of-way, and low visual and land-use impact. 12 figs
Preliminary data for the 20 May 1974, simultaneous evaluation of remote sensors experiment. [water pollution monitoring

Science.gov (United States)

Johnson, R. W.; Batten, C. E.; Bowker, D. E.; Bressette, W. E.; Grew, G. W.

1975-01-01

Several remote sensors were simultaneously used to collect data over the tidal James River from Hopewell to Norfolk, Virginia. Sensors evaluated included the Multichannel-Ocean Color Sensor, multispectral scanners, and multispectral photography. Ground truth measurements and remotely sensed data are given. Preliminary analysis indicates that suspended sediment and concentrated industrial effluent are observable from all sensors.
CERCLA site assessment workbook

International Nuclear Information System (INIS)

1994-08-01

This contains comments for each chapter of exercises (in Vol. 1) which illustrate how to conduct site assessments for CERCLA regulation. A through analysis of the exercises is provided so that work and solutions from Vol 1 can be critiqued and comments are also included on the strategy of site assessment whereas the exercises illustrate the principles involved. Covered exercises include the following: A preliminary assessment of a ground water site; waste characteristics and characterization of sources; documentation of observed releases and actual contamination of targets; the strategy of an SI at a surface water site; the soil exposure pathway; the air pathway
Status report on geochemical field results from Atlantic study sites

International Nuclear Information System (INIS)

Wilson, T.R.S.; Thomson, J.; Hydes, D.J.; Colley, S.

1983-01-01

This report summarises the results of preliminary geochemical investigations at three North Atlantic study areas. The two eastern sites, on the Cape Verde abyssal plain (CV2) and east of Great Meteor Seamount (GME) were visited during 1982. The results presented are preliminary. Studies in the western Atlantic, close to the Nares Abyssal Plain study site are more detailed and are presented in a separate paper. The report shows for the first time the relative redox status of the three sites. The differences are unexpectedly large, the most reduced cores being recovered at GME and the most oxidised at CV2. The sporadic nature of Recent sediment accumulation at these sites is also emphasised. In order to place these preliminary results in context their relevance to the production of mathematical system models is discussed in a closing section. The necessity for such models to rest on sound foundations of geochemical understanding is noted. Suggestions on future research priorities are offered for discussion. (author)
Rock mechanics site descriptive model-theoretical approach. Preliminary site description Forsmark area - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Fredriksson, Anders; Olofsson, Isabelle [Golder Associates AB, Uppsala (Sweden)

2005-12-15

The present report summarises the theoretical approach to estimate the mechanical properties of the rock mass in relation to the Preliminary Site Descriptive Modelling, version 1.2 Forsmark. The theoretical approach is based on a discrete fracture network (DFN) description of the fracture system in the rock mass and on the results of mechanical testing of intact rock and on rock fractures. To estimate the mechanical properties of the rock mass a load test on a rock block with fractures is simulated with the numerical code 3DEC. The location and size of the fractures are given by DFN-realisations. The rock block was loaded in plain strain condition. From the calculated relationship between stresses and deformations the mechanical properties of the rock mass were determined. The influence of the geometrical properties of the fracture system on the mechanical properties of the rock mass was analysed by loading 20 blocks based on different DFN-realisations. The material properties of the intact rock and the fractures were kept constant. The properties are set equal to the mean value of each measured material property. The influence of the variation of the properties of the intact rock and variation of the mechanical properties of the fractures are estimated by analysing numerical load tests on one specific block (one DFN-realisation) with combinations of properties for intact rock and fractures. Each parameter varies from its lowest values to its highest values while the rest of the parameters are held constant, equal to the mean value. The resulting distribution was expressed as a variation around the value determined with mean values on all parameters. To estimate the resulting distribution of the mechanical properties of the rock mass a Monte-Carlo simulation was performed by generating values from the two distributions independent of each other. The two values were added and the statistical properties of the resulting distribution were determined.
Rock mechanics site descriptive model-theoretical approach. Preliminary site description Forsmark area - version 1.2

International Nuclear Information System (INIS)

Fredriksson, Anders; Olofsson, Isabelle

2005-12-01

The present report summarises the theoretical approach to estimate the mechanical properties of the rock mass in relation to the Preliminary Site Descriptive Modelling, version 1.2 Forsmark. The theoretical approach is based on a discrete fracture network (DFN) description of the fracture system in the rock mass and on the results of mechanical testing of intact rock and on rock fractures. To estimate the mechanical properties of the rock mass a load test on a rock block with fractures is simulated with the numerical code 3DEC. The location and size of the fractures are given by DFN-realisations. The rock block was loaded in plain strain condition. From the calculated relationship between stresses and deformations the mechanical properties of the rock mass were determined. The influence of the geometrical properties of the fracture system on the mechanical properties of the rock mass was analysed by loading 20 blocks based on different DFN-realisations. The material properties of the intact rock and the fractures were kept constant. The properties are set equal to the mean value of each measured material property. The influence of the variation of the properties of the intact rock and variation of the mechanical properties of the fractures are estimated by analysing numerical load tests on one specific block (one DFN-realisation) with combinations of properties for intact rock and fractures. Each parameter varies from its lowest values to its highest values while the rest of the parameters are held constant, equal to the mean value. The resulting distribution was expressed as a variation around the value determined with mean values on all parameters. To estimate the resulting distribution of the mechanical properties of the rock mass a Monte-Carlo simulation was performed by generating values from the two distributions independent of each other. The two values were added and the statistical properties of the resulting distribution were determined
Preliminary radiation shielding design for BOOMERANG

International Nuclear Information System (INIS)

Donahue, Richard J.

2002-01-01

Preliminary radiation shielding specifications are presented here for the 3 GeV BOOMERANG Australian synchrotron light source project. At this time the bulk shield walls for the storage ring and injection system (100 MeV Linac and 3 GeV Booster) are considered for siting purposes

Preliminary Evaluations of CSPACE for a Station Blackout Transient in APR1400

Energy Technology Data Exchange (ETDEWEB)

Lee, T. B.; Lee, D. K.; Lee, H. S.; Lee, G. W.; Choi, T. S. [KEPCO, Daejeon (Korea, Republic of); Park, R. J.; Kim, D. H. [KAERI, Daejeon (Korea, Republic of)

2016-05-15

This paper discusses the preliminary results of the simulated station blackout (SBO) transients using the CSPACE code and presents the information pertinent to the related safety issues. CSPACE is a merged program of a master processer of Safety and Performance Analysis Code (SPACE) for nuclear power plants and a child processer of Core Meltdown Progression Accident Simulation Software (COMPASS) generated as a dynamic-link library (DLL) codes. It has been developed to predict the best-estimate transient in the pressurized water reactor (PWR) for severe accidents. SPACE and COMPASS codes take charge of the thermal-hydraulic response of PWRs and the analysis of the severe accident progression in a vessel, respectively. The initial phase is estimated starting from time zero when the loss of off-site and on-site powers occurs simultaneously. Shortly after the RCS pressure initially falls and rises slightly due to the effects of the reactor and turbine trips, the RCS pressure declines in response to the cooling provided by heat removed to the SGs. During the period of the primary heat-up and boil-off, the RCS pressure increase is limited by two cycles of the POSRV. The RCS fluid mass is lost through the pressurizer POSRV and then the core uncovers and superheated steam flows out from the RV into the coolant loops starting at 5513.0 seconds.
Vs30 mapping at selected sites within the Greater Accra Metropolitan Area

Science.gov (United States)

Nortey, Grace; Armah, Thomas K.; Amponsah, Paulina

2018-06-01

A large part of Accra is underlain by a complex distribution of shallow soft soils. Within seismically active zones, these soils hold the most potential to significantly amplify seismic waves and cause severe damage, especially to structures sited on soils lacking sufficient stiffness. This paper presents preliminary site classification for the Greater Accra Metropolitan Area of Ghana (GAMA), using experimental data from two-dimensional (2-D) Multichannel Analysis of Surface Wave (MASW) technique. The dispersive characteristics of fundamental mode Rayleigh type surface waves were utilized for imaging the shallow subsurface layers (approx. up to 30 m depth) by estimating the 1D (depth) and 2D (depth and surface location) shear wave velocities at 5 selected sites. The average shear wave velocity for 30 m depth (Vs30), which is critical in evaluating the site response of the upper 30 m, was estimated and used for the preliminary site classification of the GAM area, as per NEHRP (National Earthquake Hazards Reduction Program). Based on the Vs30 values obtained in the study, two common site types C, and D corresponding to shallow (>6 m Lower velocity profiles are inferred for the residual soils (sandy to silty clays), derived from the Accraian Formation that lies mainly within Accra central. Stiffer soil sites lie to the north of Accra, and to the west near Nyanyano. The seismic response characteristics over the residual soils in the GAMA have become apparent using the MASW technique. An extensive site effect map and a more robust probabilistic seismic hazard analysis can now be efficiently built for the metropolis, by considering the site classes and design parameters obtained from this study.
Workshop material for state review of USNRC site suitability criteria for high-level radioactive waste repositories

International Nuclear Information System (INIS)

1977-08-01

The Nuclear Regulatory Commission (NRC) is developing criteria on which to judge whether a proposed site for a geologic repository is suitable for disposal of high-level nuclear wastes. To aid in its analysis and assessment, NRC is planning three early independent reviews of the site suitability criteria development effort: a peer review by experts outside of NRC; a review by the National Academy of Sciences; and a review by State officials. This document has been prepared to aid workshop participants in understanding the Preliminary Site Suitability Criteria and to prepare them to contribute to an evaluation of those criteria
Status of siting studies for a near surface repository site for radioactive wastes in the Philippines

International Nuclear Information System (INIS)

Valdezco, E.M.; Palattao, M.V.B.; Marcelo, E.A.; Caseria, E.S.; Venida, L.L.; Cruz, J.M. dela

2002-01-01

The Philippines, through the Philippine Nuclear Research Institute (PNRI), decided to conduct a study on siting a low level radioactive waste disposal facility. The infrastructure set up for this purpose, the radioactive waste disposal concept, the overall siting process, the methodology applied and preliminary results obtained are described in this paper. (author)
Site identification: environmental and radiological considerations

International Nuclear Information System (INIS)

Waite, D.A.

1980-01-01

Radiological and environmental considerations are recognized as being of utmost importance in planning, siting, licensing, operating, and decommissioning a high-level nuclear waste repository. In such a complex undertaking, it is important to identify the major concerns anticipated to arise in all of these phases in order to address them as early as possible in the program. Three representative activities/studies are summarized which will identify some of the important radiological and environmental considerations which must be addressed through this prolonged sequence of events and will indicate how these considerations are being addressed. It should be emphasized that these are only three of many which could have been chosen. The three key activities/studies are: (1) the NWTS Program criteria for identifying repository sites, (2) the generic guide for preparing environmental evaluations for deep drilling and (3) a preliminary environmental assessment for disposal of mined rock during excavation of a repository
Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-09-01

This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km{sup 2} (570-mi{sup 2}) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation.
Environmental Survey preliminary report

Energy Technology Data Exchange (ETDEWEB)

1988-04-01

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Sandia National Laboratories conducted August 17 through September 4, 1987. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with Sandia National Laboratories-Albuquerque (SNLA). The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at SNLA, and interviews with site personnel. 85 refs., 49 figs., 48 tabs.
Evaluating Seismic Site Effects at Cultural Heritage Sites in the Mediterranean Area

Science.gov (United States)

Imposa, S.; D'Amico, S.; Panzera, F.; Lombardo, G.; Grassi, S.; Betti, M.; Muscat, R.

2017-12-01

Present study concern integrated geophysical and numerical simulation aiming at evaluate the seismic vulnerability of cultural heritage sites. Non-invasive analysis targeted to characterize local site effects as well as dynamic properties of the structure were performed. Data were collected at several locations in the Maltese Archipelago (central Mediterranean) and in some historical buildings located in Catania (Sicily). In particular, passive seismic techniques and H/V data where used to derive 1D velocity models and amplification functions. The dynamic properties of a building are usually described through its natural frequency and the damping ratio. This latter is important in seismic design since it allows one to evaluate the ability of a structure to dissipate the vibration energy during an earthquake. The fundamental frequency of the investigated structure was obtained using ambient vibrations recorded by two or more sensors monitoring the motion at different locations in the building. Accordingly, the fundamental period of several Maltese Watchtowers and some historical buildings of Catania were obtained by computing the ratio between the amplitudes of the Fourier spectrum of horizontal (longitudinal and transverse) components recorded on the top and on the ground floors. Using ANSYS code, the modal analysis was performed to evaluate the first 50 vibration modes with the aim to check the activation of the modal masses and to assess the seismic vulnerability of the tower. The STRATA code was instead adopted in the Catania heritage buildings using as reference earthquake moderate to strong shocks that struck south-eastern Sicily. In most of the investigated buildings is was not possible to identify a single natural frequency but several oscillation modes. These results appear linked to the structural complexity of the edifices, their irregular plan shape and the presence of adjacent structures. The H/V outside the buildings were used to determine predominant
A Serious Games Platform for Cognitive Rehabilitation with Preliminary Evaluation.

Science.gov (United States)

Rego, Paula Alexandra; Rocha, Rui; Faria, Brígida Mónica; Reis, Luís Paulo; Moreira, Pedro Miguel

2017-01-01

In recent years Serious Games have evolved substantially, solving problems in diverse areas. In particular, in Cognitive Rehabilitation, Serious Games assume a relevant role. Traditional cognitive therapies are often considered repetitive and discouraging for patients and Serious Games can be used to create more dynamic rehabilitation processes, holding patients' attention throughout the process and motivating them during their road to recovery. This paper reviews Serious Games and user interfaces in rehabilitation area and details a Serious Games platform for Cognitive Rehabilitation that includes a set of features such as: natural and multimodal user interfaces and social features (competition, collaboration, and handicapping) which can contribute to augment the motivation of patients during the rehabilitation process. The web platform was tested with healthy subjects. Results of this preliminary evaluation show the motivation and the interest of the participants by playing the games.
Preliminary rock mechanics laboratory: Investigation plan

International Nuclear Information System (INIS)

Oschman, K.P.; Hummeldorf, R.G.; Hume, H.R.; Karakouzian, M.; Vakili, J.E.

1987-01-01

This document presents the rationale for rock mechanics laboratory testing (including the supporting analysis and numerical modeling) planned for the site characterization of a nuclear waste repository in salt. This plan first identifies what information is required for regulatory and design purposes, and then presents the rationale for the testing that satisfies the required information needs. A preliminary estimate of the minimum sampling requirements for rock laboratory testing during site characterization is also presented. Periodic revision of this document is planned
Evaluation of physical activity web sites for use of behavior change theories.

Science.gov (United States)

Doshi, Amol; Patrick, Kevin; Sallis, James F; Calfas, Karen

2003-01-01

Physical activity (PA) Web sites were assessed for their use of behavior change theories, including constructs of the health belief model, Transtheoretical Model, social cognitive theory, and the theory of reasoned action and planned behavior. An evaluation template for assessing PA Web sites was developed, and content validity and interrater reliability were demonstrated. Two independent raters evaluated 24 PA Web sites. Web sites varied widely in application of theory-based constructs, ranging from 5 to 48 on a 100-point scale. The most common intervention strategies were general information, social support, and realistic goal areas. Coverage of theory-based strategies was low, varying from 26% for social cognitive theory to 39% for health belief model. Overall, PA Web sites provided little assessment, feedback, or individually tailored assistance for users. They were unable to substantially tailor the on-line experience for users at different stages of change or different demographic characteristics.
Preliminary site survey report for the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001)

International Nuclear Information System (INIS)

Foley, R.D.; Floyd, L.M.

1990-03-01

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted a preliminary radiological survey at the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001), in 1988. The purpose of the survey was to determine whether the property was contaminated with radioactive residues from the former Manhattan Engineer District (MED) project. The scope of this preliminary survey primarily covered the area west of the buildings around the railroad car spill containment basin. The survey included direct measurement of gamma radiation levels at the surface and soil sampling for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria for both 238 U and 226 Ra in soil. Based on the results of this radiological assessment, it is recommended that a follow-up, detailed radiological survey of both surface and subsurface environs be performed to more precisely define the extent of the contamination. 5 refs., 10 figs., 3 tabs
Preliminary safety evaluation for a medical therapy reactor

International Nuclear Information System (INIS)

Jones, J.L.; Neuman, W.A.

1989-01-01

A conceptual design of a passively safe reactor facility for boron neutron capture therapy has been previously described. The medical therapy reactor (MTR) has a maximum power level of 10 MW(thermal) and utilizes 45 wt% uranium in UZrH, 20 wt% 235 U enriched hydride fuel matrix with 1 wt% erbium, which is a burnable poison and provides prompt negative reactivity feedback. The facility has five beam ports for patient treatment and advanced neutron beam research and is capable of 2,000 to 10,000 treatments per year, assuming single 8h/day, 5 day/week operation. The epithermal treatment flux from the beam ports is large, enabling single-session treatment of brain cancers of <10-min duration, with minimal fast neutron and gamma contaminants. The reactor core is designed with sufficient excess reactivity to yield a core lifetime equal to a facility lifetime of 30 yr. A preliminary safety evaluation was performed using the RELAP5 thermal-hydraulic code. The analysis addressed accidents in several major categories, including a pump coastdown, a loss of secondary heat sink, and a $0.5 step reactivity insertion
Transport properties site descriptive model. Guidelines for evaluation and modelling

International Nuclear Information System (INIS)

Berglund, Sten; Selroos, Jan-Olof

2004-04-01

This report describes a strategy for the development of Transport Properties Site Descriptive Models within the SKB Site Investigation programme. Similar reports have been produced for the other disciplines in the site descriptive modelling (Geology, Hydrogeology, Hydrogeochemistry, Rock mechanics, Thermal properties, and Surface ecosystems). These reports are intended to guide the site descriptive modelling, but also to provide the authorities with an overview of modelling work that will be performed. The site descriptive modelling of transport properties is presented in this report and in the associated 'Strategy for the use of laboratory methods in the site investigations programme for the transport properties of the rock', which describes laboratory measurements and data evaluations. Specifically, the objectives of the present report are to: Present a description that gives an overview of the strategy for developing Site Descriptive Models, and which sets the transport modelling into this general context. Provide a structure for developing Transport Properties Site Descriptive Models that facilitates efficient modelling and comparisons between different sites. Provide guidelines on specific modelling issues where methodological consistency is judged to be of special importance, or where there is no general consensus on the modelling approach. The objectives of the site descriptive modelling process and the resulting Transport Properties Site Descriptive Models are to: Provide transport parameters for Safety Assessment. Describe the geoscientific basis for the transport model, including the qualitative and quantitative data that are of importance for the assessment of uncertainties and confidence in the transport description, and for the understanding of the processes at the sites. Provide transport parameters for use within other discipline-specific programmes. Contribute to the integrated evaluation of the investigated sites. The site descriptive modelling of
Preliminary Evaluation of MapReduce for High-Performance Climate Data Analysis

Science.gov (United States)

Duffy, Daniel Q.; Schnase, John L.; Thompson, John H.; Freeman, Shawn M.; Clune, Thomas L.

2012-01-01

MapReduce is an approach to high-performance analytics that may be useful to data intensive problems in climate research. It offers an analysis paradigm that uses clusters of computers and combines distributed storage of large data sets with parallel computation. We are particularly interested in the potential of MapReduce to speed up basic operations common to a wide range of analyses. In order to evaluate this potential, we are prototyping a series of canonical MapReduce operations over a test suite of observational and climate simulation datasets. Our initial focus has been on averaging operations over arbitrary spatial and temporal extents within Modern Era Retrospective- Analysis for Research and Applications (MERRA) data. Preliminary results suggest this approach can improve efficiencies within data intensive analytic workflows.
Preliminary evaluation of the expected radiation damage of the bayonet IFMIF back-plate

Energy Technology Data Exchange (ETDEWEB)

Frisoni, M. [Athena s.a.s, Via del Battiferro 3, I-40129 Bologna (Italy)], E-mail: manuela.frisoni@enea.it; Agostini, P. [ENEA CR Brasimone, Bacino del Brasimone 40032, Camugnano (Bolivia, Plurinational State of) (Italy); Fasanella, D. [Athena s.a.s, Via del Battiferro 3, I-40129 Bologna (Italy); Micciche, G. [ENEA CR Brasimone, Bacino del Brasimone 40032, Camugnano (Bolivia, Plurinational State of) (Italy)

2009-06-15

This paper summarises and discusses the results of a preliminary damage assessment of the non-seizure coating of the bayonet IFMIF back-plate. Neutron-induced kerma factors, dpa and gas production cross sections libraries were produced in a multigroup structure for neutron energies up to 60 MeV, by processing evaluated nuclear data files with NJOY-99.259 system. The material damage evaluations in terms of heat deposition, displacement and gas production rates were calculated using these libraries and compared with the values obtained using the data contained in the pointwise ACE format files of MCNP5 code package. The calculations were performed with MCNP5 code both using the McEnea and the McDelicious neutron source models to reproduce the energy-angle distributions of the neutrons produced in IFMIF d-Li interactions.
THE IMPORTANCE OF WEB DESIGN: VISUAL DESIGN EVALUATION OF DESTINATION WEB SITES

OpenAIRE

Fırlar, Belma; Okat Özdem, Özen

2013-01-01

As in the literature, the researchs about web site efficiency are mostly about site context. The analysis about function are mostly superficial. Whereas, controlling every little part of a web site respective is a necessity to show its efficiency. Here in this context in the study of perception and response event web sites that play an important role in visual design criteria are below the lens as featured and the web sites evaulated by heuristic evaluation method.The research focus of this s...
Planning for investigation and evaluation of potential repository sites in Sweden

International Nuclear Information System (INIS)

Almen, K.E.; Stroem, A.

