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Sample records for streamlined site investigations

  1. Assessing Contractor Capabilities for Streamlined Site Investigations

    Science.gov (United States)

    The purpose of this document is to familiarize and encourage brownfields decision makers to investigate and employ innovative methods for characterizing their sites, to assist brownfields decision makers in assessing contractors' capabilities.

  2. Brownfields Assessing Contractor Capabilities for Streamlined Site Investigation: Additional Information Regarding All Appropriate Inquiries and Hiring an Environmental Professional

    Science.gov (United States)

    This document assists Brownfields grantees and other decision makers as they assess the capabilities of contractors and consultants to determine their qualifications to provide streamlined and innovative strategies for the assessment and and cleanup.

  3. Brownfields Assessing Contractor Capabilities for Streamlined Site Investigations -- Additional Information Regarding All Appropriate Inquiries and Hiring an Environmental Professional (November 2006)

    Science.gov (United States)

    Guidance for Brownfields grantees and other decision makers to assess the capabilities of contractors and consultants to determine their qualifications to provide streamlined and innovative strategies for the assessment and cleanup of brownfields.

  4. Streamline-concentration balance model for in-situ uranium leaching and site restoration

    International Nuclear Information System (INIS)

    Bommer, P.M.; Schechter, R.S.; Humenick, M.J.

    1981-03-01

    This work presents two computer models. One describes in-situ uranium leaching and the other describes post leaching site restoration. Both models use a streamline generator to set up the flow field over the reservoir. The leaching model then uses the flow data in a concentration balance along each streamline coupled with the appropriate reaction kinetics to calculate uranium production. The restoration model uses the same procedure except that binary cation exchange is used as the restoring mechanism along each streamline and leaching cation clean up is simulated. The mathematical basis for each model is shown in detail along with the computational schemes used. Finally, the two models have been used with several data sets to point out their capabilities and to illustrate important leaching and restoration parameters and schemes

  5. Streamline-concentration balance model for in situ uranium leaching and site restoration

    International Nuclear Information System (INIS)

    Bommer, P.M.

    1979-01-01

    This work presents two computer models. One describes in situ uranium leaching and the other describes post leaching site restoration. Both models use a streamline generator to set up the flow field over the reservoir. The leaching model then uses the flow data in a concentration balance along each streamline coupled with the appropriate reaction kinetics to calculate uranium production. The restoration model uses the same procedure ecept that binary cation exchange is used as the restoring mechanism along each streamline and leaching cation clean up is stimulated. The mathematical basis for each model is shown in detail along with the computational schemes used. Finally, the two models have been used with several data sets to point out their capabilities and to illustrate important leaching and restoration parameters and schemes

  6. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 574: Neptune, Nevada National Security Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2011-08-31

    This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for closure of Corrective Action Unit (CAU) 574, Neptune. CAU 574 is included in the Federal Facility Agreement and Consent Order (FFACO) (1996 [as amended March 2010]) and consists of the following two Corrective Action Sites (CASs) located in Area 12 of the Nevada National Security Site: (1) CAS 12-23-10, U12c.03 Crater (Neptune); (2) CAS 12-45-01, U12e.05 Crater (Blanca). This plan provides the methodology for the field activities that will be performed to gather the necessary information for closure of the two CASs. There is sufficient information and process knowledge regarding the expected nature and extent of potential contaminants to recommend closure of CAU 574 using the SAFER process. Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, field screening, analytical results, the results of the data quality objective (DQO) process (Section 3.0), and an evaluation of corrective action alternatives (Appendix B), closure in place with administrative controls is the expected closure strategy for CAU 574. Additional information will be obtained by conducting a field investigation to verify and support the expected closure strategy and provide a defensible recommendation that no further corrective action is necessary. This will be presented in a Closure Report that will be prepared and submitted to the Nevada Division of Environmental Protection (NDEP) for review and approval.

  7. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2008-01-01

    This Streamlined Approach for Environmental Restoration Plan covers activities associated with Corrective Action Unit (CAU) 107 of the Federal Facility Agreement and Consent Order (FFACO, 1996 (as amended February 2008)). CAU 107 consists of the following Corrective Action Sites (CASs) located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site. (1) CAS 01-23-02, Atmospheric Test Site - High Alt; (2) CAS 02-23-02, Contaminated Areas (2); (3) CAS 02-23-03, Contaminated Berm; (4) CAS 02-23-10, Gourd-Amber Contamination Area; (5) CAS 02-23-11, Sappho Contamination Area; (6) CAS 02-23-12, Scuttle Contamination Area; (7) CAS 03-23-24, Seaweed B Contamination Area; (8) CAS 03-23-27, Adze Contamination Area; (9) CAS 03-23-28, Manzanas Contamination Area; (10) CAS 03-23-29, Truchas-Chamisal Contamination Area; (11) CAS 04-23-02, Atmospheric Test Site T4-a; (12) CAS 05-23-06, Atmospheric Test Site; (13) CAS 09-23-06, Mound of Contaminated Soil; (14) CAS 10-23-04, Atmospheric Test Site M-10; and (15) CAS 18-23-02, U-18d Crater (Sulky). Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, engineering drawings, field screening, analytical results, and the results of data quality objectives process (Section 3.0), closure in place with administrative controls or no further action will be implemented for CAU 107. CAU 107 closure activities will consist of verifying that the current postings required under Title 10 Code of Federal Regulations (CFR) Part 835 are in place and implementing use restrictions (URs) at two sites, CAS 03-23-29 and CAS 18-23-02. The current radiological postings combined with the URs are adequate administrative controls to limit site access and worker dose

  8. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2009-01-01

    This Streamlined Approach for Environmental Restoration Plan covers activities associated with Corrective Action Unit (CAU) 107 of the Federal Facility Agreement and Consent Order (1996 (as amended February 2008)). CAU 107 consists of the following Corrective Action Sites (CASs) located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site. (sm b ullet) CAS 01-23-02, Atmospheric Test Site - High Alt(sm b ullet) CAS 02-23-02, Contaminated Areas (2)(sm b ullet) CAS 02-23-03, Contaminated Berm(sm b ullet) CAS 02-23-10, Gourd-Amber Contamination Area(sm b ullet) CAS 02-23-11, Sappho Contamination Area(sm b ullet) CAS 02-23-12, Scuttle Contamination Area(sm b ullet) CAS 03-23-24, Seaweed B Contamination Area(sm b ullet) CAS 03-23-27, Adze Contamination Area(sm b ullet) CAS 03-23-28, Manzanas Contamination Area(sm b ullet) CAS 03-23-29, Truchas-Chamisal Contamination Area(sm b ullet) CAS 04-23-02, Atmospheric Test Site T4-a(sm b ullet) CAS 05-23-06, Atmospheric Test Site(sm b ullet) CAS 09-23-06, Mound of Contaminated Soil(sm b ullet) CAS 10-23-04, Atmospheric Test Site M-10(sm b ullet) CAS 18-23-02, U-18d Crater (Sulky) Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, engineering drawings, field screening, analytical results, and the results of data quality objectives process (Section 3.0), closure in place with administrative controls or no further action will be implemented for CAU 107.

  9. Investigating the effects of streamline-based fiber tractography on matrix scaling in brain connective network.

    Science.gov (United States)

    Jan, Hengtai; Chao, Yi-Ping; Cho, Kuan-Hung; Kuo, Li-Wei

    2013-01-01

    Investigating the brain connective network using the modern graph theory has been widely applied in cognitive and clinical neuroscience research. In this study, we aimed to investigate the effects of streamline-based fiber tractography on the change of network properties and established a systematic framework to understand how an adequate network matrix scaling can be determined. The network properties, including degree, efficiency and betweenness centrality, show similar tendency in both left and right hemispheres. By employing the curve-fitting process with exponential law and measuring the residuals, the association between changes of network properties and threshold of track numbers is found and an adequate range of investigating the lateralization of brain network is suggested. The proposed approach can be further applied in clinical applications to improve the diagnostic sensitivity using network analysis with graph theory.

  10. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 575: Area 15 Miscellaneous Sites, Nevada National Security Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States)

    2014-12-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 575, Area 15 Miscellaneous Sites, identified in the Federal Facility Agreement and Consent Order (FFACO). CAU 575 comprises the following four corrective action sites (CASs) located in Area 15 of the Nevada National Security Site: 15-19-02, Waste Burial Pit, 15-30-01, Surface Features at Borehole Sites, 15-64-01, Decontamination Area, 15-99-03, Aggregate Plant This plan provides the methodology for field activities needed to gather the necessary information for closing each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 575 using the SAFER process. Additional information will be obtained by conducting a field investigation to document and verify the adequacy of existing information, to affirm the predicted corrective action decisions, and to provide sufficient data to implement the corrective actions. This will be presented in a closure report that will be prepared and submitted to the Nevada Division of Environmental Protection (NDEP) for review and approval.

  11. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 538: Spill Sites, Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    Alfred Wickline

    2006-04-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions necessary for the closure of Corrective Action Unit (CAU) 538: Spill Sites, Nevada Test Site, Nevada. It has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. A SAFER may be performed when the following criteria are met: (1) Conceptual corrective actions are clearly identified (although some degree of investigation may be necessary to select a specific corrective action before completion of the Corrective Action Investigation [CAI]). (2) Uncertainty of the nature, extent, and corrective action must be limited to an acceptable level of risk. (3) The SAFER Plan includes decision points and criteria for making data quality objective (DQO) decisions. The purpose of the investigation will be to document and verify the adequacy of existing information; to affirm the decision for either clean closure, closure in place, or no further action; and to provide sufficient data to implement the corrective action. The actual corrective action selected will be based on characterization activities implemented under this SAFER Plan. This SAFER Plan identifies decision points developed in cooperation with the Nevada Division of Environmental Protection (NDEP) and where DOE will reach consensus with NDEP before beginning the next phase of work.

  12. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 398: Area 25 Spill Sites, Nevada Test Site, Nevada; TOPICAL

    International Nuclear Information System (INIS)

    K. B. Campbell

    2001-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) plan addresses the activities necessary to close Corrective Action Unit (CAU) 398: Area 25 Spill Sites. CAU 398, located in Area 25 of the Nevada Test Site, is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996), and consists of the following 13 Corrective Action Sites (CASs) (Figure 1): (1) CAS 25-44-01 , a fuel spill on soil that covers a concrete pad. The origins and use of the spill material are unknown, but the spill is suspected to be railroad bedding material. (2) CAS 25-44-02, a spill of liquid to the soil from leaking drums. (3) CAS 25-44-03, a spill of oil from two leaking drums onto a concrete pad and surrounding soil. (4) CAS 25-44-04, a spill from two tanks containing sulfuric acid and sodium hydroxide used for a water demineralization process. (5) CAS 25-25-02, a fuel or oil spill from leaking drums that were removed in 1992. (6) CAS 25-25-03, an oil spill adjacent to a tipped-over drum. The source of the drum is not listed, although it is noted that the drum was removed in 1991. (7) CAS 25-25-04, an area on the north side of the Engine-Maintenance, Assembly, and Disassembly (E-MAD) facility, where oils and cooling fluids from metal machining operations were poured directly onto the ground. (8) CAS 25-25-05, an area of oil and/or hydraulic fluid spills beneath the heavy equipment once stored there. (9) CAS 25-25-06, an area of diesel fuel staining beneath two generators that have since been removed. (10) CAS 25-25-07, an area of hydraulic oil spills associated with a tunnel-boring machine abandoned inside X-Tunnel. (11) CAS 25-25-08, an area of hydraulic fluid spills associated with a tunnel-boring machine abandoned inside Y-Tunnel. (12) CAS 25-25-16, a diesel fuel spill from an above-ground storage tank located near Building 3320 at Engine Test Stand-1 (ETS-1) that was removed in 1998. (13) CAS 25-25-17, a hydraulic oil spill

  13. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 121: Storage Tanks and Miscellaneous Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 121, Storage Tanks and Miscellaneous Sites. CAU 121 is currently listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO, 1996) and consists of three Corrective Action Sites (CASs) located in Area 12 of the Nevada Test Site (NTS): CAS 12-01-01, Aboveground Storage Tank; CAS 12-01-02, Aboveground Storage Tank; and CAS 12-22-26, Drums; 2 AST's. CASs 12-01-01 and 12-01-02 are located to the west of the Area 12 Camp, and CAS 12-22-26 is located near the U-12g Tunnel, also known as G-tunnel, in Area 12 (Figure 1). The aboveground storage tanks (ASTs) present at CASs 12-01-01 and 12-01-02 will be removed and disposed of at an appropriate facility. Soil below the ASTs will be sampled to identify whether it has been impacted with chemicals or radioactivity above action levels. If impacted soil above action levels is present, the soil will be excavated and disposed of at an appropriate facility. The CAS 12-22-26 site is composed of two overlapping areas, one where drums had formerly been stored, and the other where an AST was used to dispense diesel for locomotives used at G-tunnel. This area is located above an underground radioactive materials area (URMA), and within an area that may have elevated background radioactivity because of containment breaches during nuclear tests and associated tunnel reentry operations. CAS 12-22-26 does not include the URMA or the elevated background radioactivity. An AST that had previously been used to store liquid magnesium chloride (MgCl) was properly disposed of several years ago, and releases from this tank are not an environmental concern. The diesel AST will be removed and disposed of at an appropriate facility. Soil at the former drum area and the diesel AST area will be sampled to identify whether it has been impacted by releases, from the drums or the

  14. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 330: Areas 6, 22, and 23 Tanks and Spill Sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    T. M. Fitzmaurice

    2001-08-01

    This Streamlined Approach for Environmental restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 330, Areas 6,22, and 23 Tanks and Spill Sites. The CAUs are currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO). This CAU is located at the Nevada Test Site (NTS) (Figure 1). CAU 330 consists of the following Corrective Action Sites (CASs): (1) CAS 06-02-04 - Consists of an underground tank and piping. This CAS is close to an area that was part of the Animal Investigation Program (AIP), conducted under the U.S. Public Health Service. Its purpose was to study and perform tests on the cattle and wild animals in and around the NTS that were exposed to radionuclides. It is unknown if this tank was part of these operations. (2) CAS 22-99-06 - Is a fuel spill that is believed to be a waste oil release which occurred when Camp Desert Rock was an active facility. This CAS was originally identified as being a small depression where liquids were poured onto the ground, located on the west side of Building T-1001. This building has been identified as housing a fire station, radio station, and radio net remote and telephone switchboard. (3) CAS 23-01-02 - Is a large aboveground storage tank (AST) farm that was constructed to provide gasoline and diesel storage in Area 23. The site consists of two ASTs, a concrete foundation, a surrounding earthen berm, associated piping, and unloading stations. (4) CAS 23-25-05 - Consists of an asphalt oil spill/tar release that contains a wash covered with asphalt oil/tar material, a half buried 208-liter (L) (55-gallon [gal]) drum, rebar, and concrete located in the vicinity.

  15. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 330: Areas 6, 22, and 23 Tanks and Spill Sites, Nevada Test Site, Nevada; TOPICAL

    International Nuclear Information System (INIS)

    T. M. Fitzmaurice

    2001-01-01

    This Streamlined Approach for Environmental restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 330, Areas 6,22, and 23 Tanks and Spill Sites. The CAUs are currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO). This CAU is located at the Nevada Test Site (NTS) (Figure 1). CAU 330 consists of the following Corrective Action Sites (CASs): (1) CAS 06-02-04 - Consists of an underground tank and piping. This CAS is close to an area that was part of the Animal Investigation Program (AIP), conducted under the U.S. Public Health Service. Its purpose was to study and perform tests on the cattle and wild animals in and around the NTS that were exposed to radionuclides. It is unknown if this tank was part of these operations. (2) CAS 22-99-06 - Is a fuel spill that is believed to be a waste oil release which occurred when Camp Desert Rock was an active facility. This CAS was originally identified as being a small depression where liquids were poured onto the ground, located on the west side of Building T-1001. This building has been identified as housing a fire station, radio station, and radio net remote and telephone switchboard. (3) CAS 23-01-02 - Is a large aboveground storage tank (AST) farm that was constructed to provide gasoline and diesel storage in Area 23. The site consists of two ASTs, a concrete foundation, a surrounding earthen berm, associated piping, and unloading stations. (4) CAS 23-25-05 - Consists of an asphalt oil spill/tar release that contains a wash covered with asphalt oil/tar material, a half buried 208-liter (L) (55-gallon[gal]) drum, rebar, and concrete located in the vicinity

  16. Harnessing federal environmental expertise and focusing it on streamlining characterization and remediation at DOE's Hanford Site

    International Nuclear Information System (INIS)

    Erickson, J.K.; Kane, D.A.; McGarry, T.A.

    1993-03-01

    At the US Department of Energy, Richland Field Office (DOE-RL) Hanford Site, environmental restoration is conducted under a Tri-Party Federal Facility Agreement between DOE-RL, the Environmental Protection Agency (EPA) and the Washington State Department of Ecology (Ecology). One result of a dispute resolution was the requirement to conduct an independent review of the policies, procedures, processes, and work practices associated with remedial investigation/feasibility study (RI/FS) activity at Hanford with a goal of reducing it to 30 months. Sixteen experienced and respected federal Environmental Restoration Program/Project Managers were brought to Hanford for a two-week intensive review of the program. This paper outlines the reasons for this tactic, the mechanics of funding the process, and the benefits of this unique approach

  17. Realities of site investigation

    International Nuclear Information System (INIS)

    Beauheim, R.; Ben Benfahel, M.; Byrum, Ch.; Fedor, F.; Geier, J.; Nys, V.; Schelkes, K.; Selroos, J.O.; Szucs, I.; Whittaker, St.

    2007-01-01

    During the working session, Working Group C discussed the following questions proposed by the Scientific Programme Committee of AMIGO 2: - Provide a list of concrete examples of limitations and their reasons. In addressing these issues, consider the relation between what you can measure and what you would like to describe. - Can these limitations be handled by defensible uncertainty descriptions? - What has been your experience in predicting properties/responses and then making comparisons with subsequent measurements? How much 'after-fitting' was necessary? Did the exercise contribute to validation? What did it teach you about your abilities to characterise? - What are the realities of transferability of data between sites? What can actually be transferred (data, conceptual models, evaluation procedures) and what could not? - How have the experiences on possibilities and limitations influenced your investigation programme? - How are the limits in what can be achieved factored into safety assessment and engineering? (authors)

  18. STREAMLINED APPROACH FOR ENVIRONMENTAL RESTORATION PLAN FOR CORRECTIVE ACTION UNIT 116: AREA 25 TEST CELL C FACILITY NEVADA TEST SITE, NEVADA

    International Nuclear Information System (INIS)

    2006-01-01

    This Streamlined Approach for Environmental Restoration Plan identifies the activities required for the closure of Corrective Action Unit 116, Area 25 Test Cell C Facility. The Test Cell C Facility is located in Area 25 of the Nevada Test Site approximately 25 miles northwest of Mercury, Nevada

  19. Critique of one-stop siting in Washington: streamlining review without compromising effectiveness

    International Nuclear Information System (INIS)

    Granger, J.A.; Wise, K.R.

    1980-01-01

    The state of Washington adopted a one-stop power plant siting law in 1970 so that the regulatory elements could be coordinated into a single siting decision. Efficiency improves as duplications and inconsistencies disappear, but increasing lead times and higher costs persist in the state. An analysis of the legislation examines why certain statutory and regulatory provisions allow this to happen, pointing particularly at the review and approval process. Appropriate reforms include adequate funds and staff for the permit agency, early identification of issues, prehearing conferences, and explicit guidelines and standards. 114 references and footnotes

  20. Streamlined RI/FS planning for the groundwater operable unit at the Weldon Spring Site

    International Nuclear Information System (INIS)

    Picel, M.H.; Durham, L.A.; Blunt, D.L.; Hartmann, H.M.

    1995-01-01

    The U.S. Department of Energy (DOE) is conducting cleanup activities at the chemical plant area of the Weldon Spring Site located in St. Charles County, Missouri, about 48 km (30 mi) west of St. Louis and 22 km (14 mi) southwest of the City of St. Charles. The 88-ha (217-acre) chemical plant area is chemically and radioactively contaminated as a result of uranium processing activities conducted by the U.S. Atomic Energy Commission during the 1950s and 1960s. The Army also used the chemical plant area for the production of explosives in the 1940s. The Weldon Spring Site chemical plant area was listed on the National Priorities List (NPL) in 1989. Adjacent to the chemical plant area is another NPL site known as the Weldon Spring Ordnance Works. The ordnance works area is a former explosive production facility that manufactured trinitrotoluene (TNT) and dinitrotoluene (DNT) during World War II. The ordnance works area covers 7,000 ha (17,232 acres); cleanup of this site is managed by the U.S. Army Corps of Engineers (CE)

  1. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 356: Mud Pits and Disposal Sites, Nevada Test Site, Nevada (Revision No. 0, August 2001); FINAL

    International Nuclear Information System (INIS)