1998-01-01

The present stage of siting of the Swedish Deep Repository for spent nuclear fuel involves general siting studies on national and regional scales and feasibility studies on a municipal scale. Based on these studies, two areas will be selected for surface-based site investigations. The geoscientific site information will be used in the site evaluation process, in which performance and safety assessments and design studies are the major activities, in combination with geoscientific characterization. The safety report and EIA document from the site investigation stage will be the most important documents in the application for the siting permit and the permit to construct the deep repository. Detailed characterization will then verify the suitability of the selected site. The programme for geoscientific site investigations is based on experience from more than 20 years of field studies in several SKB projects, such as the Study Site Investigations , the Stripa Project, and the Aespoe Hard Rock Laboratory. The strategies and methodologies developed, implemented and verified within the Aespoe HRL are a very important source of information and know-how for the development of the site investigation programme. The investigations will produce geoscientific models that include all information needed to analyze the long-term safety of a deep repository located in and adapted to the geological conditions of the rock. The type of geoscientific information needed for performance and safety assessment, layout and design, environmental studies and for fundamental geoscientific understanding has been specified and compiled in a 'parameter' report. The general strategy is that performance assessment, layout and design studies will be conducted in parallel with the geoscientific investigations. Information will be transferred at logical occasions, when decisions have to be taken and when feedback is desirable for new investigation steps. The role of the geoscientific evaluation is to
An experimental apparatus to simulate body-powered prosthetic usage: Development and preliminary evaluation.

Science.gov (United States)

Gao, Fan; Rodriguez, Johanan; Kapp, Susan

2016-06-01

Harness fitting in the body-powered prosthesis remains more art than science due to a lack of consistent and quantitative evaluation. The aim of this study was to develop a mechanical, human-body-shaped apparatus to simulate body-powered upper limb prosthetic usage and evaluate its capability of quantitative examination of harness configuration. The apparatus was built upon a torso of a wooden mannequin and integrated major mechanical joints to simulate terminal device operation. Sensors were used to register cable tension, cable excursion, and grip force simultaneously. The apparatus allowed the scapula to move up to 127 mm laterally and the load cell can measure the cable tension up to 445 N. Our preliminary evaluation highlighted the needs and importance of investigating harness configurations in a systematic and controllable manner. The apparatus allows objective, systematic, and quantitative evaluation of effects of realistic harness configurations and will provide insightful and working knowledge on harness fitting in upper limb amputees using body-powered prosthesis. © The International Society for Prosthetics and Orthotics 2015.
242Pu: Preliminary evaluation with consideration of 240Pu, and some sensitivity results

International Nuclear Information System (INIS)

Jary, J.; Lagrange, C.; Philis, C.

1978-01-01

A preliminary evaluation of 242 Pu nuclear data is presented for the neutron energy range from 10 keV to 20 MeV. The fission cross section is based upon recent experimental measurements on 242 Pu. The remaining cross sections have been calculated using various nuclear models with parameters obtained mainly by both fits on 240 Pu experimental data and general reflexions on the actinides. Particular care has been taken of the direct interactions. The laws of secondary neutron energy spectra and the average number of neutrons produced per fission have been evaluated. The results have been placed in ENDF/BIV format and combined with the low energy region of ENDF/BIV MAT = 1161 data to make complete the evaluation over the whole energy range 10 -5 eV - 20 MeV. Finally, the sensitivities of some of these nuclear data available for reactor calculations are given in terms of the variation of the calculated critical masses

Evaluation of Phosphorus Site Assessment Tools: Lessons from the USA.

Science.gov (United States)

Sharpley, Andrew; Kleinman, Peter; Baffaut, Claire; Beegle, Doug; Bolster, Carl; Collick, Amy; Easton, Zachary; Lory, John; Nelson, Nathan; Osmond, Deanna; Radcliffe, David; Veith, Tamie; Weld, Jennifer

2017-11-01

Critical source area identification through phosphorus (P) site assessment is a fundamental part of modern nutrient management planning in the United States, yet there has been only sparse testing of the many versions of the P Index that now exist. Each P site assessment tool was developed to be applicable across a range of field conditions found in a given geographic area, making evaluation extremely difficult. In general, evaluation with in-field monitoring data has been limited, focusing primarily on corroborating manure and fertilizer "source" factors. Thus, a multiregional effort (Chesapeake Bay, Heartland, and Southern States) was undertaken to evaluate P Indices using a combination of limited field data, as well as output from simulation models (i.e., Agricultural Policy Environmental eXtender, Annual P Loss Estimator, Soil and Water Assessment Tool [SWAT], and Texas Best Management Practice Evaluation Tool [TBET]) to compare against P Index ratings. These comparisons show promise for advancing the weighting and formulation of qualitative P Index components but require careful vetting of the simulation models. Differences among regional conclusions highlight model strengths and weaknesses. For example, the Southern States region found that, although models could simulate the effects of nutrient management on P runoff, they often more accurately predicted hydrology than total P loads. Furthermore, SWAT and TBET overpredicted particulate P and underpredicted dissolved P, resulting in correct total P predictions but for the wrong reasons. Experience in the United States supports expanded regional approaches to P site assessment, assuming closely coordinated efforts that engage science, policy, and implementation communities, but limited scientific validity exists for uniform national P site assessment tools at the present time. Copyright © by the American Society of Agronomy, Crop Science Society of America, and Soil Science Society of America, Inc.
On-site and laboratory evaluations of soundscape quality in recreational urban spaces

DEFF Research Database (Denmark)

Bjerre, Lærke Cecilie; Larsen, Thea Mathilde; Sørensen, Anna Josefine

2017-01-01

Regulations for quiet urban areas are typically based on sound level limits alone. However, the nonacoustic context may be crucial for subjective soundscape quality. Aims: This study aimed at comparing the role of sound level and nonacoustic context for subjective urban soundscape assessment...... in the presence of the full on-site context, the visual context only, and without context. Materials and Methods: Soundscape quality was evaluated for three recreational urban spaces by using four subjective attributes: loudness, acceptance, stressfulness, and comfort. The sound level was measured at each site......, the availability of the visual context in the listening experiment had no significant effect on the ratings. The participants were overall more positive toward natural sound sources on site. Conclusion: The full immersion in the on-site nonacoustic context may be important when evaluating overall soundscape...
Methodology of site protection studies

International Nuclear Information System (INIS)

Farges, L.

1980-01-01

Preliminary studies preceding building of a nuclear facility aim at assessing the choice of a site and establishing operating and control procedures. These studies are of two types. Studies on the impact of environment on the nuclear facility to be constructed form one type and studies on the impact of nuclear facilities on the environment form the second type. A methodology giving a framework to studies of second type is presented. These studies are undertaken to choose suitable sites for nuclear facilities. After a preliminary selection of a site based on the first estimate, a detailed site study is undertaken. The procedure for this consists of five successive phases, namely, (1) an inquiry assessing the initial state of the site, (2) an initial synthesis of accumulated information for assessing the health and safety consequences of releases, (3) laboratory and field studies simulating the movement of waste products for a quantitative assessment of effects, (4) final synthesis for laying down the release limits and radiological control methods, and (5) conclusions based on comparing the data of final synthesis to the limits prescribed by regulations. These five phases are outlined. Role of periodic reassessments after the facility is in operation for same time is explained. (M.G.B.)
Evaluating suspect sites open-quotes to clean or not to clean?close quotes

International Nuclear Information System (INIS)

Murray, M.E.; Coleman, R.L.; Tiner, P.F.

1996-01-01

Within many large government reservations are many sites that are potentially contaminated from various uses such as experiments, material storage, or material processes. There also exist many smaller areas that, by proximity to contaminated sites, or due to work contracts, are likely to be contaminated. The party responsible for such sites must evaluate if remediation is required, based on current guidelines and future uses. The Departments of Defense and Energy have many sites and properties that are suspected of being contaminated or associated with operations that could cause contamination. In some cases the contaminants may have been adequately cleaned up, then decayed away, biodegraded, or dispersed to a nondetectable level. The decision to remove these sites from any further consideration of remediation or control must be based on historical data, potential contaminants, current analytical data, future uses, and the cost associated with managing the sites. This paper deals with the methodology for evaluating small sites and gives some case studies
Preliminary nuclear decommissioning cost study

International Nuclear Information System (INIS)

Sissingh, R.A.P.

1981-04-01

The decommissioning of a nuclear power plant may involve one or more of three possible options: storage with surveillance (SWS), restricted site release (RSR), and unrestricted site use(USU). This preliminary study concentrates on the logistical, technical and cost aspects of decommissioning a multi-unit CANDU generating station using Pickering GS as the reference design. The procedure chosen for evaluation is: i) removal of the fuel and heavy water followed by decontamination prior to placing the station in SWS for thiry years; ii) complete dismantlement to achieve a USU state. The combination of SWS and USU with an interim period of surveillance allows for radioactive decay and hence less occupational exposure in achieving USU. The study excludes the conventional side of the station, assumes waste disposal repositories are available 1600 km away from the station, and uses only presently available technologies. The dismantlement of all systems except the reactor core can be accomplished using Ontario Hydro's current operating, maintenance and construction procedures. The total decommissioning period is spread out over approximately 40 years, with major activities concentrated in the first and last five years. The estimated dose would be approximately 1800 rem. Overall Pickering GS A costs would be $162,000,000 (1980 Canadian dollars)
Preliminary Evaluation Methodology of ECCS Performance for Design Basis LOCA Redefinition

International Nuclear Information System (INIS)

Kang, Dong Gu; Ahn, Seung Hoon; Seul, Kwang Won

2010-01-01

To improve their existing regulations, the USNRC has made efforts to develop the risk-informed and performance-based regulation (RIPBR) approaches. As a part of these efforts, the rule revision of 10CFR50.46 (ECCS Acceptance Criteria) is underway, considering some options for 4 categories of spectrum of break sizes, ECCS functional reliability, ECCS evaluation model, and ECCS acceptance criteria. Since the potential for safety benefits and unnecessary burden reduction from design basis LOCA redefinition is high relative to other options, the USNRC is proceeding with the rulemaking for design basis LOCA redefinition. An instantaneous break with a flow rate equivalent to a double ended guillotine break (DEGB) of the largest primary piping system in the plant is widely recognized as an extremely unlikely event, while redefinition of design basis LOCA can affect the existing regulatory practices and approaches. In this study, the status of the design basis LOCA redefinition and OECD/NEA SMAP (Safety Margin Action Plan) methodology are introduced. Preliminary evaluation methodology of ECCS performance for LOCA is developed and discussed for design basis LOCA redefinition
SITEQUAL--A User's Guide: Computerized Site Evaluation for 14 Southern Hardwood Species

Science.gov (United States)

Constance A. Harrington; Bettina M. Casson

1986-01-01

An interactive computer program, SITEQUAL, has been developed from the widely-used Baker and Broadfoot field guides, which evaluate site quality for 14 southern hardwood tree species. The SITEQUAL program calculates site index for all species simultaneously and provides a breakdown of site index into the component contributions by each of the four major soil factors...
Evaluation methodology for flood damage reduction by preliminary water release from hydroelectric dams

Science.gov (United States)

Ando, T.; Kawasaki, A.; Koike, T.

2017-12-01

IPCC AR5 (2014) reported that rainfall in the middle latitudes of the Northern Hemisphere has been increasing since 1901, and it is claimed that warmer climate will increase the risk of floods. In contrast, world water demand is forecasted to exceed a sustainable supply by 40 percent by 2030. In order to avoid this expectable water shortage, securing new water resources has become an utmost challenge. However, flood risk prevention and the secure of water resources are contradictory. To solve this problem, we can use existing hydroelectric dams not only as energy resources but also for flood control. However, in case of Japan, hydroelectric dams take no responsibility for it, and benefits have not been discussed accrued by controlling flood by hydroelectric dams, namely by using preliminary water release from them. Therefore, our paper proposes methodology for assessing those benefits. This methodology has three stages as shown in Fig. 1. First, RRI model is used to model flood events, taking account of the probability of rainfall. Second, flood damage is calculated using assets in inundation areas multiplied by the inundation depths generated by that RRI model. Third, the losses stemming from preliminary water release are calculated, and adding them to flood damage, overall losses are calculated. We can evaluate the benefits by changing the volume of preliminary release. As a result, shown in Fig. 2, the use of hydroelectric dams to control flooding creates 20 billion Yen benefits, in the probability of three-day-ahead rainfall prediction of the assumed maximum rainfall in Oi River, in the Shizuoka Pref. of Japan. As the third priority in the Sendai Framework for Disaster Risk Reduction 2015-2030, `investing in disaster risk reduction for resilience - public and private investment in disaster risk prevention and reduction through structural and non-structural measures' was adopted. The accuracy of rainfall prediction is the key factor in maximizing the benefits
A preliminary study of archaeological ceramic from the Sao Paulo II, Brazil, archaeological site by Instrumental Neutron Activation Analysis (INAA)

International Nuclear Information System (INIS)

Ribeiro, Rogerio B.; Munita, Casimiro S.; Oliveira, Paulo M.S.; Neves, Eduardo G.; Tamahara, Eduardo K.

2011-01-01

The determination of trace elements plays an important role in the characterization of archaeological ceramics. It is well established that ceramics can be grouped based on similarities/dissimilarities derived from chemical data. Different analytical methods can be applied to determine the sample composition. Instrumental neutron activation analysis (INAA) is the method preferred because present several advantages in relation to the other techniques. In this work, the elements determined were As, K, La, Lu, Na, Nd, Sb, Sm, U, Yb, Ba, Ce, Co, Cr, Cs, I, Fe, Hf, Rb, Sc, Ta , Tb, Th and Zn to carry out a preliminary chemical characterization in 44 ceramic samples from Sao Paulo II archaeological site by INAA. The site is located in Coari city, 363 km from Manaus, Amazonas state (AM). The elementary concentration results were studied using multivariate statistical methods. The similarity/dissimilarity among the samples was studied by means of discriminant analysis. The compositions group classification was done through cluster analysis, showing the formation of the three distinct groups of the ceramics. (author)
Evaluation of the impact of a committed site on fusion reactor development

International Nuclear Information System (INIS)

Reid, R.L.; Nagy, A.

1979-01-01

The technical and economic merits of a committed fusion site for development of tokamak, mirror, and EBT reactor from ignition through demo phases were evaluated. Schedule compression resulting from evolving several reactor concepts and/or phases on a committed site as opposed to sequential use of independent sites was estimated. Land, water, and electrical power requirements for a committed fusion site were determined. A conceptual plot plan for siting three fusion reactors on a committed site was configured. Reactor support equipment common to the various concepts was identified as candidates for sharing. Licensing issues for fusion plants were briefly addressed
Site characterization and validation. Stage 2 - Preliminary predictions

International Nuclear Information System (INIS)

Olsson, O.; Black, J.H.; Gale, J.E.; Holmes, D.C.

1989-05-01

The Site Characterization and Validation (SCV) project is designed to assess how well we can characterize a volume of rock prior to using it as a repository. The programme of work focuses on the validation of the techniques used in site characterization. The SCV project contains 5 stages of work arranged in two 'cycles' of data-gathering, prediction, and validation. The first stage of work has included drilling of 6 boreholes (N2, N3, N4, W1, W2 and V3) and measurements of geology, fracture characteristics, stess, single borehole geophysical logging, radar, seismics and hydrogeology. The rock at the SCV site is granite with small lithological variations. Based essentially on radar and seismic results 5 'fracture zones' have been identified, named GA, GB, GC, GH and GI. They all extend acroos the entire SCV site. They aer basically in in two groups (GA, GB, GC and GH, GI). The first group are aligned N40 degree E with a dip of 35 degree to the south. The second group are aligned approximately N10 degree W dipping 60 degree E. From the stochastic analysis of the joint data it was possible to identify three main fracture orientation clusters. The orientation of two of these clusters agree roughly with orientation of the main features. Cluster B has roughly the same orientation as GH and GI, while features GA, GB and GC have an orientation similar to the more loosely defined cluster C. The orientation of the third cluster (A) is northwest with a dip to northeast. It is found that 94% of all measured hydraulic transmissivity is accounted for by 4% of the tested rock, not all of this 'concentrated' transmissivity is with the major features defined by geophysics. When the hydraulic connections across the site are examied they show that there are several welldefined zones which permit rapid transmission of hydraulic signals. These are essentially from the northeast to the southwest. (66 figs., 21 tabs., 33 refs.)
Evaluation of Aqua-Ammonia Chiller Technologies and Field Site Installation

Energy Technology Data Exchange (ETDEWEB)

Zaltash, Abdolreza [ORNL

2007-09-01

The Naval Facilities Engineering Service Center (NFESC) has sponsored Oak Ridge National Laboratory (ORNL) to review, select, and evaluate advanced, gas-fired, 5-ton, aqua-ammonia, chiller technologies. The selection criteria was that units have COP values of 0.67 or better at Air-conditioning and Refrigeration Institute (ARI) 95 F outdoor rating conditions, an active refrigerant flow control, and a variable-speed condenser fan. These features are expected to allow these units to operate at higher ambient temperatures (up to the maximum operating temperature of 110 F) with minimal degradation in performance. ORNL evaluated three potential manufacturers of advanced, gas-fired, 5-ton, aqua-ammonia chillers-Robur, Ambian, and Cooling Technologies. Unfortunately, Robur did not meet the COP requirements and Cooling Technologies could not deliver a unit to be tested at the U.S. Department of Energy (DOE)-ORNL environmental chamber testing facility for thermally activated heat pumps. This eliminated these two technologies from further consideration, leaving only the Ambian chillers for evaluation. Two Ambian chillers were evaluated at the DOE-ORNL test facility. Overall these chillers operated well over a wide range of ambient conditions with minimal degradation in performance due to several control strategies used such as a variable speed condenser fan, a modulating burner, and active refrigerant flow control. These Ambian pre-commercial units were selected for installation and field testing at three federal facilities. NFESC worked with ORNL to assist with the site selection for installation and evaluation of these chillers. Two sites (ORNL and Naval Surface Warfare Center [NSWC] Corona) had a single chiller unit installed; and at one site (Naval Amphibious Base [NAB] Little Creek), two 5-ton chillers linked together were installed to provide 10 tons of cooling. A chiller link controller developed under this project was evaluated in the field test at Little Creek.
Properties of ABNT 41xx and 86xx cast steel modified with niobium; evaluation methodology and experimental preliminary results

International Nuclear Information System (INIS)

Suzczynski, E.F.; Chatterjee, S.; Mueller, Arno

1982-01-01

The experimental methodology to evaluate the mechanical properties of ABNT 41xx and 86xx steels modified with NB in the as cast and heat treated conditions and the first preliminary results obtained in a laboratory scale, are presented. (Author) [pt
Chemical dechlorination of pesticides at a superfund site in Region II

International Nuclear Information System (INIS)

Pendergrass, S.; Prince, J.