    2001-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions necessary for the characterization and closure of Corrective Action Unit (CAU) 356, Mud Pits and Disposal Sites, as identified in the Federal Facility Agreement and Consent Order (FFACO). The CAU, located on the Nevada Test Site in Nevada, consists of seven Corrective Action Sites (CASs): CAS 03-04-01, Area 3 Change House Septic System; CAS 03-09-01, Mud Pit Spill Over; CAS 03-09-03, Mud Pit; CAS 03-09-04, Mud Pit; CAS 03-09-05, Mud Pit; CAS 20-16-01, Landfill; CAS 20-22-21, Drums. Sufficient information and process knowledge from historical documentation and investigations are the basis for the development of the phased approach chosen to address the data collection activities prior to implementing the preferred closure alternative for each CAS. The Phase I investigation will determine through collection of environmental samples from targeted populations (i.e., mud/soil cuttings above textural discontinuity) if contaminants of potential concern (COPCs) are present in concentrations exceeding preliminary action levels (PALs) at each of the CASs. If COPCs are present above PALs, a Phase II investigation will be implemented to determine the extent of contamination to support the appropriate corrective action alternative to complete closure of the site. Groundwater impacts from potentially migrating contaminants are not expected due to the depths to groundwater and limiting hydrologic drivers of low precipitation and high evaporation rates. Future land-use scenarios limit future uses to industrial activities; therefore, future residential uses are not considered. Potential exposure routes to site workers from contaminants of concern in septage and soils include oral ingestion, inhalation, or dermal contact (absorption) through in-advertent disturbance of contaminated structures and/or soils. Diesel within drilling muds is expected to be the primary COPC based on process

  2. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    A. T. Urbon

    2001-09-01

    This Streamlined Approach for Environmental Restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 326, Areas 6 and 27 Release Sites. This CAU is currently listed in the January 2001, Appendix III of the Federal Facilities Agreement and Consent Order (FFACO) (FFACO, 1996). CAU 326 is located on the Nevada Test Site (NTS) and consists of the following four Corrective Action Sites (CASS) (Figure 1): CAS 06-25-01--Is a rupture in an underground pipe that carried heating oil (diesel) from the underground heating oil tank (Tank 6-CP-1) located to the west of Building CP-70 to the boiler in Building CP-1 in the Area 6 Control Point (CP) compound. CAS 06-25-02--A heating oil spill that is a result of overfilling an underground heating oil tank (Tank 6-DAF-5) located at the Area 6 Device Assembly Facility (DAF). CAS 06-25-04--A release of waste oil that occurred while removing used oil to from Tank 6-619-4. Tank 6-619-4 is located northwest of Building 6-619 at the Area 6 Gas Station. CAS 27-25-01--Consists of an excavation that was created in an attempt to remove impacted stained soil from the Site Maintenance Yard in Area 27. Approximately 53.5 cubic meters (m{sup 3}) (70 cubic yards [yd{sup 3}]) of soil impacted by total petroleum hydrocarbons (TPH) and polychlorinated biphenyls (PCBs) was excavated before the excavation activities were halted. The excavation activities were stopped because the volume of impacted soil exceeded estimated quantities and budget.

  3. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada; TOPICAL

    International Nuclear Information System (INIS)

    A. T. Urbon

    2001-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 326, Areas 6 and 27 Release Sites. This CAU is currently listed in the January 2001, Appendix III of the Federal Facilities Agreement and Consent Order (FFACO) (FFACO, 1996). CAU 326 is located on the Nevada Test Site (NTS) and consists of the following four Corrective Action Sites (CASS) (Figure 1): CAS 06-25-01-Is a rupture in an underground pipe that carried heating oil (diesel) from the underground heating oil tank (Tank 6-CP-1) located to the west of Building CP-70 to the boiler in Building CP-1 in the Area 6 Control Point (CP) compound. CAS 06-25-02-A heating oil spill that is a result of overfilling an underground heating oil tank (Tank 6-DAF-5) located at the Area 6 Device Assembly Facility (DAF). CAS 06-25-04-A release of waste oil that occurred while removing used oil to from Tank 6-619-4. Tank 6-619-4 is located northwest of Building 6-619 at the Area 6 Gas Station. CAS 27-25-01-Consists of an excavation that was created in an attempt to remove impacted stained soil from the Site Maintenance Yard in Area 27. Approximately 53.5 cubic meters (m(sup 3)) (70 cubic yards[yd(sup 3)]) of soil impacted by total petroleum hydrocarbons (TPH) and polychlorinated biphenyls (PCBs) was excavated before the excavation activities were halted. The excavation activities were stopped because the volume of impacted soil exceeded estimated quantities and budget

  4. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 553: Areas 19, 20 Mud Pits and Cellars, Nevada Test Site, Nevada, Rev. No. 0

    International Nuclear Information System (INIS)

    Boehlecke, Robert F.

    2006-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions necessary for the closure of Corrective Action Unit (CAU) 553: Areas 19, 20 Mud Pits and Cellars, Nevada Test Site (NTS), Nevada. It has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. A SAFER may be performed when the following criteria are met: (1) Conceptual corrective actions are clearly identified (although some degree of investigation may be necessary to select a specific corrective action before completion of the Corrective Action Investigation [CAI]); (2) Uncertainty of the nature, extent, and corrective action must be limited to an acceptable level of risk; (3) The SAFER Plan includes decision points and criteria for making data quality objective (DQO) decisions. The purpose of the investigation will be to document and verify the adequacy of existing information; to affirm the decision for clean closure, closure in place, or no further action; and to provide sufficient data to implement the corrective action. The actual corrective action selected will be based on characterization activities implemented under this SAFER Plan. This SAFER Plan identifies decision points developed in cooperation with the Nevada Department of Environmental Protection (NDEP), where the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) will reach consensus with the NDEP before beginning the next phase of work. Corrective Action Unit 553 is located in Areas 19 and 20 of the NTS, approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 553 is comprised of the four Corrective Action Sites (CASs) shown on Figure 1-1 and listed below: 19-99-01, Mud Spill; 19-99-11, Mud Spill; 20-09-09, Mud Spill; and 20-99-03, Mud Spill. There is sufficient information and process

  5. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 484: Surface Debris, Waste Sites, and Burn Area, Tonopah Test Range, Nevada

    International Nuclear Information System (INIS)

    Bechel Nevada

    2004-01-01

    This Streamlined Approach for Environmental Restoration plan details the activities necessary to close Corrective Action Unit (CAU) 484: Surface Debris, Waste Sites, and Burn Area (Tonopah Test Range). CAU 484 consists of sites located at the Tonopah Test Range, Nevada, and is currently listed in Appendix III of the Federal Facility Agreement and Consent Order. CAU 484 consists of the following six Corrective Action Sites: (1) CAS RG-52-007-TAML, Davis Gun Penetrator Test; (2) CAS TA-52-001-TANL, NEDS Detonation Area; (3) CAS TA-52-004-TAAL, Metal Particle Dispersion Test; (4) CAS TA-52-005-TAAL, Joint Test Assembly DU Sites; (5) CAS TA-52-006-TAPL, Depleted Uranium Site; and (6) CAS TA-54-001-TANL, Containment Tank and Steel Structure

  6. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Smith, J. L.

    2001-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS)

  7. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    J. L. Smith

    2001-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS).

  8. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 465: Hydronuclear Nevada National Security Site, Nevada, with ROTC 1, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Patrick Matthews

    2011-11-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 465, Hydronuclear, identified in the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 465 comprises the following four corrective action sites (CASs) located in Areas 6 and 27 of the Nevada National Security Site: (1) 00-23-01, Hydronuclear Experiment; (2) 00-23-02, Hydronuclear Experiment; (3) 00-23-03, Hydronuclear Experiment; (4) 06-99-01, Hydronuclear. The sites will be investigated based on the data quality objectives (DQOs) developed on July 6, 2011, by representatives of the Nevada Division of Environmental Protection (NDEP) and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for each CAS in CAU 465. For CAU 465, two potential release components have been identified. The subsurface release component includes potential releases of radiological and nonradiological contaminants from the subsurface hydronuclear experiments and disposal boreholes. The surface release component consists of other potential releases of radiological and nonradiological contaminants to surface soils that may have occurred during the pre- and post-test activities. This plan provides the methodology for collection of the necessary information for closing each CAS component. There is sufficient information and process knowledge from historical documentation, contaminant characteristics, existing regional and site groundwater models, and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 465 using the SAFER process. For potential subsurface releases, flow and transport models will be developed to integrate existing data into a conservative

  9. Hanfor site past practice investigation strategy

    International Nuclear Information System (INIS)

    Thompson, K.M.

    1991-01-01

    The US Department of Energy (DOE), US Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) have negotiated a strategy for performing Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Past Practice investigations in a more streamlined manner with a bias-for-action. This strategy provides new concepts for (1) accelerating decision-making by maximizing the use of existing data consistent with data quality objectives and (2) undertaking expedited response actions and/or interim remedial measures as appropriate to either remove threats to human health and welfare and the environment or to reduce risk by reducing toxicity, mobility or volume of contaminants. Since the goal of the program is cleanup, much more emphasis will be placed on initiating and completing waste site cleanups through interim measures. While investigations and studies are important in meeting long-range goals, there is now agreement by the parties that an appropriate and significant portion of the near-term funding resources can and should be dedicated to remedial work, where there is sufficient information from which to plan and implement interim remedial measures. The initial stages of Hanford clean-up will optimize the use of interim cleanup actions when justified and practicable. Existing data will be evaluated as the initial basis for decision-making. If the data are found to be insufficient, additional essential data will be collected to support the IRM in a limited field investigation (LFI). Only data needed to formulate a conceptual model (source to pathway to receptor) and qualitative risk assessment would be obtained. The data quality objectives of the LFI will be established based on the use of the data in deciding on IRMs

  10. Salmon Site Remedial Investigation Report

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  11. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 539: Area 25 and Area 26 Railroad Tracks, Nevada Test Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Mark Krauss

    2010-06-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 539, Areas 25 and 26 Railroad Tracks, as identified in the Federal Facility Agreement and Consent Order (FFACO). A modification to the FFACOwas approved in May 2010 to transfer the two Railroad Tracks corrective action sites (CASs) from CAU 114 into CAU539. The two CASs are located in Areas 25 and 26 of the Nevada Test Site: • 25-99-21, Area 25 Railroad Tracks • 26-99-05, Area 26 Railroad Tracks This plan provides the methodology for field activities needed to gather the necessary information for closing the two CASs. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of the CAU 539 Railroad Tracks CASs using the SAFER process. Additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for each CAS. The results of the field investigation should support a defensible recommendation that no further corrective action is necessary. If it is determined that complete clean closure cannot be accomplished during the SAFER, then a hold point will have been reached and the Nevada Division of Environmental Protection (NDEP) will be consulted to determine whether the remaining contamination will be closed under the alternative corrective action of closure in place with use restrictions. This will be presented in a closure report that will be prepared and submitted to the NDEP for review and approval. The sites will be investigated based on the data quality objectives (DQOs) developed on December 14, 2009, by representatives of U.S.Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Navarro Nevada Environmental Services, LLC (NNES); and National Security Technologies

  12. Streamlined Approach for Environmental Restoration Work Plan for Corrective Action Unit 461: Joint Test Assembly Sites and Corrective Action Unit 495: Unconfirmed Joint Test Assembly Sites Tonopah Test Range, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Jeff Smith

    1998-08-01

    This Streamlined Approach for Environmental Restoration plan addresses the action necessary for the clean closure of Corrective Action Unit 461 (Test Area Joint Test Assembly Sites) and Corrective Action Unit 495 (Unconfirmed Joint Test Assembly Sites). The Corrective Action Units are located at the Tonopah Test Range in south central Nevada. Closure for these sites will be completed by excavating and evaluating the condition of each artillery round (if found); detonating the rounds (if necessary); excavating the impacted soil and debris; collecting verification samples; backfilling the excavations; disposing of the impacted soil and debris at an approved low-level waste repository at the Nevada Test Site

  13. Potential energy center site investigations

    International Nuclear Information System (INIS)

    Savage, W.F.

    1977-01-01

    Past studies by the AEC, NRC, NSF and others have indicated that energy centers have certain advantages over dispersed siting. There is the need, however, to investigate such areas as possible weather modifications due to major heat releases, possible changes in Federal/state/local laws and institutional arrangements to facilitate implementation of energy centers, and to assess methods of easing social and economic pressures on a surrounding community due to center construction. All of these areas are under study by ERDA, but there remains the major requirement for the study of a potential site to yield a true assessment of the energy center concept. In this regard the Division of Nuclear Research and Applications of ERDA is supporting studies by the Southern and Western Interstate Nuclear Boards to establish state and utility interest in the concept and to carry out screening studies of possible sites. After selection of a final site for center study , an analysis will be made of the center including technical areas such as heat dissipation methods, water resource management, transmission methods, construction methods and schedules, co-located fuel cycle facilities, possible mix of reactor types, etc. Additionally, studies of safeguards, the interaction of all effected entities in the siting, construction, licensing and regulation of a center, labor force considerations in terms of local impact, social and economic changes, and financing of a center will be conducted. It is estimated that the potential site study will require approximately two years

  14. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 544: Cellars, Mud Pits, and Oil Spills, Nevada Test Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Mark Krauss

    2010-07-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 544, Cellars, Mud Pits, and Oil Spills, identified in the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 544 comprises the following 20 corrective action sites (CASs) located in Areas 2, 7, 9, 10, 12, 19, and 20 of the Nevada Test Site (NTS): • 02-37-08, Cellar & Mud Pit • 02-37-09, Cellar & Mud Pit • 07-09-01, Mud Pit • 09-09-46, U-9itsx20 PS #1A Mud Pit • 10-09-01, Mud Pit • 12-09-03, Mud Pit • 19-09-01, Mud Pits (2) • 19-09-03, Mud Pit • 19-09-04, Mud Pit • 19-25-01, Oil Spill • 19-99-06, Waste Spill • 20-09-01, Mud Pits (2) • 20-09-02, Mud Pit • 20-09-03, Mud Pit • 20-09-04, Mud Pits (2) • 20-09-06, Mud Pit • 20-09-07, Mud Pit • 20-09-10, Mud Pit • 20-25-04, Oil Spills • 20-25-05, Oil Spills This plan provides the methodology for field activities needed to gather the necessary information for closing each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 544 using the SAFER process. Using the approach approved for previous mud pit investigations (CAUs 530–535), 14 mud pits have been identified that • are either a single mud pit or a system of mud pits, • are not located in a radiologically posted area, and • have no evident biasing factors based on visual inspections. These 14 mud pits are recommended for no further action (NFA), and further field investigations will not be conducted. For the sites that do not meet the previously approved closure criteria, additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible

  15. Streamlined approach for environmental restoration work plan for Corrective Action Unit 126: Closure of aboveground storage tanks, Nevada Test Site, Nevada. Revision 1

    International Nuclear Information System (INIS)

    1998-07-01

    This plan addresses the closure of several aboveground storage tanks in Area 25 of the Nevada Test Site. The unit is currently identified as Corrective Action Unit 126 in the Federal Facility Agreement and Consent Order and is listed as having six Corrective Action Sites. This plan addresses the Streamlined Approach for Environmental Restoration closure for five of the six sites. Four of the CASs are located at the Engine Test Stand complex and one is located in the Central Support Area. The sites consist of aboveground tanks, two of which were used to store diesel fuel and one stored Nalcool (an antifreeze mixture). The remaining tanks were used as part of a water demineralization process and stored either sulfuric acid or sodium hydroxide, and one was used as a charcoal adsorption furnace. Closure will be completed by removal of the associated piping, tank supports and tanks using a front end loader, backhoe, and/or crane. When possible, the tanks will be salvaged as scrap metal. The piping that is not removed will be sealed using a cement grout

  16. SFR site investigation. Bedrock Hydrogeochemistry

    International Nuclear Information System (INIS)

    Nilsson, Ann-Chatrin; Tullborg, Eva-Lena; Smellie, John; Gimeno, Maria J.; Gomez, Javier B.; Auque, Luis F.; Sandstroem, Bjoern; Pedersen, Karsten

    2011-11-01

    There are plans that the final repository for low and intermediate level radioactive waste, SFR, located about 150 km north of Stockholm, will be extended. Geoscientific studies to define and characterise a suitable bedrock volume for the extended repository have been carried out from 2007 to 2011, and have included the drilling and evaluation of seven new core drilled and four percussion boreholes. These new data, together with existing data extending back to 1985, have been interpreted and modelled in order to provide the necessary information for safety assessment and repository design. This report presents the final hydrogeochemical site description for the SFR site, and will constitute a background report for the integrated site description (the SFR Site Descriptive Model version 1.0) together with corresponding reports from the geological and hydrogeological disciplines. Most of the hydrogeochemical data from the field investigations consist of major ions and isotopes together with sporadic gas, microbe and measured redox data. Despite the close proximity of the Forsmark site, few data from this source are of relevance because of the shallow nature of the SFR site, the fact that SFR is located beneath the Baltic Sea and also the drawdown/upconing impacts of its construction on the hydrogeochemistry. This artificially imposed dynamic flow system is naturally more prevalent along major deformation fracture zones of higher transmissivity, whilst lower transmissive fractures together with the less transmissive bedrock masses between major deformation zones, still retain some evidence of the natural groundwater mixing patterns established prior to the SFR construction. The groundwaters in the SFR dataset cover a depth down to -250 m.a.s.l. with single sampling locations at -300 and -400 m.a.s.l. 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 (-15.5 to -7.5 per mille V

  17. SFR site investigation. Bedrock Hydrogeochemistry

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Ann-Chatrin [Geosigma AB, Uppsala (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden); Smellie, John [Conterra AB, Uppsala (Sweden); Gimeno, Maria J.; Gomez, Javier B.; Auque, Luis F. [Univ. of Zaragoza, Zaragoza (Spain); Sandstroem, Bjoern [WSP Sverige AB, Goeteborg (Sweden); Pedersen, Karsten [Micans AB, Moelnlycke (Sweden)

    2011-11-15

    There are plans that the final repository for low and intermediate level radioactive waste, SFR, located about 150 km north of Stockholm, will be extended. Geoscientific studies to define and characterise a suitable bedrock volume for the extended repository have been carried out from 2007 to 2011, and have included the drilling and evaluation of seven new core drilled and four percussion boreholes. These new data, together with existing data extending back to 1985, have been interpreted and modelled in order to provide the necessary information for safety assessment and repository design. This report presents the final hydrogeochemical site description for the SFR site, and will constitute a background report for the integrated site description (the SFR Site Descriptive Model version 1.0) together with corresponding reports from the geological and hydrogeological disciplines. Most of the hydrogeochemical data from the field investigations consist of major ions and isotopes together with sporadic gas, microbe and measured redox data. Despite the close proximity of the Forsmark site, few data from this source are of relevance because of the shallow nature of the SFR site, the fact that SFR is located beneath the Baltic Sea and also the drawdown/upconing impacts of its construction on the hydrogeochemistry. This artificially imposed dynamic flow system is naturally more prevalent along major deformation fracture zones of higher transmissivity, whilst lower transmissive fractures together with the less transmissive bedrock masses between major deformation zones, still retain some evidence of the natural groundwater mixing patterns established prior to the SFR construction. The groundwaters in the SFR dataset cover a depth down to -250 m.a.s.l. with single sampling locations at -300 and -400 m.a.s.l. and represent a relatively limited salinity range (1,500 to 5,500 mg/L chloride). However, the {delta}{sup 18}O values show a wide variation (-15.5 to -7.5 per mille V

  18. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada Test Site, Nevada, Revision 1

    International Nuclear Information System (INIS)

    2008-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. The Test Cell C (TCC) Facility is located in Area 25 of the Nevada Test Site (NTS) approximately 25 miles northwest of Mercury, Nevada (Figure 1). CAU 116 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) of 1996 (as amended February 2008) and consists of two Corrective Action Sites (CASs): (1) CAS 25-23-20, Nuclear Furnace Piping; and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 is described in the FFACO as the TCC Facility but actually includes Building 3210 and attached concrete shield wall only. CAU 116 will be closed by demolishing Building 3210, the attached concrete shield wall, and the nuclear furnace piping. In addition, as a best management practice (BMP), Building 3211 (moveable shed) will be demolished due to its close proximity to Building 3210. This will aid in demolition and disposal operations. Radiological surveys will be performed on the demolition debris to determine the proper disposal pathway. As much of the demolition debris as space allows will be placed into the Building 3210 basement structure. After filling to capacity with demolition debris, the basement structure will be mounded or capped and closed with administrative controls. Prior to beginning demolition activities and according to an approved Sampling and Analysis Plan (SAP), representative sampling of surface areas that are known, suspected, or have the potential to contain hazardous constituents such as lead or polychlorinated biphenyls (PCBs) will be performed throughout all buildings and structures. Sections 2.3.2, 4.2.2.2, 4.2.2.3, 4.3, and 6.2.6.1 address the methodologies employed that assure the solid debris placed in the basement structure will not contain contaminants of concern (COCs) above hazardous waste levels. The anticipated post

  19. Improving Sampling, Analysis, and Data Management for Site Investigation and Cleanup

    Science.gov (United States)

    The United States Environmental Protection Agency (EPA) supports the adoption of streamlined approaches to sampling, analysis, and data management activities conducted during site assessment, characterization, and cleanup.