1991-01-01

Selecting technologies for cleaning up hazardous waste sites is a complex task, due in part to the rapidly changing nature of the state-of-the-art in technology. There is strong support for use of innovative technologies as specified in Section 121(b) of CERCLA. However, use of an innovative technology requires overcoming a variety of challenges. These challenges include: Screening potentially appropriate technologies, including innovative technologies, and selecting one or more potential innovative technologies for which preliminary results are promising; however, site-specific data are needed prior to technology evaluation. Evaluating the effectiveness of the proposed technology for the site through the use of treatability studies. Gaining acceptance for the innovative technology, which may employ new or unfamiliar concepts. Determining optimal design and operating parameters for full-scale remediation. This paper discusses the technology evaluation process and how that process supported the selection of an innovative technology for the Myers Property site, a Superfund site in Region II. A case study is presented showing how technology screening and laboratory treatability studies were used to evaluate an innovative technology (chemical dechlorination), which was selected as the technology for remediation of soils and sediments contaminated with pesticides at this environmentally sensitive site in New Jersey. The remedy selected by the U.S. EPA for this site designates chemical dechlorination as the selected technology, but does not specify any particular vendor or process. Rather, the remedy sets forth technology performance standards and recommends certain design tasks which may be used to select a particular chemical process. This paper discusses he of these design tasks as they might apply to innovative technologies, using chemical dechlorination as a model
Hydrogeological DFN modelling using structural and hydraulic data from KLX04. Preliminary site description Laxemar subarea - version 1.2

Energy Technology Data Exchange (ETDEWEB)

Follin, Sven [SF GeoLogic AB, Taeby (Sweden); Stigsson, Martin [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Svensson, Urban [Computer-aided Fluid Engineering AB, Norrkoeping (Sweden)

2006-04-15

SKB is conducting site investigations for a high-level nuclear waste repository in fractured crystalline rocks at two coastal areas in Sweden. The two candidate areas are named Forsmark and Simpevarp. The site characterisation work is divided into two phases, an initial site investigation phase (ISI) and a complete site investigation phase (CSI). The results of the ISI phase are used as a basis for deciding on the subsequent CSI phase. On the basis of the CSI investigations a decision is made as to whether detailed characterisation will be performed (including sinking of a shaft). An integrated component in the site characterisation work is the development of site descriptive models. These comprise basic models in three dimensions with an accompanying text description. Central in the modelling work is the geological model which provides the geometrical context in terms of a model of deformation zones and the less fractured rock mass between the zones. Using the geological and geometrical description models as a basis, descriptive models for other disciplines (surface ecosystems, hydrogeology, hydrogeochemistry, rock mechanics, thermal properties and transport properties) will be developed. Great care is taken to arrive at a general consistency in the description of the various models and assessment of uncertainty and possible needs of alternative models. The main objective of this study is to support the development of a hydrogeological DFN model (Discrete Fracture Network) for the Preliminary Site Description of the Laxemar area on a regional-scale (SDM version L1.2). A more specific objective of this study is to assess the propagation of uncertainties in the geological DFN modelling reported for L1.2 into the groundwater flow modelling. An improved understanding is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. The latter will serve as a basis for describing the present
Hydrogeological DFN modelling using structural and hydraulic data from KLX04. Preliminary site description Laxemar subarea - version 1.2

International Nuclear Information System (INIS)

Follin, Sven; Stigsson, Martin; Svensson, Urban

2006-04-01

SKB is conducting site investigations for a high-level nuclear waste repository in fractured crystalline rocks at two coastal areas in Sweden. The two candidate areas are named Forsmark and Simpevarp. The site characterisation work is divided into two phases, an initial site investigation phase (ISI) and a complete site investigation phase (CSI). The results of the ISI phase are used as a basis for deciding on the subsequent CSI phase. On the basis of the CSI investigations a decision is made as to whether detailed characterisation will be performed (including sinking of a shaft). An integrated component in the site characterisation work is the development of site descriptive models. These comprise basic models in three dimensions with an accompanying text description. Central in the modelling work is the geological model which provides the geometrical context in terms of a model of deformation zones and the less fractured rock mass between the zones. Using the geological and geometrical description models as a basis, descriptive models for other disciplines (surface ecosystems, hydrogeology, hydrogeochemistry, rock mechanics, thermal properties and transport properties) will be developed. Great care is taken to arrive at a general consistency in the description of the various models and assessment of uncertainty and possible needs of alternative models. The main objective of this study is to support the development of a hydrogeological DFN model (Discrete Fracture Network) for the Preliminary Site Description of the Laxemar area on a regional-scale (SDM version L1.2). A more specific objective of this study is to assess the propagation of uncertainties in the geological DFN modelling reported for L1.2 into the groundwater flow modelling. An improved understanding is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. The latter will serve as a basis for describing the present
Preliminary safety analysis report for the TFTR

International Nuclear Information System (INIS)

Lind, K.E.; Levine, J.D.; Howe, H.J.

A Preliminary Safety Analysis Report has been prepared for the Tokamak Fusion Test Reactor. No accident scenarios have been identified which would result in exposures to on-site personnel or the general public in excess of the guidelines defined for the project by DOE
Progress in centralised ethics review processes: Implications for multi-site health evaluations.

Science.gov (United States)

Prosser, Brenton; Davey, Rachel; Gibson, Diane

2015-04-01

Increasingly, public sector programmes respond to complex social problems that intersect specific fields and individual disciplines. Such responses result in multi-site initiatives that can span nations, jurisdictions, sectors and organisations. The rigorous evaluation of public sector programmes is now a baseline expectation. For evaluations of large and complex multi-site programme initiatives, the processes of ethics review can present a significant challenge. However in recent years, there have been new developments in centralised ethics review processes in many nations. This paper provides the case study of an evaluation of a national, inter-jurisdictional, cross-sector, aged care health initiative and its encounters with Australian centralised ethics review processes. Specifically, the paper considers progress against the key themes of a previous five-year, five nation study (Fitzgerald and Phillips, 2006), which found that centralised ethics review processes would save time, money and effort, as well as contribute to more equitable workloads for researchers and evaluators. The paper concludes with insights for those charged with refining centralised ethics review processes, as well as recommendations for future evaluators of complex multi-site programme initiatives. Copyright © 2015 Elsevier Ltd. All rights reserved.
Preliminary Safety Analysis of the Gorleben Site: Safety Concept and Application to Scenario Development Based on a Site-Specific Features, Events and Processes (FEP) Database - 13304

Energy Technology Data Exchange (ETDEWEB)

Moenig, Joerg; Beuth, Thomas; Wolf, Jens [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Theodor-Heuss-Str. 4, D-38122 Braunschweig (Germany); Lommerzheim, Andre [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany); Mrugalla, Sabine [Federal Institute for Geosciences and Natural Resources (BGR), Stilleweg 2, D-30655 Hannover (Germany)

2013-07-01

Based upon the German safety criteria, released in 2010 by the Federal Ministry of the Environment (BMU), a safety concept and a safety assessment concept for the disposal of heat-generating high-level waste have both been developed in the framework of the preliminary safety case for the Gorleben site (Project VSG). The main objective of the disposal is to contain the radioactive waste inside a defined rock zone, which is called containment-providing rock zone. The radionuclides shall remain essentially at the emplacement site, and at the most, a small defined quantity of material shall be able to leave this rock zone. This shall be accomplished by the geological barrier and a technical barrier system, which is required to seal the inevitable penetration of the geological barrier by the construction of the mine. The safe containment has to be demonstrated for probable and less probable evolutions of the site, while evolutions with very low probability (less than 1 % over the demonstration period of 1 million years) need not to be considered. Owing to the uncertainty in predicting the real evolution of the site, plausible scenarios have been derived in a systematic manner. Therefore, a comprehensive site-specific features, events and processes (FEP) data base for the Gorleben site has been developed. The safety concept was directly taken into account, e.g. by identification of FEP with direct influence on the barriers that provide the containment. No effort was spared to identify the interactions of the FEP, their probabilities of occurrence, and their characteristics (values). The information stored in the data base provided the basis for the development of scenarios. The scenario development methodology is based on FEP related to an impairment of the functionality of a subset of barriers, called initial barriers. By taking these FEP into account in their probable characteristics the reference scenario is derived. Thus, the reference scenario describes a
Site study plan for regional hydrologic sampling and monitoring: Preliminary draft

International Nuclear Information System (INIS)

Dutton, A.R.

1987-01-01

The purpose of the Regional Hydrologic Studies Plan is to describe those field activities required for completion of the objectives of hydrologic activities. Many of these activities are regional in scope and are designed to provide a framework for understanding the hydrologic setting of the site and the hydrologic processes that influence site characteristics. Site Study Plans (SSPs) define activates at and in the immediate vicinity of the site. The activities specified in the Regional Hydrologic Studies Plan are performed beyond the confines of the site because the hydrologic systems extend beyond the site boundaries, because pertinent data that bear on site suitability are available outside of the site, and because natural analogues exist outside of the site that allow analysis of processes that are expected to operate within the site. 15 refs., 5 figs., 1 tab

Site survey for large wind turbines in the Rijnmond area. Plaatsingsmogelijkheden grote windturbines in het Rijnmondgebied

Energy Technology Data Exchange (ETDEWEB)

Arkesteyn, L A; Van der Ham, P

1985-01-01

This paper reveals only preliminary results of a study on site selection for large wind turbines in a heavily industrialized and urbanized area of The Netherlands: the Rijnmond area. Factors like average wind speed, coupling to electric power grid, acquisition of land, noise pollution, safety aspects, avoiding harm to birds, and fitting in the existent physical structure of the area are evaluated.
Preliminary Disposal Analysis for Selected Accelerator Production of Tritium Waste Streams

International Nuclear Information System (INIS)

Ades, M.J.; England, J.L.

1998-06-01

A preliminary analysis was performed for two selected Accelerator Production of Tritium (APT) generated mixed and low-level waste streams to determine if one mixed low-level waste (MLLW) stream that includes the Mixed Waste Lead (MWL) can be disposed of at the Nevada Test Site (NTS) and at the Hanford Site and if one low-level radioactive waste (LLW) stream, that includes the Tungsten waste stream (TWS) generated by the Tungsten Neutron Source modules and used in the Target/Blanket cavity vessel, can be disposed of in the LLW Vaults at the Savannah River Plant (SRP). The preliminary disposal analysis that the radionuclide concentrations of the two selected APT waste streams are not in full compliance with the Waste Acceptance Criteria (WAC) and the Performance Assessment (PA) radionuclide limits of the disposal sites considered
Possible sites for future nuclear power plants in Israel

Energy Technology Data Exchange (ETDEWEB)

Yaar, Ilan, E-mail: ilany@energy.gov.il [Ministry of National Infrastructure, Energy and Water Resources, Chief Scientist Office, 14 Hartum St., POB 36148, Jerusalem 9136002 (Israel); Walter, Ayelet [Ministry of National Infrastructure, Energy and Water Resources, Chief Scientist Office, 14 Hartum St., POB 36148, Jerusalem 9136002 (Israel); Sanders, Yovav [Sysnet Group, Habarzel St. 32, Tel Aviv 69710 (Israel); Felus, Yaron [Survey of Israel, 1 Lincoln St., POB 14171, Tel-Aviv 61141 (Israel); Calvo, Ran; Hamiel, Yariv [Geological Survey of Israel, 30 Malkhe Israel St., Jerusalem 95501 (Israel)

2016-03-15

A preliminary work aimed at allocating suitable new sites for possible NPPs in Israel is presented. The work is based on Israel's present NPP siting criteria, supported by selected procedure performed by various countries that conducted similar process. The site selection process was conducted in two stages: first, a selection procedure using demographic analysis was conducted; second, a seismological and geological analysis process was performed in the remaining area. From the combined two screening processes results, an overall new area of 569 km{sup 2} was located as a possible area for future construction of NPPs in Israel. Further and more comprehensive work, based on the IAEAs site selection guidelines, has to be performed in the future, in order to verify the preliminary findings presented in this work.
Ecological risk assessment on a cadmium contaminated soil landfill-a preliminary evaluation based on toxicity tests on local species and site-specific information

International Nuclear Information System (INIS)

Chen, C.-M.; Liu, M.-C.

2006-01-01

In recent years, methodology of ecological risk assessment has been developed and applied frequently for addressing various circumstances where ecological impacts are suspected or have occurred due to environmental contamination; however, its practice is very limited in Taiwan. In 1982, brown rice from rice paddy fields in Da-Tan, Tau-Yuan, was found to be contaminated with Cd and Pb due to illegal discharges of wastewater, known as the 'Cd rice' incidence. Cadmium laden soil was transferred to a constructed landfill in an industrial park 15 years after the incident. Possible leakage of the landfill was suspected by committee members of a supervising board for the remediation process, and a preliminary ecological risk evaluation was requested. A possible risk scenario was that groundwater contamination due to the leachate containing Cd and Pb from the landfill could result in pollution of coastal water, and subsequently produce toxic effects to aquatic organisms. Chemical dissipation in groundwater systems was simulated and short-term chronic toxicity tests on larvae of three local aquatic species were also performed to determine the no-observed adverse-effect concentrations (NOAECs), as well as the predicted no effect concentrations (PNECs), of the two metals in the organisms tested. The hazard quotient (HQ), the ratio of predicted environmental concentrations (PECs) to PNECs, was used for risk characterization. A worst-case-scenario calculation showed that the maximum Cd concentration at 60 m and farther downstream from the site in the groundwater system would be 0.0028 mg l -1 with a maximum initial concentration of 0.65 mg l -1 in the leachate, while for Pb, the highest concentration of 0.044 mg l -1 would be reached at a distance of 40 m and farther, which was based on an initial concentration of 4.4 mg l -1 in the leachate; however, both cases would only occur 80 years after the initiation of leakage. A presumed dilution factor of 100 was used to calculate
Review of underground siting of nuclear power plants

International Nuclear Information System (INIS)

1974-01-01

A review of the potential for the underground siting of nuclear power generating plants has been undertaken. The review comprised a survey and assessment of relevant published documents currently available, together with discussions with Government sponsored agencies and other bodies, to evaluate the current status of technology related to the design and construction of underground nuclear power plants. It includes a review of previous work related to the underground siting of power plants and other facilities; a preliminary evaluation of the relative merits of the various concepts of undergrounding which have been proposed or constructed; a review of current technology as it relates to the requirements for the design, construction and operation of underground nuclear power plants; an examination of the safety and environmental aspects; and the identification of areas of further study which will be required if the underground is to be established as a fully viable alternative to surface siting. No attempt has been made to draw final conclusions at this stage. Nothing has been found to suggest that the underground siting concept could not provide a viable alternative to the surface concept. It is also apparent that no major technological developments are required. It is not clear, however, whether the improvements in safety and containment postulated for the underground can be realized at an economic cost; or even whether any additional cost is in fact involved. The problem is essentially site dependent and requires further study for which recommendations are made. (auth)
Preliminary safety evaluation (PSE) for Sodium Storage Facility at the Fast Flux Test Facility

International Nuclear Information System (INIS)

Bowman, B.R.

1994-01-01

This evaluation was performed for the Sodium Storage Facility (SSF) which will be constructed at the Fast Flux Test Facility (FFTF) in the area adjacent to the South and West Dump Heat Exchanger (DHX) pits. The purpose of the facility is to allow unloading the sodium from the FFTF plant tanks and piping. The significant conclusion of this Preliminary Safety Evaluation (PSE) is that the only Safety Class 2 components are the four sodium storage tanks and their foundations. The building, because of its imminent risk to the tanks under an earthquake or high winds, will be Safety Class 3/2, which means the building has a Safety Class 3 function with the Safety Class 2 loads of seismic and wind factored into the design
Geoscientific programme for investigation and evaluation of sites for the deep repository

International Nuclear Information System (INIS)

2000-08-01

SKB's goal is to be able to commence site investigations in 2002. Extensive preparations are now being made for this transition to the next phase in the siting process for the deep repository. This report describes the investigation and evaluation programme, which is focused on a deep repository in accordance with the KBS-3 method for spent nuclear fuel. When areas for site investigations have been chosen, the programmes will be adapted to the site-specific conditions. The geoscientific work during the site investigation phase is supposed to provide the broad knowledge base that is required to evaluate the suitability of investigated sites for a deep repository. The material must be comprehensive enough to: show whether the selected site satisfies fundamental safety requirements; permit comparisons with other investigated sites; and serve as a basis for adaptation of the deep repository to the properties and characteristics of the site with an acceptable impact on society and the environment. The work is being carried out in consultation with municipalities, regulatory authorities and nearby residents. The main product of the investigations is a site description, which presents collected data and interpreted parameters that are of importance both for the overall scientific understanding of the site and for the analyses and assessments that are made of design and safety assessment with respect to the deep repository's layout and construction as well as its long-term performance and radiological safety. The site description should furthermore present an integrated description of the site (geosphere and biosphere) and its regional environs with respect to current state and naturally ongoing processes. A technical risk evaluation is carried out, by which is meant a description of uncertainties in calculations and the environmental impact of the civil engineering work. The main product of the safety assessment is a safety report, which analyzes whether long-term safety
Geoscientific programme for investigation and evaluation of sites for the deep repository

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-08-01

SKB's goal is to be able to commence site investigations in 2002. Extensive preparations are now being made for this transition to the next phase in the siting process for the deep repository. This report describes the investigation and evaluation programme, which is focused on a deep repository in accordance with the KBS-3 method for spent nuclear fuel. When areas for site investigations have been chosen, the programmes will be adapted to the site-specific conditions. The geoscientific work during the site investigation phase is supposed to provide the broad knowledge base that is required to evaluate the suitability of investigated sites for a deep repository. The material must be comprehensive enough to: show whether the selected site satisfies fundamental safety requirements; permit comparisons with other investigated sites; and serve as a basis for adaptation of the deep repository to the properties and characteristics of the site with an acceptable impact on society and the environment. The work is being carried out in consultation with municipalities, regulatory authorities and nearby residents. The main product of the investigations is a site description, which presents collected data and interpreted parameters that are of importance both for the overall scientific understanding of the site and for the analyses and assessments that are made of design and safety assessment with respect to the deep repository's layout and construction as well as its long-term performance and radiological safety. The site description should furthermore present an integrated description of the site (geosphere and biosphere) and its regional environs with respect to current state and naturally ongoing processes. A technical risk evaluation is carried out, by which is meant a description of uncertainties in calculations and the environmental impact of the civil engineering work. The main product of the safety assessment is a safety report, which analyzes whether long
Environmental-pathways analysis for evaluation of a low-level waste disposal site

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.; Pin, F.G.; Hill, G.S.

1983-01-01

The suitability of a site for the shallow land burial of low-level waste is evaluated by an environmental-pathways analysis. The environmental-pathways analysis considers the probable paths for the transport of contamination to man and models the long-term transport of contamination to determine the resulting dose-to-man. The model of the long-term transport of contamination is developed for a proposed site using data obtained from a comprehensive laboratory and field investigation. The proposed site is located at the US Department of Energy Portsmouth Reservation, Piketon, Ohio and is planned to accept low-level radioactive waste generated by the enrichment of uranium. Laboratory studies were performed to characterize the waste and determine the wastes' leaching and retardation characteristics with site soils and groundwater. Comprehensive drilling, sampling and laboratory investigations were performed to provide the necessary information for interpreting the site's geology and hydrology. Field tests were performed to further quantify the site's hydrology. The pathway of greatest concern is the migration of contaminated groundwater and subsequent consumption by man. This pathway was modeled using a numerical simulation of the long-term transport of contamination. Conservative scenarios were developed for leachate generation and migration through the geohydrologic system. The dose-to-man determined from the pathways analysis formed the basis for evaluating site acceptability and providing recommendations for site design and development
Environmental pathways analysis for evaluation of a low-level waste disposal site

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.; Pin, F.G.; Hill, G.S.

1984-01-01

The suitability of a site for the shallow land burial of low-level waste is evaluated by an environmental pathways analysis. The environmental pathways analysis considers the probable paths for the transport of contamination to man and models the long-term transport of contamination to determine the resulting dose to man. The model of the long-term transport of contamination is developed for a proposed site using data obtained from a comprehensive laboratory and field investigation. The proposed site is located at the US Department of Energy Portsmouth Reservation, Piketon, Ohio, and is planned to accept low-level radioactive waste generated by the enrichment of uranium. Laboratory studies were performed to characterize the waste and determine the wastes' leaching and retardation characteristics with site soils and groundwater. Comprehensive drilling, sampling and laboratory investigations were performed to provide the necessary information for interpreting the site's geology and hydrology. Field tests were performed to further quantify the site's hydrology. The pathway of greatest concern is the migration of contaminated groundwater and subsequent consumption by man. This pathway was modelled using a numerical simulation of the long-term transport of contamination. Conservative scenarios were developed for leachate generation and migration through the geohydrologic system. The dose to man determined from the pathways analysis formed the basis for evaluating site acceptability and providing recommendations for site design and development. (author)
Effect of corrosive marine atmosphere on construction materials in Tanzania: Exposure sites and preliminary results

International Nuclear Information System (INIS)

Mmari, A.G.; Uiso, C.B.S.; Makundi, I.N.; Potgieter-Vermaak, S.S.; Potgieter, J.H.; Van Grieken, R.

2007-01-01

Air pollution studies in Africa are limited and the influence of ambient air quality on buildings and constructions have not been investigated in the larger part of Sub-Saharan Africa. The increasing burden of emission from industry, traffic and coal power plants on ambient air pollution in Sub-Saharan Africa necessitated reviewing previous and current studies. In South Africa a 20-year exposure program, focusing on the effect of ambient exposure on various metals and alloys, showed that the amount of rainfall, relative humidity, atmospheric pollution, wind speed, solar radiation and structural design are some of the factors controlling atmospheric corrosion. Tanzania, being among the Sub-Saharan African countries and partly bordered by Indian ocean, the main source of marine atmosphere, experiences corrosive degradation on metal roofing and cementitious materials. This paper describes the exposure site set-up and will report on some preliminary results of air quality and its relation with the meteorological conditions, as well as surface changes observed, for the year one of exposure. These will thereafter be compared to the completed European and Asian studies, as reported by CLRTAP and RAPIDC respectively. (author)
CERCLA site assessment workbook, Volume 1

International Nuclear Information System (INIS)

1994-08-01

This workbook provides instructions for planning, implementing, and reporting site assessments under CERCLA, commonly referred to as Superfund. Site assessment consists of two information-gathering steps: the remedial preliminary assessment (PA) and the site inspection (SI). The information obtained is then used to estimate, or score, a site's relative risk to public health and the environment. The score is derived via the hazard ranking system (HRS). Although the workbook and its exercises can be adapted to group study, it is designed primarily for use by an individual
Preliminary results of the search for possible Martian landing sites to be considered for future European exploration missions

Science.gov (United States)

Martin, P.