  20. Bedrock Hydrogeology - Site investigation SFR

    Energy Technology Data Exchange (ETDEWEB)

    Oehman, Johan [Geosigma AB, Stockholm (Sweden); Bockgaard, Niclas [Golder Assoes AB, Stockholm (Sweden); Follin, Sven [SF GeoLogic AB, Taeby (Sweden)

    2012-06-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has conducted site investigations for a planned extension of the existing final repository for short-lived radioactive waste (SFR). This report presents an integrated analysis and interpretation of the historic data from the existing SFR (1980 - 1986), as well as, from the recent investigations for the planned extension of SFR (2008 - 2009). The primary objective is to establish a conceptual hydrogeological model of the bedrock for safety assessment and design analyses. Analyses and interpretations of all (old and new) hydraulic data are analysed with regard to the recently developed geological deformation zone model of the SFR model domain (Curtis et al. 2011). The methodology used by Curtis et al. (2011) has focussed on magnetic anomalies and deformation zone intercepts with ground surface greater than 300 m. In the hydrogeological modelling, however, it has been considered important to also explore the occurrence and characteristics of shallow horizontal to sub-horizontal structures (sheet joints) inside the SFR model domain. Such structures are of considerable importance for the hydrogeology in the uppermost c. 150 m of bedrock in SDM-Site Forsmark; hence the term Shallow Bedrock Aquifer was used to emphasise their hydraulic significance. In this study, the acronym SBA-structure is used for horizontal structures identified in the hydrogeological modelling. In addition to the predominantly steeply dipping geological deformation zones, eight so-called SBA-structures are modelled deterministically in the hydrogeological model. The SBA-structures are envisaged as hydraulically heterogeneous and composed of clusters of minor gently dipping to horizontal fractures rather than extensive single features. A type of structures that is partly included in the definition of the SBA-structures is the Unresolved Possible Deformations Zone (Unresolved PDZ) intercepts identified by Curtis et al. (2011). The Unresolved

  1. Site investigation SFR. Bedrock geology

    International Nuclear Information System (INIS)

    Curtis, Philip; Markstroem, Ingemar; Petersson, Jesper; Triumf, Carl-Axel; Isaksson, Hans; Mattsson, Haakan

    2011-12-01

    geological tunnel mapping and eleven drill cores remapped according to the Boremap system, input to model version 1.0 has included the results from eight new cored boreholes as well as a fuller integration of Forsmark site investigation data, a further more extensive review of the drill core from an additional 32 boreholes associated with the construction of the existing SFR facility and an updated mapping of the lower construction tunnel. The current modelling work has also reviewed the older SFR data and models. While details concerning the earlier zones lying in immediate contact with the existing SFR facility have been changed, the earlier overall position, orientation and number of these deformation zones is maintained. A significant difference concerns their thickness due to the contrasting methodologies used during the different campaigns. In SFR model version 0.1, a single deformation zone model was produced, with a volume corresponding to the regional model volume. The model contained all the deformation zones modelled irrespective of size. Separate local and regional deformation zone models have been produced in SFR model version 1.0, following resolution criteria for the different model volumes. The local model contains zones with a minimum size of 300 m, while the regional model has structures that have a minimum size constraint of 1,000 m trace length at the ground surface. The selection of these size limits is related to the model volume maximum depth (local model -300 masl and regional model -1,000 masl) and the applied methodology that requires the same model resolution throughout the defined model volume (see Section 5.3.1). To assist hydrogeological modelling work, an updated combined model, including all structures from both the regional and local models, has also been delivered. The existing SFR facility and the rock volume directly to the south-east, which is proposed for the new facility extension, lies within a tectonic block that is bounded to the

  2. Site investigation SFR. Bedrock geology

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, Philip; Markstroem, Ingemar (Golder Associates AB (Sweden)); Petersson, Jesper (Vattenfall Power Consultant AB (Sweden)); Triumf, Carl-Axel; Isaksson, Hans; Mattsson, Haakan (GeoVista AB (Sweden))

    2011-12-15

    the geological tunnel mapping and eleven drill cores remapped according to the Boremap system, input to model version 1.0 has included the results from eight new cored boreholes as well as a fuller integration of Forsmark site investigation data, a further more extensive review of the drill core from an additional 32 boreholes associated with the construction of the existing SFR facility and an updated mapping of the lower construction tunnel. The current modelling work has also reviewed the older SFR data and models. While details concerning the earlier zones lying in immediate contact with the existing SFR facility have been changed, the earlier overall position, orientation and number of these deformation zones is maintained. A significant difference concerns their thickness due to the contrasting methodologies used during the different campaigns. In SFR model version 0.1, a single deformation zone model was produced, with a volume corresponding to the regional model volume. The model contained all the deformation zones modelled irrespective of size. Separate local and regional deformation zone models have been produced in SFR model version 1.0, following resolution criteria for the different model volumes. The local model contains zones with a minimum size of 300 m, while the regional model has structures that have a minimum size constraint of 1,000 m trace length at the ground surface. The selection of these size limits is related to the model volume maximum depth (local model -300 masl and regional model -1,000 masl) and the applied methodology that requires the same model resolution throughout the defined model volume (see Section 5.3.1). To assist hydrogeological modelling work, an updated combined model, including all structures from both the regional and local models, has also been delivered. The existing SFR facility and the rock volume directly to the south-east, which is proposed for the new facility extension, lies within a tectonic block that is bounded

  3. Streamlined approach for environmental restoration closure report for Corrective Action Unit 464: Historical underground storage tank release sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    This report addresses the site characterization of two historical underground storage tank petroleum hydrocarbon release sites identified by Corrective Action Site (CAS) Numbers 02-02-03 and 09-02-01. The sites are located at the Nevada Test Site in Areas 2 and 9 and are concrete bunker complexes (Bunker 2-300, and 9-300). Characterization was completed using drilling equipment to delineate the extent of petroleum hydrocarbons at release site 2-300-1 (CAS 02-02-03). Based on site observations, the low hydrocarbon concentrations detected, and the delineation of the vertical and lateral extent of subsurface hydrocarbons, an ''A through K'' evaluation was completed to support a request for an Administrative Closure of the site

  4. Streamlined approach for environmental restoration closure report for Corrective Action Unit 464: Historical underground storage tank release sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report addresses the site characterization of two historical underground storage tank petroleum hydrocarbon release sites identified by Corrective Action Site (CAS) Numbers 02-02-03 and 09-02-01. The sites are located at the Nevada Test Site in Areas 2 and 9 and are concrete bunker complexes (Bunker 2-300, and 9-300). Characterization was completed using drilling equipment to delineate the extent of petroleum hydrocarbons at release site 2-300-1 (CAS 02-02-03). Based on site observations, the low hydrocarbon concentrations detected, and the delineation of the vertical and lateral extent of subsurface hydrocarbons, an ``A through K`` evaluation was completed to support a request for an Administrative Closure of the site.

  5. Streamlined approach for environmental restoration closure report for Corrective Action Unit 452: Historical underground storage tank release sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    This report addresses the site characterization of three historical underground storage tank (UST) petroleum hydrocarbon release sites identified as 25-3101-1, 25-3102-3, and 25-3152-1. The sites are located within the Nevada Test Site in Area 25 at Buildings 3101, 3102, and 3152. The characterization was completed to support administrative closure of the sites. Characterization was completed using drilling equipment to delineate the extent of hydrocarbon impact. Clean closure had been previously attempted at each of these sites using backhoe equipment without success due to adjacent structures, buried utilities, or depth restrictions associated with each site. Although the depth and extent of hydrocarbon impact was determined to be too extensive for clean closure, it was verified through drilling that the sites should be closed through an administrative closure. The Nevada Administrative Code ''A Through K'' evaluation completed for each site supports that there is no significant risk to human health or the environment from the impacted soils remaining at each site

  6. Green Remediation Best Management Practices: Site Investigation

    Science.gov (United States)

    The U.S. EPA Principles for Greener Cleanups outline the Agency's policy for evaluating and minimizing the environmental 'footprint' of activities undertaken when cleaning up a contaminated site and conducting site investigation.

  7. Streamlined approach for environmental restoration closure report for Corrective Action Unit No. 456: Underground storage tank release site 23-111-1, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    The underground storage tank (UST) release site 23-111-1 is located in Mercury, Nevada. The site is in Area 23 of the Nevada Test Site, (NTS) located on the north side of Building 111. The tank associated with the release was closed in place using cement grout on September 6, 1990. The tank was not closed by removal due to numerous active underground utilities, a high-voltage transformer pad, and overhead power lines. Soil samples collected below the tank bottom at the time of tank closure activities exceeded the Nevada Administrative Code Action Level of 100 milligrams per kilogram (mg/kg) for petroleum hydrocarbons. Maximum concentrations detected were 119 mg/kg. Two passive venting wells were subsequently installed at the tank ends to monitor the progress of biodegradation at the site. Quarterly air sampling from the wells was completed for approximately one year, but was discontinued since data indicated that considerable biodegradation was not occurring at the site

  8. Streamlined approach for environmental restoration closure report for Corrective Action Unit 454: Historical underground storage tank release sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    This report addresses the characterization of three historical underground storage tank (UST) petroleum hydrocarbon release sites identified as 12-B-1, 12-B-3, and 12-COMM-1. The sites are located within the Nevada Test Site in Area 12 at B Tunnel and a former Communications/Power Maintenance Shop. Release Site 12-B-1 was not able to be clean-closed as proposed in the SAFER Plan. However, hydrocarbon impacted soils were excavated down to bedrock. Release Site 12-B-3 was evaluated to verify that the identified release was not associated with the UST removed from the site. Analytical results support the assumption that wood or possibly a roof sealant used as part of the bunker construction could have been the source of hydrocarbons detected. Release Site 12-COMM-1 was not clean closed as proposed in the SAFER Plan. The vertical extent of impacted soils was determined not to extend below a depth of 2.7 m (9 ft) below ground surface (bgs). The lateral extent could not be defined due to the presence of a discontinuous lens of hydrocarbon-impacted soil

  9. Streamlined approach for environmental restoration closure report for Corrective Action Unit 454: Historical underground storage tank release sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report addresses the characterization of three historical underground storage tank (UST) petroleum hydrocarbon release sites identified as 12-B-1, 12-B-3, and 12-COMM-1. The sites are located within the Nevada Test Site in Area 12 at B Tunnel and a former Communications/Power Maintenance Shop. Release Site 12-B-1 was not able to be clean-closed as proposed in the SAFER Plan. However, hydrocarbon impacted soils were excavated down to bedrock. Release Site 12-B-3 was evaluated to verify that the identified release was not associated with the UST removed from the site. Analytical results support the assumption that wood or possibly a roof sealant used as part of the bunker construction could have been the source of hydrocarbons detected. Release Site 12-COMM-1 was not clean closed as proposed in the SAFER Plan. The vertical extent of impacted soils was determined not to extend below a depth of 2.7 m (9 ft) below ground surface (bgs). The lateral extent could not be defined due to the presence of a discontinuous lens of hydrocarbon-impacted soil.

  10. Near Regional and Site Investigations of the Temelin NPP Site

    International Nuclear Information System (INIS)

    Prachar, Ivan; Vacek, Jiri; Heralecky, Pavel

    2011-01-01

    The Temelin NPP is worldwide through heated discussion with nuclear energetic opposition. In addition this discussion goes beyond a border of the Czech Republic. On the other side, results of several international supervisions shown that Temelin NPP is fully comparable with the safest nuclear power plants in the world regarding its technical design and safety functions. This presentation deals with the near regional and site investigations of the Temelin NPP Site. It must be noted that although the Temelin site is situated in the area with low seismicity, item of seismicity is a basic argument against Temelin NPP and therefore a detail seismic hazard assessment was performed

  11. Site investigations for the disposal of spent fuel - investigation program

    International Nuclear Information System (INIS)

    Aeikaes, Timo

    1985-11-01

    The Industrial Power Company Ltd (TVO) is making preparations for the final disposal of spent nuclear fuel into the Finnish bedrock. The revised site investigation program for the years 1986-2010 is presented in this report. The objectives and activities in the near future are described in more detail. The main objectives and frame programs for the investigations in the more distant future are described. The program planning of these investigations are being developed in the preceding site investigations. The investigations for the site selection are divided into four phases: 1983-1985 selection of the investigation areas, preparations for the field investigations, drilling and investigations in a deep test borehole; 1986-1992 preliminary site investigations in 5-10 investigation areas; 1993-2000 detailed site investigations in 2-3 investigation areas. Site selection in the year 2000; 2001-2010 complementary investigations on the selected site. The first investigation phase will be carried out as planned. In this phase a 1001 m deep test borehole was drilled at Lavia in western Finland. With the investigations in the borehole and related development work, preparations were made for the future field investigations. The equipment and investigation methods are being developed during the site investigations. The equipment for taking groundwater samples and the unit for hydraulic testing have been developed. In the future the emphasis in the work will be in developing equipment for monitoring of the hydraulic head and measuring the volumetric flow. In groundwater sampling the present procedure can be improved by adding the test for the in-situ measurements. The results of the field investigations will be stored and processed in a centralized data base. The data base will transmit the results for the interpretation and then the interpreted results transmitted for model calculations and reporting. The cost estimate for the investigations in 1986-2010 is 110-125 million

  12. Impact assessment: Eroding benefits through streamlining?

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Alan, E-mail: alan.bond@uea.ac.uk [School of Environmental Sciences, University of East Anglia (United Kingdom); School of Geo and Spatial Sciences, North-West University (South Africa); Pope, Jenny, E-mail: jenny@integral-sustainability.net [Integral Sustainability (Australia); Curtin University Sustainability Policy Institute (Australia); Morrison-Saunders, Angus, E-mail: A.Morrison-Saunders@murdoch.edu.au [School of Geo and Spatial Sciences, North-West University (South Africa); Environmental Science, Murdoch University (Australia); Retief, Francois, E-mail: francois.retief@nwu.ac.za [School of Geo and Spatial Sciences, North-West University (South Africa); Gunn, Jill A.E., E-mail: jill.gunn@usask.ca [Department of Geography and Planning and School of Environment and Sustainability, University of Saskatchewan (Canada)

    2014-02-15

    This paper argues that Governments have sought to streamline impact assessment in recent years (defined as the last five years) to counter concerns over the costs and potential for delays to economic development. We hypothesise that this has had some adverse consequences on the benefits that subsequently accrue from the assessments. This hypothesis is tested using a framework developed from arguments for the benefits brought by Environmental Impact Assessment made in 1982 in the face of the UK Government opposition to its implementation in a time of economic recession. The particular benefits investigated are ‘consistency and fairness’, ‘early warning’, ‘environment and development’, and ‘public involvement’. Canada, South Africa, the United Kingdom and Western Australia are the jurisdictions tested using this framework. The conclusions indicate that significant streamlining has been undertaken which has had direct adverse effects on some of the benefits that impact assessment should deliver, particularly in Canada and the UK. The research has not examined whether streamlining has had implications for the effectiveness of impact assessment, but the causal link between streamlining and benefits does sound warning bells that merit further investigation. -- Highlights: • Investigation of the extent to which government has streamlined IA. • Evaluation framework was developed based on benefits of impact assessment. • Canada, South Africa, the United Kingdom, and Western Australia were examined. • Trajectory in last five years is attrition of benefits of impact assessment.

  13. Impact assessment: Eroding benefits through streamlining?

    International Nuclear Information System (INIS)

    Bond, Alan; Pope, Jenny; Morrison-Saunders, Angus; Retief, Francois; Gunn, Jill A.E.

    2014-01-01

    This paper argues that Governments have sought to streamline impact assessment in recent years (defined as the last five years) to counter concerns over the costs and potential for delays to economic development. We hypothesise that this has had some adverse consequences on the benefits that subsequently accrue from the assessments. This hypothesis is tested using a framework developed from arguments for the benefits brought by Environmental Impact Assessment made in 1982 in the face of the UK Government opposition to its implementation in a time of economic recession. The particular benefits investigated are ‘consistency and fairness’, ‘early warning’, ‘environment and development’, and ‘public involvement’. Canada, South Africa, the United Kingdom and Western Australia are the jurisdictions tested using this framework. The conclusions indicate that significant streamlining has been undertaken which has had direct adverse effects on some of the benefits that impact assessment should deliver, particularly in Canada and the UK. The research has not examined whether streamlining has had implications for the effectiveness of impact assessment, but the causal link between streamlining and benefits does sound warning bells that merit further investigation. -- Highlights: • Investigation of the extent to which government has streamlined IA. • Evaluation framework was developed based on benefits of impact assessment. • Canada, South Africa, the United Kingdom, and Western Australia were examined. • Trajectory in last five years is attrition of benefits of impact assessment

  14. Salmon Site Remedial Investigation Report, Appendix D

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  15. Salmon Site Remediation Investigation Report, Appendix A

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  16. Salmon Site Remedial Investigation Report, Appendix C

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  17. Salmon Site Remedial Investigation Report, Exhibit 2

    Energy Technology Data Exchange (ETDEWEB)

    USDOE NV

    1999-09-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  18. Salmon Site Remedial Investigation Report, Exhibit 5

    Energy Technology Data Exchange (ETDEWEB)

    USDOE/NV

    1999-09-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  19. Salmon Site Remedial Investigation Report, Appendix C

    Energy Technology Data Exchange (ETDEWEB)

    US DOE/NV

    1999-09-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  20. Salmon Site Remedial Investigation Report, Exhibit 2

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  1. Salmon Site Remedial Investigation Report, Main Body

    Energy Technology Data Exchange (ETDEWEB)

    US DOE/NV

    1999-09-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  2. Salmon Site Remedial Investigation Report, Exhibit 5

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  3. Site investigations. Investigation methods and general execution programme

    International Nuclear Information System (INIS)

    2001-01-01

    SKB plans to commence site investigations in 2002. The present report is a broadening of the general programme and describes the execution of the investigations in so-called discipline-specific programmes for the disciplines geology, rock mechanics, thermal properties, hydrogeology, hydro geochemistry, transport properties of the rock and surface ecosystems. It also describes various technical aspects of drilling, which comprises a significant portion of the investigations. Based on this possible programme, site-specific programmes will then be prepared and adapted to the site-specific questions and conditions on the specific candidate area. The main product of the investigations is a site description. This document presents an integrated description of the site (geosphere and biosphere) and its regional environs with respect to current state and naturally ongoing processes. Provided that the initial site investigation shows that the site is still favourable, complete investigations are commenced. Primary investigation data are stored in SKB's database SICADA. The database's primary data mainly represent parameter values for single measurement points or limited measurement objects. Primary data are subjected to both discipline-specific and integrated analysis and interpretation in order to be able to subdivide the site into suitable geometric units and to assign discipline-specific properties to these geometric units. In this way a three-dimensional, primarily geo scientific, site-descriptive model of rock and ground is built. The site-descriptive model is represented with the aid of both geographic information systems (GIS) and above all SKB's CAD-based computer tool, Rock Visualization System (RVS). RVS is also used as an active instrument in the interpretation of information, especially to be able to judge the relative locations of different deformation zones. When the site has been selected, the investigations are focused on characterizing conditions at depth

  4. Site investigations: Strategy for rock mechanics site descriptive model

    International Nuclear Information System (INIS)

    Andersson, Johan; Christiansson, Rolf; Hudson, John

    2002-05-01

    As a part of the planning work for the Site Investigations, SKB has developed a Rock Mechanics Site Descriptive Modelling Strategy. Similar strategies are being developed for other disciplines. The objective of the strategy is that it should guide the practical implementation of evaluating site specific data during the Site Investigations. It is also understood that further development may be needed. This methodology enables the crystalline rock mass to be characterised in terms of the quality at different sites, for considering rock engineering constructability, and for providing the input to numerical models and performance assessment calculations. The model describes the initial stresses and the distribution of deformation and strength properties of the intact rock, of fractures and fracture zones, and of the rock mass. The rock mass mechanical properties are estimated by empirical relations and by numerical simulations. The methodology is based on estimation of mechanical properties using both empirical and heroretical/numerical approaches; and estimation of in situ rock stress using judgement and numerical modelling, including the influence of fracture zones. These approaches are initially used separately, and then combined to produce the required characterisation estimates. The methodology was evaluated with a Test Case at the Aespoe Hard Rock Laboratory in Sweden. The quality control aspects are an important feature of the methodology: these include Protocols to ensure the structure and coherence of the procedures used, regular meetings to enhance communication, feedback from internal and external reviewing, plus the recording of an audit trail of the development steps and decisions made. The strategy will be reviewed and, if required, updated as appropriate

  5. Site investigations: Strategy for rock mechanics site descriptive model

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden); Christiansson, Rolf [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Hudson, John [Rock Engineering Consultants, Welwyn Garden City (United Kingdom)

    2002-05-01

    As a part of the planning work for the Site Investigations, SKB has developed a Rock Mechanics Site Descriptive Modelling Strategy. Similar strategies are being developed for other disciplines. The objective of the strategy is that it should guide the practical implementation of evaluating site specific data during the Site Investigations. It is also understood that further development may be needed. This methodology enables the crystalline rock mass to be characterised in terms of the quality at different sites, for considering rock engineering constructability, and for providing the input to numerical models and performance assessment calculations. The model describes the initial stresses and the distribution of deformation and strength properties of the intact rock, of fractures and fracture zones, and of the rock mass. The rock mass mechanical properties are estimated by empirical relations and by numerical simulations. The methodology is based on estimation of mechanical properties using both empirical and heroretical/numerical approaches; and estimation of in situ rock stress using judgement and numerical modelling, including the influence of fracture zones. These approaches are initially used separately, and then combined to produce the required characterisation estimates. The methodology was evaluated with a Test Case at the Aespoe Hard Rock Laboratory in Sweden. The quality control aspects are an important feature of the methodology: these include Protocols to ensure the structure and coherence of the procedures used, regular meetings to enhance communication, feedback from internal and external reviewing, plus the recording of an audit trail of the development steps and decisions made. The strategy will be reviewed and, if required, updated as appropriate.