2007-08-01

considered, as well as lessons learned from past landing experiences. Finally, nolanding zones shall be identified based on a number of available criteria. A preliminary investigation and classification of potential landing sites for future European Mars exploration missions is summarised here, with the assumed following general requirements: • Moderate latitudes (e.g., 15ºS to 45ºN). Such a latitude range would be suitable for Exomars. • Low-to-moderate elevation (e.g., below 2000 m) • Relatively flat surface in the landing ellipse (e.g., slopes Power and communications systems requirements - Illumination and temperature requirements - Biological potential and planetary protection Possible landing regions on Mars resulting from this preliminary investigation can be categorised into two classes, depending on the level of risk assessed for the landing in terms of, e.g., roughness and rock abundance: • Low-risk regions: Amazonis Planitia, Utopia Planitia, and Elysium Planitia. One of their potential drawbacks is that most areas of these regions exhibit a relatively high dust index which could be detrimental to the scientific interest of the in-situ mission. • Moderate-risk regions: - Syrtis Major / Nili Fossae, where phyllosilicates and hydrated minerals can be found based on recent evidence from orbit (Mars Express/OMEGA). - Isidis Planitia, in particular because this region presents a low vertical roughness. - Chryse/Acidalia Planitia, where phyllosilicates, hydrated minerals and sulfates can be found. - The region that spans the terrains from Sinus Meridiani to Syrtis Major, between 15ºS and 45ºN. This region exhibits a high dust index, and is represented by rougher, heavily cratered terrains in many areas. Within these regions, a more detailed identification of landing sites can be performed by refining the study (top-down approach) using higher-resolution geological and compositional maps (e.g., Mars Express/HRSC-OMEGA and/or MRO/HiRISECRISM) coupled with
Scar evaluation of split thickness skin graft donor site

Directory of Open Access Journals (Sweden)

Jani Muha

2014-12-01

Full Text Available BACKGROUND. Split thickness skin graft harvesting causes a certain degree of scaring on the donor site. Donor site scar can cause aesthetic and functional sequelae on the patient's body. Our goal was to study the process of donor site selection, and then evaluate donor site scars and their impact on patients. PATIENTS AND METHODS. This retrospective study included 45 patients aged 5 to 61 years (in average 36, who have been treated with STSG in the 2004–2010 period. 57.8% of them were men. On a follow-up visit, we photographed healed skin defects and donor sites. We then determined and compared the surface areas of skin defect and the donor site using the Adobe® Illustrator® CS5 computer program. Donor site scars were assessed according to the Vancouver scar scale (VSS. We examined scar’s light touch sensitivity with monofilaments and skin colouring compared to adjacent healthy skin using colorimeter. Patients were also interviewed about their treatment course in a form of a standardized questionnaire. RESULTS. Our research has revealed that 20.0% of patients participated in the decision making process of choosing the donor site, while in 80.0% the donor site was chosen by the surgeon himself. 6.7% of patients were not satisfied with their donor site. Most of the patients (37/45 had donor sites on their thighs. In average, the donor site surface area was 94% bigger than the skin defect area. We found statistically significant differences in VSS values, light touch sensitivity and skin colouring between donor site scaring and adjacent healthy skin. CONCLUSIONS. Donor site scar can represent a lasting aesthetic and functional disability for patients. Our research has shown that most of the patients do not participate in the donor site selection process, but are satisfied with their donor site. In most cases, STGSs are harvested from the thigh, other anatomical regions, where scarring would be aesthetically less obtrusive, are underused
Synthesis gas demonstration plant program, Phase I. Site confirmation report

Energy Technology Data Exchange (ETDEWEB)

1978-12-01

With few reservations, the Baskett, Kentucky site exhibits the necessary characteristics to suggest compatibility with the proposed Synthesis Gas Demonstration Plant Project. An evaluation of a broad range of technical disciplinary criteria in consideration of presently available information indicated generally favorable conditions or, at least, conditions which could be feasibly accommodated in project design. The proximity of the Baskett site to market areas and sources of raw materials as well as a variety of transportation facilities suggests an overall favorable impact on Project economic feasibility. Two aspects of environmental engineering, however, have been identified as areas where the completion or continuation of current studies are required before removing all conditions on site suitability. The first aspect involves the current contradictory status of existing land use and planning ordinances in the site area. Additional investigation of the legality of, and local attitudes toward, these present plans is warranted. Secondly, terrestrial and aquatic surveys of plant and animal life species in the site area must be completed on a seasonal basis to confirm the preliminary conclusion that no exclusionary conditions exist.
Streambed scour evaluations and conditions at selected bridge sites in Alaska, 2012

Science.gov (United States)

Beebee, Robin A.; Schauer, Paul V.

2015-11-19

Streambed scour potential was evaluated at 18 river- and stream-spanning bridges in Alaska that have unknown foundation details or a lack of existing scour analysis. All sites were evaluated for stream stability and long-term scour potential. Contraction scour and abutment scour were calculated for 17 bridges, and pier scour was calculated for 7 bridges that had piers. Vertical contraction (pressure flow) scour was calculated for sites with overtopping floods (where the modeled water surface was higher than the superstructure of the bridge). In most cases, hydraulic models of the 1- and 0.2-percent annual exceedance probability floods (also known as the 100- and 500-year floods, respectively) were used to derive hydraulic variables for the scour calculations. Alternate flood values were used in scour calculations for sites where smaller floods overtopped a bridge or where standard flood-frequency estimation techniques did not apply. Scour was also calculated for large recorded floods at several sites. Equations for scour in cohesive soils were used for sites where streambed sediment was silt-sized or smaller.
Targeted Health Assessment for Wastes Contained at the Niagara Falls Storage Site to Guide Planning for Remedial Action Alternatives - 13428

Energy Technology Data Exchange (ETDEWEB)

Busse, John; Keil, Karen; Staten, Jane; Miller, Neil; Barker, Michelle [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States); MacDonell, Margaret; Peterson, John; Chang, Young-Soo; Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01

The U.S. Army Corps of Engineers (USACE) is evaluating potential remedial alternatives at the 191-acre Niagara Falls Storage Site (NFSS) in Lewiston, New York, under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Manhattan Engineer District (MED) and Atomic Energy Commission (AEC) brought radioactive wastes to the site during the 1940's and 1950's, and the U.S. Department of Energy (US DOE) consolidated these wastes into a 10-acre interim waste containment structure (IWCS) in the southwest portion of the site during the 1980's. The USACE is evaluating remedial alternatives for radioactive waste contained within the IWCS at the NFSS under the Feasibility Study phase of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process. A preliminary evaluation of the IWCS has been conducted to assess potential airborne releases associated with uncovered wastes, particularly during waste excavation, as well as direct exposures to uncovered wastes. Key technical issues for this assessment include: (1) limitations in waste characterization data; (2) representative receptors and exposure routes; (3) estimates of contaminant emissions at an early stage of the evaluation process; (4) consideration of candidate meteorological data and air dispersion modeling approaches; and (5) estimates of health effects from potential exposures to both radionuclides and chemicals that account for recent updates of exposure and toxicity factors. Results of this preliminary health risk assessment indicate if the wastes were uncovered and someone stayed at the IWCS for a number of days to weeks, substantial doses and serious health effects could be incurred. Current controls prevent such exposures, and the controls that would be applied to protect onsite workers during remedial action at the IWCS would also effectively protect the public nearby. This evaluation provides framing context for the upcoming development and detailed
Site evaluation using measured meteorology data

Energy Technology Data Exchange (ETDEWEB)

Cooper, R. E.; Rusche, B. C. [Savannah River Lab., E.I. du Pont de Nemours and Co., Aiken, South Carolina (United States)

1967-07-01

A key factor in reactor site evaluation is the frequency of occurrence of various dispersion conditions and this relationship to potential off-site doses following a reactor accident. Detailed measurements of the wind speed, wind direction, and temperature at heights up to 1200 ft at the Savannah River Plant form the basis for a comprehensive analysis of the frequency of occurrence of potential off-site doses. A complete set of data was taken about every five minutes, and 107,000 sets (about one year of data) were analyzed. The meteorology data were converted to ordinary dispersion parameters through correlating equations developed at Brookhaven National Laboratory. The results were expressed on curves in dose per unit release of activity vs distance from the reactor with probability of occurrence as a parameter. Separate sets of curves were calculated for releases of noble gas and of halogens and at release heights of 200 ft (a nominal stack height) and of 850 ft (about the height of the tallest power plant stacks). Additional curves were developed to show dose as a function of direction and probability of occurrence. In addition to the dose frequency distribution analyses performed as a function of height of release, direction, and distance; more conventional frequency distributions of wind speed, wind direction, and thermal stability were developed as a function of height. All the analyses were carried out on the IBM 360/65. These results represent the first known analysis utilizing data up to 1200 ft and taken often enough to develop reliable frequency distributions for a short term release. (author)
Preliminary experiments for measuring Kd values for cesium and strontium. To be used in site evaluations

International Nuclear Information System (INIS)

Benischek, I.; Hess, V.; Metzker, E.

1992-03-01

In an underground dump not only technolgical barriers but also the natural geological formations are efficient in withholding radionuclides. Sites are to be chosen where the rocks have good sorption properties and where transportation due to various chemical interactions should be minimal. Minerals obtained from deep drilling - granodiorite, mylonite and granit gneis - were investigated. The liquid phase (cement leaching water) contained different amounts of cesium 137 and strontium 85. Details of the experiments and results are given
Integrating risks at contaminated sites

International Nuclear Information System (INIS)

MacDonell, M.; Habegger, L.; Nieves, L.; Schreiber, Z.; Travis, C.

2000-01-01

The U.S. Department of Energy (DOE) is responsible for a number of large sites across the country that were radioactively and chemically contaminated by past nuclear research, development, and production activities. Multiple risk assessments are being conducted for these sites to evaluate current conditions and determine what measures are needed to protect human health and the environment from today through the long term. Integrating the risks associated with multiple contaminants in different environmental media across extensive areas, over time periods that extend beyond 1,000 years, and for a number of different impact categories--from human health and ecological to social and economic--represents a considerable challenge. A central element of these integrated analyses is the ability to reflect key interrelationships among environmental resources and human communities that may be adversely affected by the actions or inactions being considered for a given site. Complicating the already difficult task of integrating many kinds of risk is the importance of reflecting the diverse values and preferences brought to bear by the multiple parties interested in the risk analysis process and outcome. An initial conceptual framework has been developed to provide an organized structure to this risk integration, with the aim of supporting effective environmental management decisions. This paper highlights key issues associated with comprehensive risk integration and offers suggestions developed from preliminary work at a complex DOE site

Method of impact evaluation of storage sites for uranium ore tailings

International Nuclear Information System (INIS)

Servant, A.C.; Cessac, B.

2001-11-01

Mining and ore processing generate liquid effluents and solid waste ( tailings) in important quantities. On fifty years exploitation, 50 millions tons of tailings have been stored on twenty sites in France. From a radiological point of view, the uranium tailings contain only natural radioisotopes, daughters of 238 U and 235 U families and for a low part daughter's of 232 Th family. Their activity stay low to very low, under the ore activity. It decreases very slowly because of the long period of some radionuclides ( 230 Th, 75 000 years, 226 Ra, 1600 years). generally stored on the exploitation site, these tailings constitute a radiological source term of which it is necessary to evaluate the impact on man and environment. At close-down of an uranium ore exploitation site, the operator is required to give to the prefect of his region a file of rehabilitation with the dispositions to take to limit the radiological impact of the storage. It is in this frame that the direction of pollutions and risks prevention (D.P.P.R.) from the Minister of Territory landscaping and the Institute of protection and nuclear safety (I.R.S.N.) established a convention, reference 56/2000, relative to investigations in matter of radiological impact evaluation of uranium tailings storage sites, in order to supply a document allowing to judge the pertinence of the different files made by Cogema in the frame of tailings storage of uranium ore processing. The present document constitutes the report planned at the 3. article ( 3. paragraph) of the convention. It gives the information necessary to the evaluation of impact studies for the sites in question. (N.C.)
An alternative method to record rising temperatures during dental implant site preparation: a preliminary study using bovine bone

Directory of Open Access Journals (Sweden)

Domenica Laurito

2010-12-01

Full Text Available Overheating is constantly mentioned as a risk factor for bone necrosis that could compromise the dental implant primary stability. Uncontrolled thermal injury can result in a fibrous tissue, interpositioned at the implant-bone interface, compromising the long-term prognosis. The methods used to record temperature rise include either direct recording by thermocouple instruments or indirect estimating by infrared thermography. This preliminary study was carried out using bovine bone and a different method of temperatures rising estimation is presented. Two different types of drills were tested using fluoroptic thermometer and the effectiveness of this alternative temperature recording method was evaluated.
Alaska Open-file Report 144 Assessment of Thermal Springs Sites Aleutian Arc, Atka Island to Becherof Lake -- Preliminary Results and Evaluation

Energy Technology Data Exchange (ETDEWEB)

Motyka, R.J.; Moorman, M.A.; Liss, S.A.

1981-12-01

Twenty of more than 30 thermal spring areas reported to exist in the Aleutian arc extending from Atka Island to Becherof Lake were investigated during July and August, 1980. Thermal activity of three of these sites had diminished substantially or no longer existed. At least seven more sites where thermal-spring activity is probable or certain were not visited because of their remoteness or because of time constraints. The existence of several other reported thermal spring sites could not be verified; these sites are considered questionable. On the basis of geothermometry, subsurface reservoir temperatures in excess of 150 C are estimated for 10 of the thermal spring sites investigated. These sites all occur in or near regions of Recent volcanism. Five of the sites are characterized by fumaroles and steaming ground, indicating the presence of at least a shallow vapor-dominated zone. Two, the Makushin Valley and Glacier Valley thermal areas, occur on the flanks of active Mukushin Volcano located on Unalaska Island, and may be connected to a common source of heat. Gas geothermometry suggests that the reservoir feeding the Kliuchef thermal field, located on the flanks of Kliuchef volcano of northeast Atka Island, may be as high as 239 C.
Antares: preliminary demonstrator results

International Nuclear Information System (INIS)

Kouchner, A.

2000-05-01

The ANTARES collaboration is building an undersea neutrino telescope off Toulon (Mediterranean sea) with effective area ∼ 0.1 km 2 . An extensive study of the site properties has been achieved together with software analysis in order to optimize the performance of the detector. Results are summarized here. An instrumented line, linked to shore for first time via an electro-optical cable, has been immersed late 1999. The preliminary results of this demonstrator line are reported. (author)
Evaluation of site effects in Loja basin (southern Ecuador)

Science.gov (United States)

Guartán, J.; Navarro, M.; Soto, J.

2013-05-01

Site effect assessment based on subsurface ground conditions is often crucial for estimating the urban seismic hazard. In order to evaluate the site effects in the intra-mountain basin of Loja (southern Ecuador), geological and geomorphological survey and ambient noise measurements were carried out. A classification of shallow geologic materials was performed through a geological cartography and the use of geotechnical data and geophysical surveys. Seven lithological formations have been analyzed, both in composition and thickness of existing materials. The shear-wave velocity structure in the center of the basin, composed by alluvial materials, was evaluated by means of inversion of Rayleigh wave dispersion data obtained from vertical-component array records of ambient noise. VS30 structure was estimated and an average value of 346 m s-1 was obtained. This value agrees with the results obtained from SPT N-value (306-368 m s-1). Short-period ambient noise observations were performed in 72 sites on a 500m × 500m dimension grid. The horizontal-to-vertical spectral ratio (HVSR) method was applied in order to determine a ground predominant period distribution map. This map reveals an irregular distribution of predominant period values, ranged from 0.1 to 1.0 s, according with the heterogeneity of the basin. Lower values of the period are found in the harder formation (Quillollaco formation), while higher values are predominantly obtained in alluvial formation. These results will be used in the evaluation of ground dynamic properties and will be included in seismic microzoning of Loja basin. Keywords: Landform classification, Ambient noise, SPAC method, Rayleigh waves, Shear velocity profile, Ground predominant period. ;
Site observational work plan for the UMTRA Project site at Tuba City, Arizona

International Nuclear Information System (INIS)

1994-09-01

The requirements for ground water compliance for Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Tuba City, Arizona, site, are found in the Uranium Mill Tailings Radiation Control Act; Subparts B and C of the U.S. Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings (40 CFR 192 (1994)), and the associated proposed 1987 standards (52 FR 36000). During the surface remedial action, an estimated 1,400,000 cubic yards (yd 3 ) (1,100,000 cubic meters [m 3 ]) of uranium mill tailings and other contaminated materials were consolidated and stabilized in place in an unlined disposal cell covering 50 acres (20 hectares). The surface remedial action was completed in April 1990. Ground water beneath the Tuba City site was contaminated by subsurface migration of water from uranium ore processing activities. The main source of contaminants was water from the tailings piles that began in 1956 when the mill opened and ended in 1966 when the mill closed. 800,000 tons (725,000 tonnes) of uranium ore were processed onsite over a 10-year period. The wet tailings remaining after processing were placed as a slurry in three piles at the site. Water from these tailings then seeped into the ground and migrated downward to the ground water. The Tuba City site is currently in a post-stabilization, prelicensing status. The site is expected to remain in this status until licensed by the U.S. Nuclear Regulatory Commission (NRC) for long-term surveillance and maintenance. The preliminary ground water compliance strategy at the Tuba City site is active remediation-specific technology to be evaluated is in situ bioremediation. This selection was made because of the potential ability of bioremediation to reduce concentrations to lower levels than a conventional extraction system and to minimize disturbance of the water resource
Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

Energy Technology Data Exchange (ETDEWEB)

Soederbaeck, Bjoern [ed.

2008-06-15

The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding
Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

International Nuclear Information System (INIS)

Soederbaeck, Bjoern

2008-06-01

The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding
Draft environmental assessment: Deaf Smith County site, Texas. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy identified a location in Deaf Smith County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Deaf Smith site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment, which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Deaf Smith site is not disqualified under the guidelines. The site is in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Swisher site. Although the Swisher site appears to be suitable for site characterization, DOE has concluded that the Deaf Smith site is the preferred site. The DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Deaf Smith site as one of five sites suitable for characterization. Having compared the Deaf Smith site with the other four sites proposed for nomination, the DOE has determined that the Deaf Smith site is one of the three preferred sites for recommendation to the President as candidates for characterization
Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

International Nuclear Information System (INIS)

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs
Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs.
Draft environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received on the draft EA. The Yucca Mountain site is located in the Great Basin, one of five distinct geohydrologic settings that are being considered for the first repository. On the basis of the evaluations reported in this draft EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Yucca Mountain site as one of five sites suitable for characterization. Furthermore, having performed a comparative evaluation of the five sites proposed for nomination, the DOE has determined that the Yucca Mountain site is one of three sites preferred for site characterization
Evaluation of local site effect from microtremor measurements in Babol City, Iran

Science.gov (United States)

Rezaei, Sadegh; Choobbasti, Asskar Janalizadeh

2018-03-01

Every year, numerous casualties and a large deal of financial losses are incurred due to earthquake events. The losses incurred by an earthquake vary depending on local site effect. Therefore, in order to conquer drastic effects of an earthquake, one should evaluate urban districts in terms of the local site effect. One of the methods for evaluating the local site effect is microtremor measurement and analysis. Aiming at evaluation of local site effect across the city of Babol, the study area was gridded and microtremor measurements were performed with an appropriate distribution. The acquired data was analyzed through the horizontal-to-vertical noise ratio (HVNR) method, and fundamental frequency and associated amplitude of the H/V peak were obtained. The results indicate that fundamental frequency of the study area is generally lower than 1.25 Hz, which is acceptably in agreement with the findings of previous studies. Also, in order to constrain and validate the seismostratigraphic model obtained with this method, the results were compared with geotechnical, geological, and seismic data. Comparing the results of different methods, it was observed that the presented geophysical method can successfully determine the values of fundamental frequency across the study area as well as local site effect. Using the data obtained from the analysis of microtremor, a microzonation map of fundamental frequency across the city of Babol was prepared. This map has numerous applications in designing high-rise building and urban development plans.
Removal site evaluation report on the Tower Shielding Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-09-01

This removal site evaluation report for the Tower Shielding Facility (TSF) at Oak Ridge National Laboratory was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Tower Shielding Facility pose a substantial risk to human health or the environment (i.e., a high probability of adverse effects) and if remedial site evaluations or removal actions are, therefore, required. The scope of the project included a review of historical evidence regarding operations and use of the facility; interviews with facility personnel concerning current and past operating practices; a site inspection; and identification of hazard areas requiring maintenance, removal, or remedial actions. Based an the findings of this removal site evaluation, adequate efforts are currently being made at the TSF to contain and control existing contamination and hazardous substances on site in order to protect human health and the environment No conditions requiring maintenance or removal actions to mitigate imminent or potential threats to human health and the environment were identified during this evaluation. Given the current conditions and status of the buildings associated with the TSF, this removal site evaluation is considered complete and terminated according to the requirements for removal site evaluation termination
Limited site review for the San Joaquin Nuclear Project. Project No. 499

International Nuclear Information System (INIS)

1977-06-01

This report is the Nuclear Regulatory Commission's (Commission) safety evaluation of a proposed site near Bakersfield, California, on which the Los Angeles Department of Water and Power (applicant) in association with a number of other organizations proposes to build a nuclear facility at a future date. A construction permit application has not been filed but the applicant has informed us of its intention to submit an Environmental Report during February 1980 and a Preliminary Safety Analysis Report during May 1980
Draft environmental assessment: reference repository location, Hanford Site, Washington. Nuclear Waste Policy Act (Section 112)

International Nuclear Information System (INIS)

1984-12-01

In February 1983, the US Department of Energy (DOE) identified a reference repository location at the Hanford Site in Washington as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the reference repository location at the Hanford Site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received on the draft EA. The reference repository location at Hanford is located in the Columbia Plateau, one of five distinct geohydrologic settings that are being considered for the first repository. On the basis of the evaluations reported in this draft EA, the DOE has found that the reference repository location at Hanford is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the reference repository location at Hanford as one of five sites suitable for characterization. Furthermore, having performed a comparative evaluation of the five sites proposed for nomination, the DOE has determined that the reference repository location at Hanford is one of three sites preferred for site characterization
Prospective safety performance evaluation on construction sites.

Science.gov (United States)

Wu, Xianguo; Liu, Qian; Zhang, Limao; Skibniewski, Miroslaw J; Wang, Yanhong

2015-05-01

This paper presents a systematic Structural Equation Modeling (SEM) based approach for Prospective Safety Performance Evaluation (PSPE) on construction sites, with causal relationships and interactions between enablers and the goals of PSPE taken into account. According to a sample of 450 valid questionnaire surveys from 30 Chinese construction enterprises, a SEM model with 26 items included for PSPE in the context of Chinese construction industry is established and then verified through the goodness-of-fit test. Three typical types of construction enterprises, namely the state-owned enterprise, private enterprise and Sino-foreign joint venture, are selected as samples to measure the level of safety performance given the enterprise scale, ownership and business strategy are different. Results provide a full understanding of safety performance practice in the construction industry, and indicate that the level of overall safety performance situation on working sites is rated at least a level of III (Fair) or above. This phenomenon can be explained that the construction industry has gradually matured with the norms, and construction enterprises should improve the level of safety performance as not to be eliminated from the government-led construction industry. The differences existing in the safety performance practice regarding different construction enterprise categories are compared and analyzed according to evaluation results. This research provides insights into cause-effect relationships among safety performance factors and goals, which, in turn, can facilitate the improvement of high safety performance in the construction industry. Copyright © 2015 Elsevier Ltd. All rights reserved.
Development of a Preliminary Model for Evaluating Occupational Health and Safety Risk Management Maturity in Small and Medium-Sized Enterprises

Directory of Open Access Journals (Sweden)

Bilal Kaassis

2018-02-01

Full Text Available Management of occupational health and safety (OHS risks is a crucial component of any business. Numerous investigations have shown that work-related injuries and deaths occur disproportionately in small-to-medium-sized enterprises (SMEs and that this is clearly due to deficient management of OHS risks. The main goal of this work is to develop a base of indicators suitable for evaluating OHS risk management maturity in industrial SMEs. A preliminary model is then proposed for this evaluation, based on a small number of relevant indicators selected from a careful bibliographic review. The work begins with a critical review of the literature and analysis of known concepts, methods, tools and models of measurement of risk analysis maturity in order to extract relevant indicators. The most suitable indicators are then grouped to form the basis of a preliminary model for evaluating OHS risk management maturity in the SME setting. Our findings will help managers of SMEs make sound decisions in their quest to improve the OHS performance of their businesses.
Nevada potential repository preliminary transportation strategy: Study 1

Energy Technology Data Exchange (ETDEWEB)

None,

1995-04-01

Limited feasible options exist when considering the shipment of spent nuclear fuel and high-level radioactive waste. These options are rail or truck; because of the weight associated with transportation casks (68.0 to 113.4 tonnes/75 to 125 tons), heavy-haul trucks are also considered. Yucca Mountain currently lacks rail service or an existing right-of-way for rail; it also lacks a dedicated highway suitable for heavy-haul trucks. Approximately 11,230 shipments by rail are planned from waste producer sites to Nevada, with an additional 1,041 shipments by legal-weight truck from four reactor sites not capable of upgrading for rail shipment. This study identifies the reasonable alternatives for waste transport to the potential repository site, describes the evaluation process performed to identify those alternatives, and discusses the reasons for elimination of transportation routes deemed to be not reasonable. The study concluded that heavy haul truck transportation is feasible-cost is very favorable when compared to rail-but route restrictions must be further evaluated. In addition to restrictions due to seasonal weather conditions, specific routes have additional restrictions, including no travel on holidays or weekends, and travel during daylight hours only. Further restrictions will be imposed by the U.S. Department of Transportation based on routing of radioactive materials by highway. Operation and maintenance costs for heavy-haul over a 24-year period, based on preliminary information, were calculated on an estimated operational cost of $15,000 per trip, with an estimated 468 trips per year average (11,230 total trips), for an estimated cost of $171 million to $173 million, depending on the route used. Because the initial costs and the total system life cycle costs of heavy-haul are approximately 50 percent lower than the lowest rail cost, this option will continue to be evaluated.
Nevada potential repository preliminary transportation strategy: Study 1

International Nuclear Information System (INIS)

1995-04-01

Limited feasible options exist when considering the shipment of spent nuclear fuel and high-level radioactive waste. These options are rail or truck; because of the weight associated with transportation casks (68.0 to 113.4 tonnes/75 to 125 tons), heavy-haul trucks are also considered. Yucca Mountain currently lacks rail service or an existing right-of-way for rail; it also lacks a dedicated highway suitable for heavy-haul trucks. Approximately 11,230 shipments by rail are planned from waste producer sites to Nevada, with an additional 1,041 shipments by legal-weight truck from four reactor sites not capable of upgrading for rail shipment. This study identifies the reasonable alternatives for waste transport to the potential repository site, describes the evaluation process performed to identify those alternatives, and discusses the reasons for elimination of transportation routes deemed to be not reasonable. The study concluded that heavy haul truck transportation is feasible-cost is very favorable when compared to rail-but route restrictions must be further evaluated. In addition to restrictions due to seasonal weather conditions, specific routes have additional restrictions, including no travel on holidays or weekends, and travel during daylight hours only. Further restrictions will be imposed by the U.S. Department of Transportation based on routing of radioactive materials by highway. Operation and maintenance costs for heavy-haul over a 24-year period, based on preliminary information, were calculated on an estimated operational cost of $15,000 per trip, with an estimated 468 trips per year average (11,230 total trips), for an estimated cost of $171 million to $173 million, depending on the route used. Because the initial costs and the total system life cycle costs of heavy-haul are approximately 50 percent lower than the lowest rail cost, this option will continue to be evaluated

Columbia River impact evaluation plan

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

As a result of past practices, four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency`s (EPA`s) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980. To accomplish the timely cleanup of the past-practice units, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), was signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE). To support the Tri-Party Agreement, milestones were adopted. These milestones represent the actions needed to ensure acceptable progress toward Hanford Site compliance with CERCLA, RCRA, and the Washington State Hazardous Waste Management Act of 1976. This report was prepared to fulfill the requirement of Tri-Party Agreement Milestone M-30-02, which requires a plan to determine cumulative health and environmental impacts to the Columbia River. This plan supplements the CERCLA remedial investigations/feasibility studies (RI/FS) and RCRA facility investigations/corrective measures studies (RFI/CMSs) that will be undertaken in the 100 Area. To support the plan development process, existing information was reviewed and a preliminary impact evaluation based on this information was performed. The purpose of the preliminary impact evaluation was to assess the adequacy of existing data and proposed data collection activities. Based on the results of the evaluation, a plan is proposed to collect additional data or make changes to existing or proposed data collection activities.
Grid-connected ICES: preliminary feasibility analysis and evaluation. Volume 2. Final report

Energy Technology Data Exchange (ETDEWEB)

1977-06-30

The HEAL Complex in New Orleans will serve as a Demonstration Community for which the ICES Demonstration System will be designed. The complex is a group of hospitals, clinics, research facilities, and medical educational facilities. The five tasks reported on are: preliminary energy analysis; preliminary institutional assessment; conceptual design; firming-up of commitments; and detailed work management plan.
TRANSIT: model for providing generic transportation input for preliminary siting analysis

International Nuclear Information System (INIS)

McNair, G.W.; Cashwell, J.W.

1985-02-01

To assist the US Department of Energy's efforts in potential facility site screening in the nuclear waste management program, a computerized model, TRANSIT, is being developed. Utilizing existing data on the location and inventory characteristics of spent nuclear fuel at reactor sites, TRANSIT derives isopleths of transportation mileage, costs, risks and fleet requirements for shipments to storage sites and/or repository sites. This technique provides a graphic, first-order method for use by the Department in future site screening efforts. 2 refs
Summary of the Preliminary Analysis of Savannah River Depleted Uranium Trioxide

International Nuclear Information System (INIS)

2010-01-01

This report summarizes a preliminary special analysis of the Savannah River Depleted Uranium Trioxide waste stream (SVRSURANIUM03, Revision 2). The analysis is considered preliminary because a final waste profile has not been submitted for review. The special analysis is performed to determine the acceptability of the waste stream for shallow land burial at the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada National Security Site (NNSS). The Savannah River Depleted Uranium Trioxide waste stream requires a special analysis because the waste stream's sum of fractions exceeds one. The 99Tc activity concentration is 98 percent of the NNSS Waste Acceptance Criteria and the largest single contributor to the sum of fractions.
Evaluation of regulatory processes affecting nuclear power plant early site approval and standardization

International Nuclear Information System (INIS)

1983-12-01

This report presents the results of a survey and evaluation of existing federal, state and local regulatory considerations affecting siting approval of power plants in the United States. Those factors that may impede early site approval of nuclear power plants are identified, and findings related to the removal of these impediments and the general improvement of the approval process are presented. A brief evaluation of standardization of nuclear plant design is also presented
Engineering Geological Evaluation Of A Proposed Landfill Site At ...

African Journals Online (AJOL)

Evaluation of a location at Aba-Kulodi adjacent to kilometre 8 along the Ibadan / Ile-Ife expressway, Southwestern Nigeria was carried out to determine its suitability or otherwise as a landfill site. Two Vertical Electrical Soundings (VES) 30.00m apart were executed to obtain subsurface information on depth to bedrock and ...
Development of methods and criteria for a standardized evaluation of contaminated sites and abandoned waste disposal sites particularly concerning their ground water contamination potential. Pt. 1. Final Report

International Nuclear Information System (INIS)

Kerndorff, H.; Schleyer, R.; Arneth, J.D.; Struppe, T.; Milde, G.

1994-01-01

Contaminated sites should be evaluated to such an extend, that nearly all risks for man and environment can be safely estimated. An assessment for such sites is presented which combines a substance-specific and a site-specific evaluation. It is a standardized path-specific concept in which - as an example - the contamination path ''waste - groundwater - drinking-water'' is investigated and evaluated in detail. Path-specific main contaminants are established on a statistic basis and ranked according to normalized evaluation numbers of 1-100. Their toxicity potential is calculated for which a particular and standardized method was developed. Main contaminants having a high toxicity potential are called priority contaminants. For the most important exposure/usage on this contamination path, the drinking-water catchment, hygienic and toxicologic based standards are presented. Together with site-specific conditions and the also path-specific and normalized transfer/persistency potential of the priority contaminants it is possible to come to a site- and usage/exposure-specific evaluation of individual sites. (orig.) [de
Worldwide Evaluations of Quinoa: Preliminary Results from Post International Year of Quinoa FAO Projects in Nine Countries.

Science.gov (United States)

Bazile, Didier; Pulvento, Cataldo; Verniau, Alexis; Al-Nusairi, Mohammad S; Ba, Djibi; Breidy, Joelle; Hassan, Layth; Mohammed, Maarouf I; Mambetov, Omurbek; Otambekova, Munira; Sepahvand, Niaz Ali; Shams, Amr; Souici, Djamel; Miri, Khaled; Padulosi, Stefano

2016-01-01

Chenopodium quinoa Willd., a high quality grain crop, is resistant to abiotic stresses (drought, cold, and salt) and offers an optimal source of protein. Quinoa represents a symbol of crop genetic diversity across the Andean region. In recent years, this crop has undergone a major expansion outside its countries of origin. The activities carried out within the framework of the International Year of Quinoa provided a great contribution to raise awareness on the multiple benefits of quinoa as well as to its wider cultivation at the global level. FAO is actively involved in promoting and evaluating the cultivation of quinoa in 26 countries outside the Andean region with the aim to strengthen food and nutrition security. The main goal of this research is to evaluate the adaptability of selected quinoa genotypes under different environments outside the Andean region. This paper presents the preliminary results from nine countries. Field evaluations were conducted during 2013/2014 and 2014/2015 in Asia (Kyrgyzstan and Tajikistan), and the Near East and North African countries (Algeria, Egypt, Iraq, Iran, Lebanon, Mauritania, and Yemen). In each country, the trials were carried out in different locations that globally represent the diversity of 19 agrarian systems under different agro-ecological conditions. Twenty-one genotypes of quinoa were tested using the same experimental protocol in all locations consisting in a randomized complete block design (RCBD) with three replicates. Some genotypes showed higher yields and the Q18 and Q12 landraces displayed greater adaptation than others to new environmental conditions. The Q21 and Q26 landraces were evaluated with stable and satisfactory levels of yield (>1 t.ha(-1)) in each of the different trial sites. This production stability is of considerable importance especially under climate change uncertainty. While these results suggest that this Andean crop is able to grow in many different environments, social, and cultural
Worldwide Evaluations of Quinoa: Preliminary Results from Post International Year of Quinoa FAO Projects in Nine Countries

Science.gov (United States)

Bazile, Didier; Pulvento, Cataldo; Verniau, Alexis; Al-Nusairi, Mohammad S.; Ba, Djibi; Breidy, Joelle; Hassan, Layth; Mohammed, Maarouf I.; Mambetov, Omurbek; Otambekova, Munira; Sepahvand, Niaz Ali; Shams, Amr; Souici, Djamel; Miri, Khaled; Padulosi, Stefano

2016-01-01

Chenopodium quinoa Willd., a high quality grain crop, is resistant to abiotic stresses (drought, cold, and salt) and offers an optimal source of protein. Quinoa represents a symbol of crop genetic diversity across the Andean region. In recent years, this crop has undergone a major expansion outside its countries of origin. The activities carried out within the framework of the International Year of Quinoa provided a great contribution to raise awareness on the multiple benefits of quinoa as well as to its wider cultivation at the global level. FAO is actively involved in promoting and evaluating the cultivation of quinoa in 26 countries outside the Andean region with the aim to strengthen food and nutrition security. The main goal of this research is to evaluate the adaptability of selected quinoa genotypes under different environments outside the Andean region. This paper presents the preliminary results from nine countries. Field evaluations were conducted during 2013/2014 and 2014/2015 in Asia (Kyrgyzstan and Tajikistan), and the Near East and North African countries (Algeria, Egypt, Iraq, Iran, Lebanon, Mauritania, and Yemen). In each country, the trials were carried out in different locations that globally represent the diversity of 19 agrarian systems under different agro-ecological conditions. Twenty-one genotypes of quinoa were tested using the same experimental protocol in all locations consisting in a randomized complete block design (RCBD) with three replicates. Some genotypes showed higher yields and the Q18 and Q12 landraces displayed greater adaptation than others to new environmental conditions. The Q21 and Q26 landraces were evaluated with stable and satisfactory levels of yield (>1 t.ha−1) in each of the different trial sites. This production stability is of considerable importance especially under climate change uncertainty. While these results suggest that this Andean crop is able to grow in many different environments, social, and cultural
Safety Evaluation Report Restart of K-Reactor Savannah River Site

International Nuclear Information System (INIS)

1991-10-01

In April 1991, the Department of Energy (DOE) issued DOE/DP-0084T, ''Safety Evaluation Report Restart of K-Reactor Savannah River Site.'' The Safety Evaluation Report (SER) documents the results of DOE reviews and evaluations of the programmatic aspects of a large number of issues necessary to be satisfactorily addressed before restart. The issues were evaluated for compliance with the restart criteria included in the SER. The results of those evaluations determined that the restart criteria had been satisfied for some of the issues. However, for most of the issues at least part of the applicable restart criteria had not been found to be satisfied at the time the evaluations were prepared. For those issues, open or confirmatory items were identified that required resolution. In August 1991, DOE issued DOE/DP-0090T, ''Safety Evaluation Report Restart of K-Reactor Savannah River Site Supplement 1.'' That document was the first Supplement to the April 1991 SER, and documented the resolution of 62 of the open items identified in the SER. This document is the second Supplement to the April 1991 SER. This second SER Supplement documents the resolution of additional open times identified in the SER, and includes a complete list of all remaining SER open items. The resolution of those remaining open items will be documented in future SER Supplements. Resolution of all open items for an issue indicates that its associated restart criteria have been satisfied, and that DOE concludes that the programmatic aspects of the issue have been satisfactorily addressed
Preliminary evaluation of microstructure and mechanical properties on low activation ferritic steels

International Nuclear Information System (INIS)

Hsu, C.Y.; Lechtenberg, T.A.

1985-01-01

Radioactive waste disposal has become a primary concern for the selection of materials for the structural components for fusion reactors. One way to minimize this potential environmental problem is to use structural materials in which the induced radioactivity decays quickly to levels that allow for near-surface disposal under 10CFR61 rules. The primary objective of this work is to develop low activation ferritic steels that exhibit mechanical and physical properties approximately equivalent to the HT-9 and 9Cr-1Mo steels, but which only contain elements that would permit near-surface disposal under 10CFR61 after exposure to fusion neutrons. A preliminary evaluation of the microstructure and mechanical properties of a 9Cr-2.5W-0.3V-0.15C (GA3X) low activation ferritic steel has been performed. An optimum heat treatment condition has been defined for GA3X steel. The properties and microstructure of the quenched and tempered specimens were characterized via hardness measurement and optical metallographic observation. The hot-microhardness and ductility parameter measurements were used to estimate the tensile properties at elevated temperatures. The estimated tensile strengths of GA3X steel at elevated temperatures are comparable to both 9Cr-1Mo and the modified 9Cr-1Mo steels. These preliminary results are encouraging in that they suggest that suitable low activation alloys can be successfully produced in this ferritic alloy class
Preliminary characterization of slow growing rhizobial strains ...

African Journals Online (AJOL)

In this paper, we did some preliminary characterization of six slow growing rhizobial strains, isolated from Retama monosperma (L.) Boiss. root nodules sampled from 3 sites along the coast of Oran (CapeFalcon, Bousfer and MersElHadjadj) in Northwestern Algeria. Results of this study showed that all strains had a very ...
Site Characterization Analysis Penetrometer System (SCAPS): An Innovative Technology Evaluation Report

National Research Council Canada - National Science Library

Jack, Lary

1995-01-01

... of subsurface soil at hazardous waste sites. The effectiveness of each technology was evaluated by comparing each technology's results to the results obtained using conventional reference methods...
Preliminary Design Analysis of a HGD for the NHDD Program at Korea

International Nuclear Information System (INIS)

Song, Kee Nam; Lee, H. Y.; Lee, S. B.; Kim, Y. W.

2007-01-01

Korea Atomic Energy Research Institute is in the process of carrying out a Nuclear Hydrogen Development and Demonstration (NHDD) Program by considering the indirect cycle gas cooled reactors that produce heat at temperatures in the order of 950 .deg. C. A coaxial double-tube Hot Gas Duct (HGD) is a key component connecting the reactor pressure vessel and the intermediate heat exchanger for the NHDD program. Recently, a preliminary design evaluation for the hot gas duct of the NHDD program was carried out. These preliminary design activities include a decision on the geometric dimensions, a strength evaluation, an appropriate material selection, and identifying the design code for the HGD. In this study, a preliminary strength evaluation for the HGD of the NHDD program has been undertaken based on the HTR-10 design concepts. Also, a preliminary evaluation of the creep-fatigue damage for a high temperature HGD structure has been carried out according to the draft code case for Alloy 617. Preliminary strength evaluation results for the HGD showed that the geometric dimensions of the proposed HGD would be acceptable for the design requirements
Hanford Site storm water comprehensive site compliance evaluation report for the reporting period July 1, 1996 through June 30, 1997

International Nuclear Information System (INIS)

Perkins, C.J.