  6. Site investigations. Investigation methods and general execution programme

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-01-01

    SKB plans to commence site investigations in 2002. The present report is a broadening of the general programme and describes the execution of the investigations in so-called discipline-specific programmes for the disciplines geology, rock mechanics, thermal properties, hydrogeology, hydro geochemistry, transport properties of the rock and surface ecosystems. It also describes various technical aspects of drilling, which comprises a significant portion of the investigations. Based on this possible programme, site-specific programmes will then be prepared and adapted to the site-specific questions and conditions on the specific candidate area. The main product of the investigations is a site description. This document presents an integrated description of the site (geosphere and biosphere) and its regional environs with respect to current state and naturally ongoing processes. Provided that the initial site investigation shows that the site is still favourable, complete investigations are commenced. Primary investigation data are stored in SKB's database SICADA. The database's primary data mainly represent parameter values for single measurement points or limited measurement objects. Primary data are subjected to both discipline-specific and integrated analysis and interpretation in order to be able to subdivide the site into suitable geometric units and to assign discipline-specific properties to these geometric units. In this way a three-dimensional, primarily geo scientific, site-descriptive model of rock and ground is built. The site-descriptive model is represented with the aid of both geographic information systems (GIS) and above all SKB's CAD-based computer tool, Rock Visualization System (RVS). RVS is also used as an active instrument in the interpretation of information, especially to be able to judge the relative locations of different deformation zones. When the site has been selected, the investigations are focused on characterizing

  7. Geotechnical investigations of the PEP site

    International Nuclear Information System (INIS)

    Gould, R.S.

    1976-02-01

    The purpose of this paper is to summarize the general nature of the geology and rock and soil formations of the PEP site as they relate to the design and construction of the project; to describe site investigation programs and to catalog the geotechnical information presently available about the site. The recently-completed investigation of subterranean conditions around the PEP ring when coupled with previous surveys gives us a good understanding of what to expect with regard to tunneling, undertaking larger underground excavations and constructing research halls are the interaction areas. It bears out the predictions made in Jacobs and Associates' report of 1973; i.e., that the ring housing construction is classified as soft-ground tunneling and that large underground openings, such as region 10 and the injection junction structures, will require great attention to support. A shield or shields will probably be required. On the positive side, the site affords very good conditions for soft-ground tunneling. Water will be a problem in some areas, but not an unsolvable one. The possibility of encountering lethal or explosive gases, almost always the case in tunneling in California's coastal formations, exists but has not been ascertained. Finally, no reasons to change current cost estimates or schedules have merged from the investigation. 13 refs., 1 fig

  8. Alternative approaches to improve site investigations

    International Nuclear Information System (INIS)

    Beach, R.B.; Silka, L.R.

    1992-01-01

    Common complaints about standard investigations at hazardous waste sites include high costs and long time frames. Investigations at military bases as part of the installation restoration program or base closures suffer additionally from nonuniformity of approach and results and redundancy of work effort conducted by multiple environmental contractors. The problems of high costs and long time frames can be minimized by the consistent use of alternative sampling methods (such as soil gas surveys) and the utilization of analytical screening procedures at both on-site and off-site laboratories. Acceptable data quality is maintained by several procedures. Incorporation of quality control measures (10 % frequency), such as matrix spikes and duplicates, into the alternative analytical techniques allows assessment of the data quality relative to predetermined data quality objectives (DQOs). Confirmation of the screening results (10% frequency) using standard US EPA methods, such as the contract laboratory program (CLP) statement of work (SOW), allows an additional evaluation of the data accuracy. Depending on the investigative objectives, knowledge based computer systems (expert systems,) could be used to improve uniformity of site evaluations. Several case histories will be presented demonstrating how soil gas surveys, screening analyses and standard analyses can be utilized to give increased site information in a reduced time frame and at a cost savings of 30 to 40%. One case history illustrates a screening technique developed by the author for polynuclear aromatics (semi-volatile organic compounds) that can be conducted at a cost savings of 90% relative to a standard US EPA method. A comparison of the phased investigative approach to one using an integrated field team is presented for fuel spill or UST areas

  9. Streamlining Research by Using Existing Tools

    OpenAIRE

    Greene, Sarah M.; Baldwin, Laura-Mae; Dolor, Rowena J.; Thompson, Ella; Neale, Anne Victoria

    2011-01-01

    Over the past two decades, the health research enterprise has matured rapidly, and many recognize an urgent need to translate pertinent research results into practice, to help improve the quality, accessibility, and affordability of U.S. health care. Streamlining research operations would speed translation, particularly for multi-site collaborations. However, the culture of research discourages reusing or adapting existing resources or study materials. Too often, researchers start studies and...

  10. Geophysical investigation, Salmon Site, Lamar County, Mississippi

    International Nuclear Information System (INIS)

    1995-02-01

    Geophysical surveys were conducted in 1992 and 1993 on 21 sites at the Salmon Site (SS) located in Lamar County, Mississippi. The studies are part of the Remedial Investigation/Feasibility Study (RI/FS) being conducted by IT Corporation for the U.S. Department of Energy (DOE). During the 1960s, two nuclear devices and two chemical tests were detonated 826 meters (in) (2710 feet [ft]) below the ground surface in the salt dome underlying the SS. These tests were part of the Vela Uniform Program conducted to improve the United States capability to detect, identify, and locate underground nuclear detonations. The RI/FS is being conducted to determine if any contamination is migrating from the underground shot cavity in the salt dome and if there is any residual contamination in the near surface mud and debris disposal pits used during the testing activities. The objective of the surface geophysical surveys was to locate buried debris, disposal pits, and abandoned mud pits that may be present at the site. This information will then be used to identify the locations for test pits, cone penetrometer tests, and drill hole/monitor well installation. The disposal pits were used during the operation of the test site in the 1960s. Vertical magnetic gradient (magnetic gradient), electromagnetic (EM) conductivity, and ground-penetrating radar (GPR) surveys were used to accomplish these objectives. A description of the equipment used and a theoretical discussion of the geophysical methods are presented Appendix A. Because of the large number of figures relative to the number of pages of text, the geophysical grid-location maps, the contour maps of the magnetic-gradient data, the contour maps of the EM conductivity data, and the GPR traverse location maps are located in Appendix B, Tabs I through 22. In addition, selected GPR records are located in Appendix C

  11. Hanford site past practice investigation strategy: Lessons learned

    International Nuclear Information System (INIS)

    Thompson, K. Michael

    1992-01-01

    The U. S. Department of Energy (DOE), U. S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) have negotiated a strategy for performing Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Past Practice investigations in a more streamlined manner with a bias-for-action. This strategy provides new concepts for 1) accelerating decision-making by maximizing the use of existing data consistent with data quality objectives and 2) undertaking expedited response actions and/or interim remedial measures as appropriate to either remove threats to human health and welfare and the environment or to reduce risk by reducing toxicity, mobility or volume of contaminants. Since the goal of the program is cleanup, much more emphasis will be placed on initiating and completing waste site cleanups through interim measures. While investigations and studies are important in meeting long-range goals, there is now agreement by the parties that an appropriate and significant portion of the near-term funding resources can and should be dedicated to remedial work, where there is sufficient information from which to plan and implement interim remedial measures. The initial stages of Hanford clean-up will optimize the use of interim cleanup actions when justified and practicable. Existing data will be evaluated as the initial basis for decision-making. If the data are found to be insufficient, additional essential data will be collected to support the IRM in a limited field investigation (LFI). Only data needed to formulate a conceptual model (source to pathway to receptor) and qualitative risk assessment would be obtained. The data quality objectives of the LFI will be established based on the use of the data in deciding on IRMs. The data might not need to be of the same quality needed to support final RODs, since the IRM itself would yield valuable information for

  12. Bedrock Hydrogeology-Site investigation SFR

    International Nuclear Information System (INIS)

    Oehman, Johan; Bockgaard, Niclas; Follin, Sven

    2012-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has conducted site investigations for a planned extension of the existing final repository for short-lived radioactive waste (SFR). This report presents an integrated analysis and interpretation of the historic data from the existing SFR (1980 - 1986), as well as, from the recent investigations for the planned extension of SFR (2008 - 2009). The primary objective is to establish a conceptual hydrogeological model of the bedrock for safety assessment and design analyses. Analyses and interpretations of all (old and new) hydraulic data are analysed with regard to the recently developed geological deformation zone model of the SFR model domain (Curtis et al. 2011). The methodology used by Curtis et al. (2011) has focussed on magnetic anomalies and deformation zone intercepts with ground surface greater than 300 m. In the hydrogeological modelling, however, it has been considered important to also explore the occurrence and characteristics of shallow horizontal to sub-horizontal structures (sheet joints) inside the SFR model domain. Such structures are of considerable importance for the hydrogeology in the uppermost c. 150 m of bedrock in SDM-Site Forsmark; hence the term Shallow Bedrock Aquifer was used to emphasise their hydraulic significance. In this study, the acronym SBA-structure is used for horizontal structures identified in the hydrogeological modelling. In addition to the predominantly steeply dipping geological deformation zones, eight so-called SBA-structures are modelled deterministically in the hydrogeological model. The SBA-structures are envisaged as hydraulically heterogeneous and composed of clusters of minor gently dipping to horizontal fractures rather than extensive single features. A type of structures that is partly included in the definition of the SBA-structures is the Unresolved Possible Deformations Zone (Unresolved PDZ) intercepts identified by Curtis et al. (2011). The Unresolved

  13. Hydrogeologic investigations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Hawkins, W.L.; Trudeau, D.A.; Drellack, S.L.

    1992-01-01

    The Nevada Test Site was established in 1950 as a continental area for testing nuclear devices and, since 1963, all nuclear detonations there have been underground. Most tests are conducted in vertical shafts with a small percentage conducted in tunnels. The majority of detonation points are above the water table, primarily in volcanic rocks or alluvium. In the testing areas the water table is 450--700 m below the surface. Pre- and post- event geologic investigations are conducted for each test location and long-term studies assess the impact of underground testing on a more regional scale. Studies in progress have not identified any impact on the regional ground water system from testing, but some local effects have been recognized. In some areas where several large tests have been conducted below the water table, water levels hundreds of meters above the regional water table have been measured and radioactivity has been discovered associated with fractures in a few holes. Flow-through and straddle packer testing has revealed unexpectedly high hydraulic pressures at depth. Recently, a multiple completion monitoring well installed to study three zones has confirmed the existence of a significant upward hydraulic gradient. These observations of local pressurization and fracture flow are being further explored to determine the influence of underground nuclear testing on the regional hydrogeologic system

  14. Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 120: Areas 5 and 6 Aboveground Storage Tanks, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Allison Urban

    1999-06-01

    This Closure Report provides documentation for the closure of Corrective Action Unit 120. CAU 120 consists of two Corrective Action Sites located in Areas 5 and 6 of the Nevada Test Site. CAS 05-01-01 is located in Area 5 and consists of three 45,800-liter aboveground storage tanks, piping, and debris associated with Well RNM-1. CAS 06-01-01 in Area 6 consists of two aboveground storage tanks and two tanker trailers All the CAU 120 items have been used to convey or contain radiologically contaminated fluid from post-nuclear event activities at the NTS> Closure of this CAU was completed by collecting samples to identify the appropriate method of disposal for tanks, piping, debris, and tankers in each CAS. Placing low-level radioactive waste into the appropriate containers and disposing of waste in the Area 5 Radioactive Waste Management Site, the Area 9 10C Landfill, and the Area 3 Radioactive Waste Management Site.