1997-01-01

On September 9, 1992, the US Environmental Protection Agency (EPA) issued General Permit No. WA-R-00-OOOF, Authorization to Discharge Under the National Pollutant Discharge Elimination System (NPDES) for Storm Water Discharges Associated with Industrial Activity to the US Department of Energy, Richland Operations Office (RL). RL submitted a Notice of Intent to comply with this permit to EPA in conformance with the General Permit requirements on October 1, 1992. On February 14, 1994, EPA issued a Storm Water General Permit Coverage Notice and assigned WA-R-00-Al7F as the Hanford Site's National Pollutant Discharge Elimination System (NPDES) storm water permit number. The Hanford Site Storm Water Pollution Prevention Plan (SWPPP) (WHC 1996a) was certified by J. E Rasmussen, Director Environmental Assurance, RL, on September 24, 1996, in compliance with Part IV.B(i) of the General Permit. As required by General Permit No. WA-R-00-OOOF (WA-R-00-Al7F), Section IV, Part D, Section 4.c, an annual report must be developed by RL and retained on site to verify that the requirements listed in the General Permit are being implemented. The previous Hanford Site Storm Plater Comprehensive Site Compliance Evaluation Report (WHC 1996b) addressed the period from July 1995 through June 1996. This document fulfills the requirement to prepare an annual report and contains the results of inspections of the storm water outfalls listed in the SWPPP (WHC 1996a). This report also describes the methods used to conduct the 1100 Storm Plater Comprehensive Site Compliance Evaluation (SWCSCE) as required in Part IV, Section D.4.c in the General Permit; summarizes the results of the compliance evaluation; and documents significant leaks and spills. The reporting year for this SWCSCE report is July 1, 1996 through June 30, 1997
Preliminary evaluation of the tibial tuberosity-trochlear groove measurement

DEFF Research Database (Denmark)

Miles, James Edward; Kirpensteijn, Jolle; Svalastoga, Eiliv Lars

guide surgical treatment. The TTTG measures tibial tuberosity position relative to the axis of the femoral trochlea. A preliminary investigation of TTTG measurement was performed using the red fox (Vulpes vulpes) cadavers as a morphologically similar and homogenous substitute for dog cadavers. CT...
Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

Science.gov (United States)

Lingga, Marwan Mossa

A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.
Assessment of hydrologic transport of radionuclides from the Rulison Underground Nuclear Test Site, Colorado

International Nuclear Information System (INIS)

Earman, S.; Chapman, J.; Andricevic, R.

1996-09-01

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Rulison site in west-central Colorado was the location of an underground detonation of a 40-kiloton nuclear device in 1969. The test took place 2,568 m below ground surface in the Mesaverde Formation. Though located below the regional water table, none of the bedrock formations at the site yielded water during hydraulic tests, indicating extremely low permeability conditions. The scenario evaluated was the migration of radionuclides from the blast-created cavity through the Mesaverde Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity and the correlation scale of hydraulic conductivity, with transport of strontium and cesium also sensitive to the sorption coefficient
Preventative Vaccines for Zika Virus Outbreak: Preliminary Evaluation

Directory of Open Access Journals (Sweden)

Eun Kim

2016-11-01

Full Text Available Since it emerged in Brazil in May 2015, the mosquito-borne Zika virus (ZIKV has raised global concern due to its association with a significant rise in the number of infants born with microcephaly and neurological disorders such as Guillain-Barré syndrome. We developed prototype subunit and adenoviral-based Zika vaccines encoding the extracellular portion of the ZIKV envelope gene (E fused to the T4 fibritin foldon trimerization domain (Efl. The subunit vaccine was delivered intradermally through carboxymethyl cellulose microneedle array (MNA. The immunogenicity of these two vaccines, named Ad5.ZIKV-Efl and ZIKV-rEfl, was tested in C57BL/6 mice. Prime/boost immunization regimen was associated with induction of a ZIKV-specific antibody response, which provided neutralizing immunity. Moreover, protection was evaluated in seven-day-old pups after virulent ZIKV intraperitoneal challenge. Pups born to mice immunized with Ad5.ZIKV-Efl were all protected against lethal challenge infection without weight loss or neurological signs, while pups born to dams immunized with MNA-ZIKV-rEfl were partially protected (50%. No protection was seen in pups born to phosphate buffered saline-immunized mice. This study illustrates the preliminary efficacy of the E ZIKV antigen vaccination in controlling ZIKV infectivity, providing a promising candidate vaccine and antigen format for the prevention of Zika virus disease.
Using a site-specific technical error to establish training responsiveness: a preliminary explorative study.

Science.gov (United States)

Weatherwax, Ryan M; Harris, Nigel K; Kilding, Andrew E; Dalleck, Lance C

2018-01-01

Even though cardiorespiratory fitness (CRF) training elicits numerous health benefits, not all individuals have positive training responses following a structured CRF intervention. It has been suggested that the technical error (TE), a combination of biological variability and measurement error, should be used to establish specific training responsiveness criteria to gain further insight on the effectiveness of the training program. To date, most training interventions use an absolute change or a TE from previous findings, which do not take into consideration the training site and equipment used to establish training outcomes or the specific cohort being evaluated. The purpose of this investigation was to retrospectively analyze training responsiveness of two CRF training interventions using two common criteria and a site-specific TE. Sixteen men and women completed two maximal graded exercise tests and verification bouts to identify maximal oxygen consumption (VO 2 max) and establish a site-specific TE. The TE was then used to retrospectively analyze training responsiveness in comparison to commonly used criteria: percent change of >0% and >+5.6% in VO 2 max. The TE was found to be 7.7% for relative VO 2 max. χ 2 testing showed significant differences in all training criteria for each intervention and pooled data from both interventions, except between %Δ >0 and %Δ >+7.7% in one of the investigations. Training nonresponsiveness ranged from 11.5% to 34.6%. Findings from the present study support the utility of site-specific TE criterion to quantify training responsiveness. A similar methodology of establishing a site-specific and even cohort specific TE should be considered to establish when true cardiorespiratory training adaptations occur.

DEMONSTRATION OF FUEL CELLS TO RECOVER ENERGY FROM ANAEROBIC DIGESTER GAS - PHASE I. CONCEPTUAL DESIGN, PRELIMINARY COST, AND EVALUATION STUDY

Science.gov (United States)

The report discusses Phase I (a conceptual design, preliminary cost, and evaluation study) of a program to demonstrate the recovery of energy from waste methane produced by anaerobic digestion of waste water treatment sludge. The fuel cell is being used for this application becau...
HACCP and water safety plans in Icelandic water supply: preliminary evaluation of experience.

Science.gov (United States)

Gunnarsdóttir, María J; Gissurarson, Loftur R

2008-09-01

Icelandic waterworks first began implementing hazard analysis and critical control points (HACCP) as a preventive approach for water safety management in 1997. Since then implementation has been ongoing and currently about 68% of the Icelandic population enjoy drinking water from waterworks with a water safety plan based on HACCP. Preliminary evaluation of the success of HACCP implementation was undertaken in association with some of the waterworks that had implemented HACCP. The evaluation revealed that compliance with drinking water quality standards improved considerably following the implementation of HACCP. In response to their findings, waterworks implemented a large number of corrective actions to improve water safety. The study revealed some limitations for some, but not all, waterworks in relation to inadequate external and internal auditing and a lack of oversight by health authorities. Future studies should entail a more comprehensive study of the experience with the use of HACCP with the purpose of developing tools to promote continuing success.
TECHNOLOGY EVALUATION REPORT, SITE PROGRAM DEMONSTRATION TEST: SHIRCO PILOT-SCALE INFRARED INCINERATION SYSTEM ROSE TOWNSHIP DEMODE ROAD SUPERFUND SITE - VOLUME II

Science.gov (United States)

The performance of the Shirco pilot-scale infrared thermal destruction system has been evaluated at the Rose Township, Demode Road Superfund Site and is presented in the report. The waste tested consisted of solvents, organics and heavy metals in an illegal dump site. Volume I gi...
Volcanic Hazard Assessments for Nuclear Installations: Methods and Examples in Site Evaluation

International Nuclear Information System (INIS)

2016-07-01

To provide guidance on the protection of nuclear installations against the effects of volcanoes, the IAEA published in 2012 IAEA Safety Standards Series No. SSG-21, Volcanic Hazards in Site Evaluation for Nuclear Installations. SSG-21 addresses hazards relating to volcanic phenomena, and provides recommendations and general guidance for evaluation of these hazards. Unlike seismic hazard assessments, models for volcanic hazard assessment have not undergone decades of review, evaluation and testing for suitability in evaluating hazards at proposed nuclear installations. Currently in volcanology, scientific developments and detailed methodologies to model volcanic phenomena are evolving rapidly.This publication provides information on detailed methodologies and examples in the application of volcanic hazard assessment to site evaluation for nuclear installations, thereby addressing the recommendations in SSG-21. Although SSG-21 develops a logical framework for conducting a volcanic hazard assessment, this publication demonstrates the practicability of evaluating the recommendations in SSG-21 through a systematic volcanic hazard assessment and examples from Member States. The results of this hazard assessment can be used to derive the appropriate design bases and operational considerations for specific nuclear installations
Review Article : Utilization of Environmental Radiochemistry Techniques for Selection and Evaluation of Nuclear Facility Sites

International Nuclear Information System (INIS)

Atta, E.R.; Madbouly, A.M.; Zakaria, Kh.M.

2016-01-01

This research review puts necessary considerations on the available environmental radiochemistry techniques for selection and evaluation of a nuclear facility sites.The main bjective in site evaluation for nuclear facilities in terms of nuclear safety is to protect the site workers, the public and the environment from the effects of ionizing radiation release from nuclear facilities due to accidents. The extreme sensitivity and speed of radiochemical methods make their applications of considerable importance in several fields and they have found many uses. Information about the existed radioactivity in the different nuclear facilities is an essential requirement for their environmental assessment. It is necessary to estimate the various radioactivity levels in the environment through qualitative and quantitative analytical techniques and to assess the potential effects of the nuclear facility in the region by considering the characteristics of sites.The siting and site evaluation requirements are discussed. Emphasis was given to types of radiochemical techniques used for characterization of the site parameters which determine the potential hazards of the site on the facility and the facility on the site. Emphasis has been also given to the quantitative and qualitative analysis of naturally occurring radionuclides for monitoring and control .There are some techniques employed such as radioactive tracer technique, liquid scintillation technique, gamma spectrometry technique, neutron activation analysis technique, fluorimetric technique and isotope hydrology technique.
Preliminary criteria for shallow-land storage/disposal of low-level radioactive solid waste in an arid environment

International Nuclear Information System (INIS)

Shord, A.L.

1979-09-01

Preliminary criteria for shallow land storage/disposal of low level radioactive solid waste in an arid environment were developed. Criteria which address the establishment and operation of a storage/disposal facility for low-level radioactive solid wastes are discussed. These were developed from the following sources: (1) a literature review of solid waste burial; (2) a review of the regulations, standards, and codes pertinent to the burial of radioactive wastes; (3) on site experience; and (4) evaluation of existing burial grounds and practices
Effect of site-specific heterogeneous evolution on phylogenetic reconstruction: a simple evaluation.

Science.gov (United States)

Cheng, Qiqun; Su, Zhixi; Zhong, Yang; Gu, Xun

2009-07-15

Recent studies have shown that heterogeneous evolution may mislead phylogenetic analysis, which has been neglected for a long time. We evaluate the effect of heterogeneous evolution on phylogenetic analysis, using 18 fish mitogenomic coding sequences as an example. Using the software DIVERGE, we identify 198 amino acid sites that have experienced heterogeneous evolution. After removing these sites, the rest of sites are shown to be virtually homogeneous in the evolutionary rate. There are some differences between phylogenetic trees built with heterogeneous sites ("before tree") and without heterogeneous sites ("after tree"). Our study demonstrates that for phylogenetic reconstruction, an effective approach is to identify and remove sites with heterogeneous evolution, and suggests that researchers can use the software DIVERGE to remove the influence of heterogeneous evolution before reconstructing phylogenetic trees.
Lifetime Evaluation of PV Inverters considering Panel Degradation Rates and Installation Sites

DEFF Research Database (Denmark)

Sangwongwanich, Ariya; Yang, Yongheng; Sera, Dezso

2017-01-01

The PV inverter lifetime is affected by the installed sites related to different solar irradiance and ambient temperature profiles. In fact, the installation site also affects the PV panel degradation rate, and thus the long-term power production. Prior-art lifetime analysis in PV inverters has...... not yet investigated the impact of panel degradation. This paper thus evaluates the lifetime of PV inverters considering panel degradation rates and installation sites. Evaluations have been carried out on PV systems installed in Denmark and Arizona. The results reveal that the PV panel degradation rate...... has a considerable impact on the PV inverter lifetime, especially in the hot climate (e.g., Arizona), where the panel degrades at a faster rate. In that case, the PV inverter lifetime estimation can be deviated by 54%, if the impact of PV panel degradation is not taken into account....
Usability evaluation of mobile ICT support used at the building construction site

DEFF Research Database (Denmark)

Christiansson, Per; Svidt, Kjeld

2006-01-01

The paper summarizes findings from field evaluations and controlled laboratory usability evaluations of new mobile Information and Communication Technology, ICT, support used by craftsmen at construction sites as well as a discussion of methodologies for user centred ICT tools design. The finding...
Geotechnical evaluation of the proposed WIPP site in southeast New Mexico

International Nuclear Information System (INIS)

Weart, W.D.

1978-10-01

The Department of Energy is proposing to demonstrate the acceptability of geologic disposal of radioactive waste by locating a Waste Isolation Pilot Plant (WIPP) in the salt beds 26 miles east of Carlsbad, New Mexico. The WIPP will serve as a permanent repository for defense generated transuranic contaminated waste and will also be used as a facility in which experiments and demonstrations with all radioactive waste types can be conducted. The present area being proposed for the WIPP is the second such location in the Delaware Basin for which new site data have been developed; the first site proved geologically unacceptable. Ecologic and socioeconomic aspects have been investigated and extensive geophysical, geological and hydrologic studies have been conducted to allow an evaluation of site acceptability. Geotechnical aspects of site characterization are examined. These studies are now sufficiently complete that the site can be recommended for further development of the WIPP
Preliminary assessment of using tree-tissue analysis and passive-diffusion samplers to evaluate trichloroethene contamination of ground water at Site SS-34N, McChord Air Force Base, Washington, 2001

Science.gov (United States)

Cox, S.E.

2002-01-01

Two low-cost innovative sampling procedures for characterizing trichloroethene (TCE) contamination in ground water were evaluated for use at McChord Air Force Base (AFB) by the U.S. Geological Survey, in cooperation with the U.S. Air Force McChord Air Force Base Installation Restoration Program, in 2001. Previous attempts to characterize the source of ground-water contamination in the heterogeneous glacial outwash aquifer at McChord site SS-34N using soil-gas surveys, direct-push exploration, and more than a dozen ground-water monitoring wells have had limited success. The procedures assessed in this study involved analysis of tree-tissue samples to map underlying ground-water contamination and deploying passive-diffusion samplers to measure TCE concentrations in existing monitoring wells. These procedures have been used successfully at other U.S. Department of Defense sites and have resulted in cost avoidance and accelerated site characterization. Despite the presence of TCE in ground water at site SS-34N, TCE was not detected in any of the 20 trees sampled at the site during either early spring or late summer sampling. The reason the tree tissue procedure was not successful at the McChord AFB site SS-34N may have been due to an inability of tree roots to extract moisture from a water table 30 feet below the land surface, or that concentrations of TCE in ground water were not large enough to be detectable in the tree tissue at the sampling point. Passive-diffusion samplers were placed near the top, middle, and bottom of screened intervals in three monitoring wells and TCE was observed in all samplers. Concentrations of TCE from the passive-diffusion samplers were generally similar to concentrations found in samples collected in the same wells using conventional pumping methods. In contrast to conventional pumping methods, the collection of ground-water samples using the passive-diffusion samples did not generate waste purge water that would require hazardous
Hydroelectric generating site signage

Energy Technology Data Exchange (ETDEWEB)

Bentley, K [British Columbia Hydro, Vancouver, BC (Canada)

1997-04-01

Recreational sites have been developed at several BC Hydro reservoirs. These sites are visited by approximately 800,000 people annually and therefore, require consistent control measures to ensure public safety and to restrict public access to hazardous areas. BC Hydro is in the process of establishing a province-wide standard in which layout, colour, description of hazards, BC Hydro identity and sign placement would follow an established set of criteria. Proposed signs would consist of a pictograph and a printed warning below. Preliminary designs for 16 of the signs were presented. 16 figs.
Evaluation of afforestation development and natural colonization on a reclaimed mine site

Science.gov (United States)

Diana Laarmann; Henn Korjus; Allan Sims; Ahto Kangur; Andres Kiviste; John Stanturf

2015-01-01

Post-mining restoration sites often develop novel ecosystems as soil conditions are completely new and ecosystem assemblage can be spontaneous even on afforested sites. This study presents results from long-term monitoring and evaluation of an afforested oil-shale quarry in Estonia. The study is based on chronosequence data of soil and vegetation and comparisons are...
Hydrologic investigations to evaluate a potential site for a nuclear-waste repository, Yucca Mountain, Nevada Test Site

International Nuclear Information System (INIS)

Wilson, W.E.

1985-01-01

Yucca Mountain, Nevada Test Site, is being evaluated by the U.S. Department of Energy for its suitability as a site for a mined geologic respository for high-level nuclear wastes. The repository facility would be constructed in densely welded tuffs in the unsaturated zone. In support of the evaluation, the U.S. Geological Survey is conducting hydrologic investigations of both the saturated and unsaturated zones, as well as paleohydrologic studies. Investigation in saturated-zone hydrology will help define one component of ground-water flow paths and travel times to the accessible environment. A two-dimensional, steady-state, finite-element model was developed to describe the regional hydrogeologic framework. The unsaturated zone is 450 to 700 meters thick at Yucca Mountain; precipitation averages about 150 millimeters per year. A conceptual hydrologic model of the unsaturated zone incorporates the following features: minimal net infiltration, variable distribution of flux, lateral flow, potential for perched-water zones, fracture and matrix flow, and flow along faults. The conceptual model is being tested primarily by specialized test drilling; plans also are being developed for in-situ testing in a proposed exploratory shaft. Quaternary climatic and hydrologic conditions are being evaluated to develop estimates of the hydrologic effects of potential climatic changes during the next 10,000 years. Evaluation approaches include analysis of plant macrofossils in packrat middens, evaluation of lake and playa sediments, infiltration tests, and modeling effects of potential increased recharge on the potentiometric surface
Stereo Evaluation of CARTOSAT-1 Data on Test Site 5 - First DLR Results

OpenAIRE

Lehner, Manfred; Müller, Rupert; Reinartz, Peter

2006-01-01

DLR's Remote Sensing Technology Institute has more than 20 years of history in developing spaceborne stereo scanners (MEOSS, MOMS) and the corresponding stereo evaluation software systems. The institute takes part in CARTOSAT-1 Scientific Assessment Program (C-SAP) as a principal investigator for German (Southeast Bavaria, test site not yet included in the C-SAP list) and Spanish (Catalonia, TS10) test sites for which also PI evaluations for SPOT-5 HRS SAP had been done in 2003-4. As CARTO...
In Situ Vitrification preliminary results from the first large-scale radioactive test

International Nuclear Information System (INIS)

Buelt, J.L.; Westsik, J.H.

1988-01-01

The first large-scale radioactive test (LSRT) of In Situ Vitrification (ISV) has been completed. In Situ Vitrification is a process whereby joule heating immobilizes contaminated soil in place by converting it to a durable glass and crystalline waste form. The LSRT was conducted at an actual transuranic contaminated soil site on the Department of Energy's Hanford Site. The test had two objectives: 1) determine large-scale processing performance and 2) produce a waste form that can be fully evaluated as a potential technique for the final disposal of transuranic-contaminated soil sites at Hanford. This accomplishment has provided technical data to evaluate the ISV process for its potential in the final disposition of transuranic-contaminated soil sites at Hanford. The LSRT was completed in June 1987 after 295 hours of operation and 460 MWh of electrical energy dissipated to the molten soil. This resulted in a minimum of a 450-t block of vitrified soil extending to a depth of 7.3m (24 ft). The primary contaminants vitrified during the demonstration were Pu and Am transuranics, but also included up to 26,000 ppm fluorides. Preliminary data show that their retention in the vitrified product exceeded predictions meaning that fewer contaminants needed to be removed from the gaseous effluents by the processing equipment. The gaseous effluents were contained and treated throughout the run; that is, no radioactive or hazardous chemical releases were detected
General guidelines for recommendation of sites for nuclear waste repositories

International Nuclear Information System (INIS)

1983-01-01

These guidelines were developed in accordance with the requirements of Section 112(a) of the Nuclear Waste Policy Act of 1982 for use by the Secretary of Energy in evaluating the suitability of sites for the development of repositories. The guidelines will be used for suitability evaluations and determinations made pursuant to Section 112(b) and any preliminary suitability determinations required by Section 114(f). The guidelines set forth in this Part are intended to complement the requirements set forth in the Act, 10 CFR Part 60, and 40 CFR Part 191. In applying these guidelines, the DOE will resolve any inconsistencies between these guidelines and the above documents in a manner determined by the DOE to most closely agree with the intent of the Act
Implementation of transdiagnostic treatment for emotional disorders in residential eating disorder programs: A preliminary pre-post evaluation.

Science.gov (United States)

Thompson-Brenner, Heather; Boswell, James F; Espel-Huynh, Hallie; Brooks, Gayle; Lowe, Michael R

2018-03-19

Data are lacking from empirically supported therapies implemented in residential programs for eating disorders (EDs). Common elements treatments may be well-suited to address the complex implementation and treatment challenges that characterize these settings. This study assessed the preliminary effect of implementing a common elements therapy on clinician treatment delivery and patient (N = 616) symptom outcomes in two residential ED programs. The Unified Protocol for Transdiagnostic Treatment of Emotional Disorders was adapted to address ED and co-occurring psychopathology and implemented across sites. Therapists' treatment fidelity was rated independently to assess implementation success. Additionally, longitudinal (pre-post) design compared treatment outcomes among patients treated before and after implementation. Patient outcomes included ED and depressive symptoms, experiential avoidance, anxiety sensitivity, and mindfulness. Following training and implementation, clinicians demonstrated adequate to good fidelity. Relative to pre-implementation, post-implementation patients showed significantly greater improvements in experiential avoidance, anxiety sensitivity, and mindfulness at discharge (ps ≤ .04) and more favorable outcomes on ED symptom severity, depression, and experiential avoidance at 6-month follow up (ps ≤ .0001). Preliminary pilot data support the feasibility of implementing transdiagnostic common elements therapy in residential ED treatment, and suggest that implementation may benefit transdiagnostic outcomes for patients.
Infiltration experiment for closure cap evaluation at the Savannah River Site

International Nuclear Information System (INIS)

Roddy, N.S.; Cook, J.R.

1990-01-01

This document discusses several large waste disposal facilities at the Savannah River Site which are being closed. These facilities include two seepage basins and the low-level waste disposal facility. The key element of the closures is the construction of a cap system to limit the infiltration of water which might reach the disposed waste. Cap designs have been modeled using the Hydrologic Evaluation of Landfill Performance (HELP) computer code. This code was developed by the US Army Corps of Engineers for the Environmental Protection Agency to model the effects of various cap and liner designs on the water balance at landfills. A field experiment has been set up which will allow the results of the HELP Code to be verified at the Savannah River Site (SRS) by measuring the actual water balance created by closure cap configurations which will be used in waste site closures at SRS. Two of the caps will be similar to those used for the planned closure activities. Each one has a specific closure arrangement. Once operational, the experiment will be evaluated for a five-year period
Cold vacuum drying facility site evaluation report

International Nuclear Information System (INIS)

Diebel, J.A.

1996-01-01

In order to transport Multi-Canister Overpacks to the Canister Storage Building they must first undergo the Cold Vacuum Drying process. This puts the design, construction and start-up of the Cold Vacuum Drying facility on the critical path of the K Basin fuel removal schedule. This schedule is driven by a Tri-Party Agreement (TPA) milestone requiring all of the spent nuclear fuel to be removed from the K Basins by December, 1999. This site evaluation is an integral part of the Cold Vacuum Drying design process and must be completed expeditiously in order to stay on track for meeting the milestone

Preliminary siting criteria for the proposed mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Jorgenson-Waters, M.

1992-09-01

The Mixed and Low-Level Waste Treatment Facility project was established in 1991 by the US Department of Energy Idaho Field Office. This facility will provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies the siting requirements imposed on facilities that treat and store these waste types by Federal and State regulatory agencies and the US Department of Energy. Site selection criteria based on cost, environmental, health and safety, archeological, geological and service, and support requirements are presented. These criteria will be used to recommend alternative sites for the new facility. The National Environmental Policy Act process will then be invoked to evaluate the alternatives and the alternative sites and make a final site determination
Evaluation of health risks associated with proposed ground water standards at selected inactive uranium mill-tailings sites

International Nuclear Information System (INIS)

Hamilton, L.D.; Medeiros, W.H.; Meinhold, A.; Morris, S.C.; Moskowitz, P.D.; Nagy, J.; Lackey, K.

1989-04-01

The US Environmental Protection Agency (EPA) has proposed ground water standards applicable to all inactive uranium mill-tailings sites. The proposed standards include maximum concentration limits (MCL) for currently regulated drinking water contaminants, as well as the addition of standards for molybdenum, uranium, nitrate, and radium-226 plus radium-228. The proposed standards define the point of compliance to be everywhere downgradient of the tailings pile, and require ground water remediation to drinking water standards if MCLs are exceeded. This document presents a preliminary description of the Phase 2 efforts. The potential risks and hazards at Gunnison, Colorado and Lakeview, Oregon were estimated to demonstrate the need for a risk assessment and the usefulness of a cost-benefit approach in setting supplemental standards and determining the need for and level of restoration at UMTRA sites. 8 refs., 12 tabs
Evaluation of health risks associated with proposed ground water standards at selected inactive uranium mill-tailings sites

Energy Technology Data Exchange (ETDEWEB)

Hamilton, L.D.; Medeiros, W.H.; Meinhold, A.; Morris, S.C.; Moskowitz, P.D.; Nagy, J.; Lackey, K.

1989-04-01

The US Environmental Protection Agency (EPA) has proposed ground water standards applicable to all inactive uranium mill-tailings sites. The proposed standards include maximum concentration limits (MCL) for currently regulated drinking water contaminants, as well as the addition of standards for molybdenum, uranium, nitrate, and radium-226 plus radium-228. The proposed standards define the point of compliance to be everywhere downgradient of the tailings pile, and require ground water remediation to drinking water standards if MCLs are exceeded. This document presents a preliminary description of the Phase 2 efforts. The potential risks and hazards at Gunnison, Colorado and Lakeview, Oregon were estimated to demonstrate the need for a risk assessment and the usefulness of a cost-benefit approach in setting supplemental standards and determining the need for and level of restoration at UMTRA sites. 8 refs., 12 tabs.
Cell emulation and preliminary results.

Science.gov (United States)

2016-07-01

This report details preliminary results of the testing plan implemented by the Hawaii Natural Energy Institute to evaluate Electric Vehicle (EV) battery durability and reliability under electric utility grid operations. Commercial EV battery cells ar...
Preliminary report about nuclear accident of Chernobylsk reactor

International Nuclear Information System (INIS)

Oliveira, A.R. de.

1986-07-01

The preliminary report of nuclear accident at Chernobyl, in URSS is presented. The Chernobyl site is located geographically and the RBMK type reactors - initials of russian words which mean high power pressure tube reactors are described. The conditions of reactor operation in beginning of accident, the events which lead to reactor destruction, the means to finish the fire, the measurements adopted by Russian in the accident location, the estimative of radioactive wastes, the meteorological conditions during the accident, the victims and medical assistence, the sanitary aspects and consequences for population, the evaluation of radiation doses received at small and medium distance and the estimative of reffered doses by population attained are presented. The official communication of Russian Minister Council and the declaration of IAEA general manager during a collective interview in Moscou are annexed. (M.C.K.) [pt
Preliminary Evaluation of Critical Wave Energy Thresholds at Natural and Created Coastal Wetlands

National Research Council Canada - National Science Library

Shafer, Deborah

2003-01-01

This technical note presents an evaluation of the wave climate at eight natural and created coastal wetland sites in an effort to identify the existence of critical wave energy thresholds for long-term marsh stability...
Evaluation of Five Sedimentary Rocks Other Than Salt for Geologic Repository Siting Purposes

Energy Technology Data Exchange (ETDEWEB)

Croff, A.G.; Lomenick, T.F.; Lowrie, R.S.; Stow, S.H.

2003-11-15

The US Department of Energy (DOE), in order to increase the diversity of rock types under consideration by the geologic disposal program, initiated the Sedimary ROck Program (SERP), whose immediate objectiv eis to evaluate five types of secimdnary rock - sandstone, chalk, carbonate rocks (limestone and dolostone), anhydrock, and shale - to determine the potential for siting a geologic repository. The evaluation of these five rock types, together with the ongoing salt studies, effectively results in the consideration of all types of relatively impermeable sedimentary rock for repository purposes. The results of this evaluation are expressed in terms of a ranking of the five rock types with respect to their potential to serve as a geologic repository host rock. This comparative evaluation was conducted on a non-site-specific basis, by use of generic information together with rock evaluation criteria (RECs) derived from the DOE siting guidelines for geologic repositories (CFR 1984). An information base relevant to rock evaluation using these RECs was developed in hydrology, geochemistry, rock characteristics (rock occurrences, thermal response, rock mechanics), natural resources, and rock dissolution. Evaluation against postclosure and preclosure RECs yielded a ranking of the five subject rocks with respect to their potential as repository host rocks. Shale was determined to be the most preferred of the five rock types, with sandstone a distant second, the carbonate rocks and anhydrock a more distant third, and chalk a relatively close fourth.
Evaluation of Five Sedimentary Rocks Other Than Salt for Geologic Repository Siting Purposes

International Nuclear Information System (INIS)

Croff, A.G.; Lomenick, T.F.; Lowrie, R.S.; Stow, S.H.

2003-01-01

The US Department of Energy (DOE), in order to increase the diversity of rock types under consideration by the geologic disposal program, initiated the Sedimary ROck Program (SERP), whose immediate objectiv eis to evaluate five types of secimdnary rock - sandstone, chalk, carbonate rocks (limestone and dolostone), anhydrock, and shale - to determine the potential for siting a geologic repository. The evaluation of these five rock types, together with the ongoing salt studies, effectively results in the consideration of all types of relatively impermeable sedimentary rock for repository purposes. The results of this evaluation are expressed in terms of a ranking of the five rock types with respect to their potential to serve as a geologic repository host rock. This comparative evaluation was conducted on a non-site-specific basis, by use of generic information together with rock evaluation criteria (RECs) derived from the DOE siting guidelines for geologic repositories (CFR 1984). An information base relevant to rock evaluation using these RECs was developed in hydrology, geochemistry, rock characteristics (rock occurrences, thermal response, rock mechanics), natural resources, and rock dissolution. Evaluation against postclosure and preclosure RECs yielded a ranking of the five subject rocks with respect to their potential as repository host rocks. Shale was determined to be the most preferred of the five rock types, with sandstone a distant second, the carbonate rocks and anhydrock a more distant third, and chalk a relatively close fourth.
Temelin 3,4 Siting

International Nuclear Information System (INIS)

Kubanova, Iva; Fuzer, Jiri

2011-01-01

will follow. Siting process is three-step process in the Czech Republic. Finished EIA process managed by Ministry of Environment is a prerequisite for siting approval issued by State Office for Nuclear Safety. Then the final territorial decision is issued by building (construction) authority which can be located either in the relevant close city or in Southern Bohemia Region Office. Temelin site is a proven site, so siting of Temelin 3,4 is focused mainly on verification of available site data and methods used, verification of site suitability for new generation reactors and application of current licensing requirements. As a basis Initial Safety Report must be prepared and covers topics prescribed by the Czech Atomic Law: general project information, site evaluation, technical concept description, preliminary evaluation of operation impact on population, environment (with reference to EIA process), future decommissioning method, physical protection analyses and siting quality assurance evaluation and principles for next stages. CEZ, a. s. currently prepares Initial Safety Report in format pre-agreed with State Office for Nuclear Safety
Preliminary parametric performance assessment of potential final waste forms for alpha low-level waste at the Idaho National Engineering Laboratory. Revision 1

International Nuclear Information System (INIS)

Smith, T.H.; Sussman, M.E.; Myers, J.; Djordjevic, S.M.; DeBiase, T.A.; Goodrich, M.T.; DeWitt, D.

1995-08-01

This report presents a preliminary parametric performance assessment (PA) of potential waste disposal systems for alpha-contaminated, mixed, low-level waste (ALLW) currently stored at the Transuranic Storage Area of INEL. The ALLW, which contains from 10 to 100 nCi/g of transuranic (TRU) radionuclides, is awaiting treatment and disposal. The purpose of this study was to examine the effects of several parameters on the radiological-confinement performance of potential disposal systems for the ALLW. The principal emphasis was on the performance of final waste forms (FWFs). Three categories of FWF (cement, glass, and ceramic) were addressed by evaluating the performance of two limiting FWFs for each category. Performance at five conceptual disposal sites was evaluated to illustrate the effects of site characteristics on the performance of the total disposal system. Other parameters investigated for effects on receptor dose included inventory assumptions, TRU radionuclide concentration, FWF fracture, disposal depth, water infiltration rates, subsurface-transport modeling assumptions, receptor well location, intrusion scenario assumptions, and the absence of waste immobilization. These and other factors were varied singly and in some combinations. The results indicate that compliance of the treated and disposed ALLW with the performance objectives depends on the assumptions made, as well as on the FWF and the disposal site. Some combinations result in compliance, while others do not. The implications of these results for decision making relative to treatment and disposal of the INEL ALLW are discussed. The report compares the degree of conservatism in this preliminary parametric PA against that in four other PAs and one risk assessment. All of the assessments addressed the same disposal site, but different wastes. The report also presents a qualitative evaluation of the uncertainties in the PA and makes recommendations for further study
Evaluation du potentiel éolien des sites de Kayar et de Potou ...

African Journals Online (AJOL)

However, due to the lack of a reliable and accurate atlas of wind in Senegal, previous studies on the evaluation of wind potential are needed in this country. This paper proposes a method for assessing the wind potential applied on two sites and a method of choosing a suitable wind turbine of the site. In this study, the wind ...
Preliminary geological suitability assessment for LILW disposal

International Nuclear Information System (INIS)

Tomse, P.; Mele, I.

2001-01-01

Due to the growing need for a final disposal of LILW, the final solution for the short-lived LILW is the key issue of radioactive waste management in Slovenia at the moment. ARAO - the Slovenian Agency for Radwaste Management - is intensely involved in the re-initiated site selection process for a LILW repository. In this new process we are trying to combine as best as possible the technical, geologically-led and the advocacy-site selection processes. By a combination of technical and volunteer approach to the site selection we wish to guarantee high public involvement and sufficient flexibility of the process to adapt to specific conditions or new circumstances while the project is ongoing. In the technical phase, our tendency is to retain a larger number of potential areas/sites. We also keep open the possibility of choosing the type of repository. The decision between the surface and underground option will be made only once the site has been defined. In accordance with the IAEA recommendations the site selection process is divided into four stages: the conceptual and planning stage, area survey stage, site characterisation stage and site confirmation stage. Last year the area survey stage was started. In the preliminary geological suitability assessment the required natural predisposition of Slovene territory was assessed in order to locate geologically suitable formations. The assessment of natural conditions of the system was based on consideration of the main geological, hydro-geological and seismotectonic conditions. It was performed with ARC/INFO technology. The results are compiled in a map, showing potential areas for underground and surface disposal of LILW in Slovenia. It has been established that there is a potential suitability for both surface and underground disposal on about 10 000 km 2 of the Slovenian territory, which represents almost half of the entire Slovenian territory. These preliminary results are now being carefully re-examined. As an
Towards the Study of the Early Medieval Site Bashanta-II

Directory of Open Access Journals (Sweden)

Ochir-Goryaeva Maria A.

2016-12-01

Full Text Available The authors offer preliminary results on study of a new early medieval site discovered in the Gorodovikovo District (Kalmykia during a field survey near Bashanta-I hillfort at Chapaevskoe Lake (or Tsagan nur in Kalmyk language. The new site is found 8 km to the south-west from Bashanta-I hillfort, on the bank of the Egorlyk River. The site is dated by two radiocarbon dates by the middle of the 7th – late 8th centuries, i.e. by the time of Khazar Khanate. Some preliminary studies on the site included topographical mapping, collection of stray finds and a few prospection pits. These activities yielded numerous ceramic sherds, roof tiles and debris of masonry. Judging by the existing cultural stratum, remains of stone structures made of shell stone blocks and numerous ceramic finds of good quality, the new site was a settlement of Saltovo-Mayaki Culture, presumably a satellite hillfort. The identity of ceramics and construction materials allowed the authors to name this new site as Bashanta-II.
Geological and geophysical investigations in the selection and characterization of the disposal site for high-level nuclear waste in Finland

Energy Technology Data Exchange (ETDEWEB)

Paulamaki, S.; Paananen, M.; Kuivamaki, A. [Geological Survey of Finland, Espoo (Finland); Wikstrom, L. [Posiva Oy, Olkiluoto (Finland)], e-mail: seppo.paulamaki@gtk.fi

2011-07-01

Two power companies, Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy, are preparing for the final disposal of spent nuclear fuel deep in the Finnish bedrock. In the initial phase of the site selection process in the late 1970s and early 1980s, the Geological Survey of Finland (GTK) examined the general bedrock factors that would have to be taken into account in connection with final disposal with reference to the international guidelines adapted to Finnish conditions. On the basis of extensive basic research data, it was concluded that it is possible to find a potential disposal site that fulfils the geological safety criteria. In the subsequent site selection survey covering the whole of Finland, carried out by GTK in 1983-1985, 101 potential investigation areas were discovered. Eventually, five areas were selected by TVO for preliminary site investigations: Romuvaara and Veitsivaara in the Archaean basement complex, Kivetty and Syyry in the Proterozoic granitoid area, and Olkiluoto (TVO's NPP site) in the Proterozoic migmatite area. The preliminary site investigations at the selected sites in 1987-1992 comprised deep drillings together with geological, geophysical, hydrogeological and hydrogeochemical investigations. A conceptual geological bedrock model was constructed for each site, including lithology, fracturing, fracture zones and hydrogeological conditions. On the basis of preliminary site investigations, TVO selected Romuvaara, Kivetty and Olkiluoto for detailed site investigations to be carried out during 1993-2000. After the feasibility studies, the island of Haestholmen, where Fortum's Loviisa nuclear power plant is located, was added to the list of potential disposal sites. In the detailed site investigations, additional data on bedrock were gathered, the previous conceptual geological, hydrogeological and hydrogeochemical models were complemented, the rock mechanical properties of the bedrock were examined, and the constructability
Geological and geophysical investigations in the selection and characterization of the disposal site for high-level nuclear waste in Finland

Energy Technology Data Exchange (ETDEWEB)

Paulamaki, S; Paananen, M; Kuivamaki, A [Geological Survey of Finland, Espoo (Finland); Wikstrom, L. [Posiva Oy, Olkiluoto (Finland)], e-mail: seppo.paulamaki@gtk.fi

2011-07-01

Two power companies, Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy, are preparing for the final disposal of spent nuclear fuel deep in the Finnish bedrock. In the initial phase of the site selection process in the late 1970s and early 1980s, the Geological Survey of Finland (GTK) examined the general bedrock factors that would have to be taken into account in connection with final disposal with reference to the international guidelines adapted to Finnish conditions. On the basis of extensive basic research data, it was concluded that it is possible to find a potential disposal site that fulfils the geological safety criteria. In the subsequent site selection survey covering the whole of Finland, carried out by GTK in 1983-1985, 101 potential investigation areas were discovered. Eventually, five areas were selected by TVO for preliminary site investigations: Romuvaara and Veitsivaara in the Archaean basement complex, Kivetty and Syyry in the Proterozoic granitoid area, and Olkiluoto (TVO's NPP site) in the Proterozoic migmatite area. The preliminary site investigations at the selected sites in 1987-1992 comprised deep drillings together with geological, geophysical, hydrogeological and hydrogeochemical investigations. A conceptual geological bedrock model was constructed for each site, including lithology, fracturing, fracture zones and hydrogeological conditions. On the basis of preliminary site investigations, TVO selected Romuvaara, Kivetty and Olkiluoto for detailed site investigations to be carried out during 1993-2000. After the feasibility studies, the island of Haestholmen, where Fortum's Loviisa nuclear power plant is located, was added to the list of potential disposal sites. In the detailed site investigations, additional data on bedrock were gathered, the previous conceptual geological, hydrogeological and hydrogeochemical models were complemented, the rock mechanical properties of the bedrock were examined, and the constructability and the
Preliminary experimental evaluation of a four wheel motors, batteries plus ultracapacitors and series hybrid powertrain

Energy Technology Data Exchange (ETDEWEB)

Rambaldi, Lorenzo [Interuniversity Research Center on Sustainable Development, Sapienza University of Rome, Rome (Italy); Bocci, Enrico [Department of Mechanics and Aeronautics, Sapienza University of Rome, Rome (Italy); Orecchini, Fabio [Guglielmo Marconi University, Rome (Italy)

2011-02-15

This paper reports the preliminary experimental evaluation of a four wheel motors series hybrid prototype equipped with an internal combustion engine coupled to a generator and an energy recovery system (batteries plus ultracapacitors). The paper analyses global efficiency (energy dissipated to overcome the dissipative forces on energy dissipated in fuel), autonomy in electric configuration, and the efficiency of the regenerative braking system. The tests were carried out in a test cell equipped with a chassis dynamometer. The tests were performed according to the current regulated procedures. A constant speed test was performed in order to evaluate the autonomy of the vehicle in the electric configuration. The results show that the real tank to wheels efficiency is about 30% for HOST as a series hybrid and 79% for HOST as an electric vehicle. (author)
Power plant site evaluation, electric energy demand forecasts - Douglas Point Site. Volume 3. Final report

International Nuclear Information System (INIS)

Wilson, J.W.

1975-07-01

This is part of a series of reports containing an evaluation of the proposed Douglas Point nuclear generating station site located on the Potomac River in Maryland 30 miles south of Washington, D.C. This report contains chapters on the Potomac Electric Power Company's market, forecasting future demand, modelling, a residential demand model, a nonresidential demand model, the Southern Maryland Electric Cooperative Model, short term predictive accuracy, and total system requirements
Establishing a site for A Slovenian LILW repository - 16151

International Nuclear Information System (INIS)

VIRSEK, SANDI; SPILER, JANJA; VESELIC, MIRAN

2009-01-01

In this paper we will describe the practice and siting process for a LILW repository in Slovenia. Slovenia is a small country, and, consequently, its nuclear programme is small. It does include almost everything that large programmes have, but we still do not have a repository. In 2004, the Slovenian Radwaste management agency (ARAO) initiated a new procedure to find a proper location for a LILW repository. ARAO asked all Slovenian communities to participate. All communities have the option to withdraw from the process until they have approved the site. We received eight responses, and we prepared methodologies with different parameters to evaluate all potential sites. All sites were assessed by Slovenian experts, and determinations were based on using prepared methodologies. On the basis of their expert opinions, we prepared a pre-feasibility study and chose the three most suitable sites. With these three we continued the process. After that time, one of the communities withdrew from the procedure, and another one reversed its proposed site and proposed a new one. For the third site we continued with the programme, and we prepared a feasibility study with a Strategic Environmental Impact Assessment and preliminary safety calculations for the comparison of different concepts of disposal units. If everything goes according to the plan for this site and the concept, we expect site approval in the first half of 2009. After that, we will start preparing everything necessary for building permission. (authors)
Angkor site monitoring and evaluation by radar remote sensing

Science.gov (United States)

Chen, Fulong; Jiang, Aihui; Ishwaran, Natarajan

2014-11-01

Angkor, in the northern province of Siem Reap, Cambodia, is one of the most important world heritage sites of Southeast Asia. Seasonal flood and ground sinking are two representative hazards in Angkor site. Synthetic Aperture Radar (SAR) remote sensing has played an important role for the Angkor site monitoring and management. In this study, 46 scenes of TerraSAR data acquired in the span of February, 2011 to December, 2013 were used for the time series analysis and hazard evaluation; that is, two-fold classification for flood area extracting and Multi-Temporal SAR Interferometry (MT-InSAR) for ground subsidence monitoring. For the flood investigation, the original Single Look Complex (SLC) TerraSAR-X data were transferred into amplitude images. Water features in dry and flood seasons were firstly extracted using a proposed mixed-threshold approach based on the backscattering; and then for the correlation analysis between water features and the precipitation in seasonally and annually. Using the MT-InSAR method, the ground subsidence was derived with values ranging from -50 to +12 mm/yr in the observation period of February, 2011 to June, 2013. It is clear that the displacement on the Angkor site was evident, implying the necessity of continuous monitoring.
Site characterization report for the basalt waste isolation project. Volume III

International Nuclear Information System (INIS)

1982-11-01

The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 3 contains chapters 13 through 19: site issues and plans; geoengineering and repository design issues and plans; waste package and site geochemistry issues and plans; performance-assessment issues and plans; site characterization program; quality assurance; and identification of alternate sites

Preliminary development and evaluation of an algae-based air regeneration system

Science.gov (United States)

Nienow, J. A.

2000-01-01

The potential of air regeneration system based on the growth of microalgae on the surface of porous ceramic tubes is evaluated. The algae have been maintained in the system for extended periods, up to 360 days. Preliminary measurements of the photosynthetic capacity have been made for Chlorella vulgaris (UTEX 259), Neospongiococcum punctatum (UTEX 786), Stichococcus sp., and Gloeocapsa sp. Under standard test conditions (photosynthetic photon flux approximately 66 micromoles m-2 s-1, initial CO2 concentration approximately 450 micromoles mol-1), mature tubes remove up to 0.2 micromoles of CO2 per tube per minute. The rate of removal increases with photon flux up to at least 225 micromoles m-2 s-1 (PPF); peak rates of 0.35 micromoles of CO2 per tube per minute have been achieved with Chlorella vulgaris. These rates correspond to between 120 and 210 micromoles of CO2 removed per square meter of projected area per minute.
A critical evaluation of Web sites offering patient information on tinnitus.

LENUS (Irish Health Repository)

Kieran, Stephen M

2012-02-01

The Internet is a vast information resource for both patients and healthcare professionals. However, the quality and content often lack formal scrutiny, so we examined the quality of patient information regarding tinnitus on the Internet. Using the three most popular search engines (google.com, yahoo.com, and msn.com), we found pertinent Web sites using the search term tinnitus. Web sites\\' accountability and authorship were evaluated using previously published criteria. The quality of patient information about tinnitus was assessed using a new 10-point scale, the Tinnitus Information Value (TIV). Statistical analysis was performed using the independent sample t-test (p sites was constructed using the first 30 English-language Web sites identified by each search engine. After duplicates and sites only containing links to other Web sites were eliminated, 39 remained. The mean score for accountability was 2.13 on scale of 0 to 7. The mean TIV was 5.0 on a scale of 0 to 10. Only 12 sites (30.8%) had their authors clearly identified. Twenty-two (56.4%) sites were sponsored by commercial interests or represented private practices. The mean TIV was significantly higher (p = 0.037) for noncommercial (personal, academic institution, or charity) sites (5.88 +\\/- 2.39 SD) than those representing commercial interests (4.32 +\\/- 2.10 SD). Tinnitus information available on the Internet is indeed variable, and care should be taken in recommending tinnitus Web sites to patients.
A qualitative evaluation of radionuclide concentrations in Hanford Site Wildlife, 1983 through 1992

International Nuclear Information System (INIS)

Poston, T.M.; Cooper, A.T.

1994-10-01

Environmental monitoring has been conducted at the U.S. Department of Energy's (DOE's) Hanford Site in southeastern Washington State since 1945. Fish and wildlife have been monitored since 1945, however, a major emphasis on mammals did not occur until the 1970s. This report focuses on the 10-year period from 1983 through 1992. The objectives of this report are to evaluate 90 Sr and 137 Cs concentrations in Site wildlife populations and, when possible, evaluate trends in concentrations over this period of time. No distinct trends in radionuclide concentrations were apparent in most species sampled. Many measurements were at or below the analytical limit of detection. This evaluation found that concentrations of 90 Sr in rabbit and deer bone were elevated in animals collected from areas adjacent to industrialized areas. Similarly, radionuclide concentrations in duck muscle from waterfowl collected at B Pond were elevated with 137 Cs when compared to background concentrations. None of the measured concentrations were high enough to pose any risk to theoretical human consumers of game animals inhabiting the Hanford Site. Estimates of the annual dose from the consumption of 40 kg (88 lb) of Hanford Site wildlife were less than 0.001 times the National Council on Radiation Protection and Measurements and the DOE guideline of 100 mrem/yr
Benefits of Multiple Methods for Evaluating HIV Counseling and Testing Sites in Pennsylvania.

Science.gov (United States)

Encandela, John A.; Gehl, Mary Beth; Silvestre, Anthony; Schelzel, George

1999-01-01

Examines results from two methods used to evaluate publicly funded human immunodeficiency virus (HIV) counseling and testing in Pennsylvania. Results of written mail surveys of all sites and interviews from a random sample of 30 sites were similar in terms of questions posed and complementary in other ways. (SLD)
Preliminary Evaluation of a Social Skills Training and Facilitated Play Early Intervention Programme for Extremely Shy Young Children in China

Science.gov (United States)

Li, Yan; Coplan, Robert J.; Wang, Yuemin; Yin, Jingtong; Zhu, Jingjing; Gao, Zhuqing; Li, Linhui

2016-01-01

The goal of this study was to provide a preliminary evaluation of a social skills and facilitated play early intervention programme to promote social interaction, prosocial behaviours and socio-communicative skills among young extremely shy children in China. Participants were a sample of n = 16 extremely shy young children attending kindergarten…
Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks

Energy Technology Data Exchange (ETDEWEB)

ROGERS, C.A.

2000-02-17

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.
Criticality Safety Evaluation of Hanford Site High-Level Waste Storage Tanks

International Nuclear Information System (INIS)

ROGERS, C.A.

2000-01-01

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions
National Evaluation of the Weatherization Assistance Program: Preliminary Evaluation Plan for Program Year 2006

Energy Technology Data Exchange (ETDEWEB)

Ternes, Mark P [ORNL; Schweitzer, Martin [ORNL; Tonn, Bruce Edward [ORNL; Schmoyer, Richard L [ORNL; Eisenberg, Joel Fred [ORNL

2007-02-01

federal, state, and local initiatives. For example, the use of computerized audits has increased, cooling and baseload measures have been added, weatherization approaches tailored to the unique construction characteristics of mobile homes have been developed, the weatherization of large multifamily buildings has expanded and become more sophisticated, the flexibility to improve 'energy-related' health and safety has been provided, and leveraging with utilities, other state programs, and owners of large multifamily buildings has increased considerably. The Department of Energy tasked ORNL with planning the new evaluation in light of its experience in conducting the previous national evaluation and the metaevaluations. This preliminary evaluation plan, developed by ORNL, documents how the new national evaluation will be performed. In the remaining portion of this section, the purpose and fundamental questions the evaluation will address are identified and how these questions were derived is discussed.
Preventative Vaccines for Zika Virus Outbreak: Preliminary Evaluation.

Science.gov (United States)

Kim, Eun; Erdos, Geza; Huang, Shaohua; Kenniston, Thomas; Falo, Louis D; Gambotto, Andrea

2016-11-01

Since it emerged in Brazil in May 2015, the mosquito-borne Zika virus (ZIKV) has raised global concern due to its association with a significant rise in the number of infants born with microcephaly and neurological disorders such as Guillain-Barré syndrome. We developed prototype subunit and adenoviral-based Zika vaccines encoding the extracellular portion of the ZIKV envelope gene (E) fused to the T4 fibritin foldon trimerization domain (Efl). The subunit vaccine was delivered intradermally through carboxymethyl cellulose microneedle array (MNA). The immunogenicity of these two vaccines, named Ad5.ZIKV-Efl and ZIKV-rEfl, was tested in C57BL/6 mice. Prime/boost immunization regimen was associated with induction of a ZIKV-specific antibody response, which provided neutralizing immunity. Moreover, protection was evaluated in seven-day-old pups after virulent ZIKV intraperitoneal challenge. Pups born to mice immunized with Ad5.ZIKV-Efl were all protected against lethal challenge infection without weight loss or neurological signs, while pups born to dams immunized with MNA-ZIKV-rEfl were partially protected (50%). No protection was seen in pups born to phosphate buffered saline-immunized mice. This study illustrates the preliminary efficacy of the E ZIKV antigen vaccination in controlling ZIKV infectivity, providing a promising candidate vaccine and antigen format for the prevention of Zika virus disease. Copyright Â© 2016 The Authors. Published by Elsevier B.V. All rights reserved.
Preliminary evaluation of licensing issues associated with U.S.-sited CANDU-PHW nuclear power plants

International Nuclear Information System (INIS)

van Erp, J.B.

1977-12-01

The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S
Preliminary evaluation of licensing issues associated with U. S. -sited CANDU-PHW nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

van Erp, J B

1977-12-01

The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S.
Site characterization report for the basalt waste isolation project. Volume II

Energy Technology Data Exchange (ETDEWEB)

None

1982-11-01

The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment.
Site characterization report for the basalt waste isolation project. Volume II

International Nuclear Information System (INIS)

1982-11-01

The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment
Methodology to evaluate the site standard seismic motion for a nuclear facility

International Nuclear Information System (INIS)

Soares, W.A.

1983-03-01

An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic priciples of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; avalable methodologies and recommended procedures to evaluate the site standard seismic motion. (E.G.) [pt
Natural phenomena evaluations of the K-25 site UF6 cylinder storage yards

International Nuclear Information System (INIS)

Fricke, K.E.

1996-01-01

The K-25 Site UF 6 cylinder storage yards are used for the temporary storage of UF 6 normal assay cylinders and long-term storage of other UF 6 cylinders. The K-25 Site UF 6 cylinder storage yards consist of six on-site areas: K-1066-B, K-1066-E, K-1066-F, K-1066-J, K-1066-K and K-1066-L. There are no permanent structures erected on the cylinder yards, except for five portable buildings. The operating contractor for the K-25 Site is preparing a Safety Analysis Report (SAR) to examine the safety related aspects of the K-25 Site UF 6 cylinder storage yards. The SAR preparation encompasses many tasks terminating in consequence analysis for the release of gaseous and liquid UF 6 , one of which is the evaluation of natural phenomena threats, such as earthquakes, floods, and winds. In support of the SAR, the six active cylinder storage yards were evaluated for vulnerabilities to natural phenomena, earthquakes, high winds and tornados, tornado-generated missiles, floods (local and regional), and lightning. This report summarizes those studies. 30 refs
Thermal modelling. Preliminary site description Simpevarp subarea - version 1.2

International Nuclear Information System (INIS)

Sundberg, Jan; Back, Paer-Erik; Bengtsson, Anna; Laendell, Maerta

2005-08-01

This report presents the thermal site descriptive model for the Simpevarp subarea, version 1.2. The main objective of this report is to present the thermal modelling work where data has been identified, quality controlled, evaluated and summarised in order to make an upscaling to lithological domain level possible. The thermal conductivity at possible canister scale has been modelled for four different lithological domains (RSMA01 (Aevroe granite), RSMB01 (Fine-grained dioritoid), RSMC01 (mixture of Aevroe granite and Quartz monzodiorite), and RSMD01 (Quartz monzodiorite)). A main modelling approach has been used to determine the mean value of the thermal conductivity. Three alternative/complementary approaches have been used to evaluate the spatial variability of the thermal conductivity at domain level. The thermal modelling approaches are based on the lithological model for the Simpevarp subarea, version 1.2 together with rock type models constituted from measured and calculated (from mineral composition) thermal conductivities. For one rock type, the Aevroe granite (501044), density loggings within the specific rock type has also been used in the domain modelling in order to consider the spatial variability within the Aevroe granite. This has been possible due to the presented relationship between density and thermal conductivity, valid for the Aevroe granite. Results indicate that the mean of thermal conductivity is expected to exhibit only a small variation between the different domains, from 2.62 W/(m.K) to 2.80 W/(m.K). The standard deviation varies according to the scale considered and for the canister scale it is expected to range from 0.20 to 0.28 W/(m.K). Consequently, the lower confidence limit (95% confidence) for the canister scale is within the range 2.04-2.35 W/(m.K) for the different domains. The temperature dependence is rather small with a decrease in thermal conductivity of 1.1-3.4% per 100 deg C increase in temperature for the dominating rock
Removal site evaluation report on Building 7602 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-09-01

This removal site evaluation report for Building 7602 at Oak Ridge National Laboratory was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the facility pose a substantial risk to human health or the environment (i.e., a high probability of adverse effects) and whether remedial site evaluations or removal actions are, therefore, required. The scope of the project included (1) a search for, and review of, readily available historical records regarding operations and use of the facility (including hazardous substance usage and existing contamination); (2) interviews with facility personnel concerning current and past practices; and (3) a brief walk-through to visually inspect the facility and identify existing hazard areas requiring maintenance actions, removal actions, or remedial evaluation. The results of the removal site evaluation indicate that areas associated with Building 7602 pose no imminent hazards requiring maintenance actions. Adequate engineering and administrative controls are in place and enforced within the facility to ensure worker and environmental protection. Current actions that are being taken to prevent further release of contamination and ensure worker safety within Building 7602 are considered adequate until decontamination and decommissioning activities begin. Given the current status and condition of Building 7602, this removal site evaluation is considered complete and terminated
Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket

Energy Technology Data Exchange (ETDEWEB)

Lian, Qiang; Cui, Shijie [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Tian, Wenxi, E-mail: wxtian@mail.xjtu.edu.cn [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Zhang, Jing; Zhang, Dalin; Su, G.H. [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China)

2017-05-15

Highlights: • The CFETR HCSB blanket has been investigated using RELAP5. • Loss of Off-Site Power is investigated. • The parametric analyses during In-Box LOCA are investigated. • The HCSB blanket for CFETR is designed with sufficient decay heat removal capability. - Abstract: As one of three candidate tritium breeding blanket concepts for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of helium cooled solid breeder (HCSB) blanket was recently proposed. In this paper, the preliminary thermal-hydraulic and safety analyses of the typical outboard equatorial blanket module (No.12) have been carried out using RELAP5/Mod3.4 code. Two design basis accidents are investigated based on the steady-state initialization, including Loss of Off-Site Power and In-Box Loss of Coolant Accident (LOCA). The differences between circulator coast down and circulator rotor locked under Loss of Off-Site Power are compared. Regarding the In-Box LOCA, the influences of different break sizes and locations are thoroughly analyzed based on a relatively accurate modeling method of the heat structures in sub-modules. The analysis results show that the blanket and the combined helium cooling system (HCS) are designed with sufficient decay heat removal capability for both accidents, which can preliminarily verify the feasibility of the conceptual design. The research work can also provide an important reference for parameter optimization of the blanket and its HCS in the next stage.
Site observational work plan for the UMTRA Project Site at Tuba City, Arizona

International Nuclear Information System (INIS)

1994-09-01

The requirements for ground water compliance for Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Tuba City, Arizona, site, are found in the Uranium Mill Tailings Radiation Control Act; Subparts B and C of the U.S. Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings (40 CFR 192 (1994)), and the associated proposed 1987 standards (52 FR 36000). During the surface remedial action, an estimated 1,400,000 cubic yards (yd 3 ) (1,100,000 cubic meters [m 3 ]) of uranium mill tailings and other contaminated materials were consolidated and stabilized in place in an unlined disposal cell covering 50 acres (20 hectares). The surface remedial action was completed in April 1990. Ground water beneath the Tuba City site was contaminated by subsurface migration of water from uranium ore processing activities. The main source of contaminants was water from the tailings piles that began in 1956 when the mill opened and ended in 1966 when the mill closed. A total of 800,000 tons (725,000 tonnes) of uranium ore were processed onsite over a 10-year period. Two processes were used to refine the ore: an acid leach process and a sodium carbonate alkaline process. Water from these tailings then seeped into the ground and migrated downward to the ground water. The Tuba City site is currently in a post-stabilization, prelicensing status. The preliminary ground water compliance strategy at the Tuba City site is active remediation. The specific technology to be evaluated is in situ bioremediation. This selection was made because of the potential ability of bioremediation to reduce concentrations to lower levels than a conventional extraction system and to minimize disturbance of the water resource
Preliminary study of long-term wind characteristics of the Mexican Yucatan Peninsula

International Nuclear Information System (INIS)

Soler-Bientz, Rolando; Watson, Simon; Infield, David

2009-01-01

Mexico's Yucatan Peninsula is one of the most promising areas for wind energy development within the Latin American region but no comprehensive assessment of wind resource has been previously published. This research presents a preliminary analysis of the meteorological parameters relevant to the wind resource in order to find patterns in their long-term behaviour and to establish a foundation for subsequent research into the wind power potential of the Yucatan Peninsula. Three meteorological stations with data measured for a period between 10 and 20 years were used in this study. The monthly trends of ambient temperature, atmospheric pressure and wind speed data were identified and are discussed. The directional behaviour of the winds, their frequency distributions and the related Weibull parameters are presented. Wind power densities for the study sites have been estimated and have been shown to be relatively low (wind power class 1), though a larger number of suitable sites needs to be studied before a definitive resource evaluation can be reported.

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