  15. Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 120: Areas 5 and 6 Aboveground Storage Tanks, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Allison Urban

    1999-01-01

    This Closure Report provides documentation for the closure of Corrective Action Unit 120. CAU 120 consists of two Corrective Action Sites located in Areas 5 and 6 of the Nevada Test Site. CAS 05-01-01 is located in Area 5 and consists of three 45,800-liter aboveground storage tanks, piping, and debris associated with Well RNM-1. CAS 06-01-01 in Area 6 consists of two aboveground storage tanks and two tanker trailers All the CAU 120 items have been used to convey or contain radiologically contaminated fluid from post-nuclear event activities at the NTS> Closure of this CAU was completed by collecting samples to identify the appropriate method of disposal for tanks, piping, debris, and tankers in each CAS. Placing low-level radioactive waste into the appropriate containers and disposing of waste in the Area 5 Radioactive Waste Management Site, the Area 9 10C Landfill, and the Area 3 Radioactive Waste Management Site

  16. Streamlined approach for environmental restoration closure report for Corrective Action Unit 120: Areas 5 and 6 aboveground storage tanks, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    This Closure Report provides documentation for the closure of Corrective Action Unit (CAU) 120 of the Federal Facilities Agreement and Consent Order (FFACO). CAU 120 consists of two Corrective Action Sites (CASs) located in Areas 5 and 6 of the Nevada Test Site (NTS), which are approximately 130 kilometers (80 miles) northwest of Las Vegas, Nevada. CAS 05-01-01 is located in Area 5 and consists of three 45,800-liter (12,100-gallon) aboveground storage tanks (ASTs), piping, and debris associated with Well RNM-1. CAS 06-01-01 consists of two ASTs and two tanker trailers (all portable) that were originally located at the Area 6 Cp-50 Hot Park and which had been moved to the Area 6 Waste Handling Facility. All of the items in CAU 120 have been used to contain or convey radiologically contaminated fluid that was generated during post-nuclear event activities at the NTS.

  17. Streamlined approach for environmental restoration closure report for Corrective Action Unit 120: Areas 5 and 6 aboveground storage tanks Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1999-06-01

    This Closure Report provides documentation for the closure of Corrective Action Unit (CAU) 120 of the Federal Facilities Agreement and Consent Order (FFACO). CAU 120 consists of two Corrective Action Sites (CASs) located in Areas 5 and 6 of the Nevada Test Site (NTS), which are approximately 130 kilometers (80 miles) northwest of Las Vegas, Nevada. CAS 05-01-01 is located in Area 5 and consists of three 45,800-liter (12,100-gallon) aboveground storage tanks (ASTs), piping, and debris associated with Well RNM-1. CAS 06-01-01 consists of two ASTs and two tanker trailers (all portable) that were originally located at the Area 6 Cp-50 Hot Park and which had been moved to the Area 6 Waste Handling Facility. All of the items in CAU 120 have been used to contain or convey radiologically contaminated fluid that was generated during post-nuclear event activities at the NTS

  18. Small Scale Multisource Site – Hydrogeology Investigation

    Science.gov (United States)

    A site impacted by brackish water was evaluated using traditional hydrogeologic and geochemical site characterization techniques. No single, specific source of the brine impacted ground water was identified. However, the extent of the brine impacted ground water was found to be...

  19. Archaeological Investigations at a Wisconsin Petroglyph Site

    Directory of Open Access Journals (Sweden)

    Jack Steinbring

    2014-01-01

    Full Text Available Preliminary test excavations at the Hensler Petroglyph Site in East Central Wisconsin, U.S.A. have disclosed the remains of aboriginal engravings below Aeolian sediments dated to ca. 15,000 years B.P. The stratified deposits lying adjacent to an engraved panel, containing 35 pecked images, have yielded animal-like cobbles, some covered with red ochre, apparently picked for some esoteric use. The site itself has unusual natural shapes in the rock formation, along with acoustical properties, lightning strikes, a magnetic anomaly, and geographic prominence. Collectively these factors are thought to have attracted the ancient rock artists to the site.

  20. Site description of Laxemar at completion of the site investigation phase. SDM-Site Laxemar

    International Nuclear Information System (INIS)

    2009-12-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has undertaken site characterisation in two different areas, Forsmark and Laxemar-Simpevarp, in order to identify a suitable location for a geological repository of spent nuclear fuel according to the KBS-3 method. The site investigations have been conducted in campaigns, punctuated by data freezes. After each data freeze, the site data have been analysed and modelling has been carried out with the overall purpose to develop a site descriptive model (SDM). The site descriptive model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It is also essential for safety assessment, since the SDM is the only source for site-specific input. Another important use of the site descriptive model is in the environmental impact assessment. An SDM is an integrated model of geology, thermal properties, rock mechanics, hydrogeology, hydrogeochemistry, bedrock transport properties and a description of the surface system. The site descriptive model compiled in the current report, SDM-Site Laxemar, presents an integrated understanding of the Laxemar-Simpevarp area (with special emphasis on the Laxemar subarea) at the completion of the surface-based investigations, which were conducted during the period 2002 to 2007. A summary is also provided of the abundant underlying data and the discipline specific models that support the site understanding. The description relies heavily on background reports that address, in particular, details of the data analyses and modelling of the different disciplines. The Laxemar-Simpevarp area is located in the province of Smaaland within the municipality of Oskarshamn, about 230 km south of Stockholm. The candidate area for site investigation is located along the shoreline of the strait of Kalmarsund, within a 1.8 billion year old suite of well preserved bedrock belonging to the Transscandinavian Igneous Belt formed during

  1. Site description of Forsmark at completion of the site investigation phase. SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    2008-12-15

    The Swedish Nuclear Fuel and Waste Management Co., SKB, has undertaken site characterisation in two different areas, Forsmark and Laxemar-Simpevarp, in order to identify a suitable location for a geological repository of spent nuclear fuel according to the KBS-3 method. The site investigations have been conducted in campaigns, punctuated by data freezes. After each data freeze, the site data have been analysed and modelling has been carried out with the overall purpose to develop a site descriptive model (SDM). The site descriptive model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It is also essential for safety assessment, since the model is the only source for site-specific input. Another important use of the site descriptive model is in the environmental impact assessment. An SDM is an integrated model for geology, thermal properties, rock mechanics, hydrogeology, hydrogeochemistry, bedrock transport properties and a description of the surface system. The site descriptive model compiled in the current report, SDM-Site, presents an integrated understanding of the Forsmark area at the completion of the surface-based investigations, which were conducted at Forsmark during the period 2002 to 2007. It also provides a summary of the abundant underlying data and the discipline-specific models that support the site understanding. The description relies heavily on background reports that address, in particular, details in data analyses and modelling in the different disciplines. The Forsmark area is located in northern Uppland within the municipality of Oesthammar, about 120 km north of Stockholm. The candidate area for site investigation is located along the shoreline of Oeregrundsgrepen, within the north-western part of a major tectonic lens that formed between 1.87 and 1.85 billion years ago during the Svecokarelian orogeny. The candidate area is approximately 6 km long and 2 km wide. The

  2. Site description of Laxemar at completion of the site investigation phase. SDM-Site Laxemar

    Energy Technology Data Exchange (ETDEWEB)

    2009-12-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has undertaken site characterisation in two different areas, Forsmark and Laxemar-Simpevarp, in order to identify a suitable location for a geological repository of spent nuclear fuel according to the KBS-3 method. The site investigations have been conducted in campaigns, punctuated by data freezes. After each data freeze, the site data have been analysed and modelling has been carried out with the overall purpose to develop a site descriptive model (SDM). The site descriptive model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It is also essential for safety assessment, since the SDM is the only source for site-specific input. Another important use of the site descriptive model is in the environmental impact assessment. An SDM is an integrated model of geology, thermal properties, rock mechanics, hydrogeology, hydrogeochemistry, bedrock transport properties and a description of the surface system. The site descriptive model compiled in the current report, SDM-Site Laxemar, presents an integrated understanding of the Laxemar-Simpevarp area (with special emphasis on the Laxemar subarea) at the completion of the surface-based investigations, which were conducted during the period 2002 to 2007. A summary is also provided of the abundant underlying data and the discipline specific models that support the site understanding. The description relies heavily on background reports that address, in particular, details of the data analyses and modelling of the different disciplines. The Laxemar-Simpevarp area is located in the province of Smaaland within the municipality of Oskarshamn, about 230 km south of Stockholm. The candidate area for site investigation is located along the shoreline of the strait of Kalmarsund, within a 1.8 billion year old suite of well preserved bedrock belonging to the Transscandinavian Igneous Belt formed during

  3. Site description of Forsmark at completion of the site investigation phase. SDM-Site Forsmark

    International Nuclear Information System (INIS)

    2008-12-01

    The Swedish Nuclear Fuel and Waste Management Co., SKB, has undertaken site characterisation in two different areas, Forsmark and Laxemar-Simpevarp, in order to identify a suitable location for a geological repository of spent nuclear fuel according to the KBS-3 method. The site investigations have been conducted in campaigns, punctuated by data freezes. After each data freeze, the site data have been analysed and modelling has been carried out with the overall purpose to develop a site descriptive model (SDM). The site descriptive model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It is also essential for safety assessment, since the model is the only source for site-specific input. Another important use of the site descriptive model is in the environmental impact assessment. An SDM is an integrated model for geology, thermal properties, rock mechanics, hydrogeology, hydrogeochemistry, bedrock transport properties and a description of the surface system. The site descriptive model compiled in the current report, SDM-Site, presents an integrated understanding of the Forsmark area at the completion of the surface-based investigations, which were conducted at Forsmark during the period 2002 to 2007. It also provides a summary of the abundant underlying data and the discipline-specific models that support the site understanding. The description relies heavily on background reports that address, in particular, details in data analyses and modelling in the different disciplines. The Forsmark area is located in northern Uppland within the municipality of Oesthammar, about 120 km north of Stockholm. The candidate area for site investigation is located along the shoreline of Oeregrundsgrepen, within the north-western part of a major tectonic lens that formed between 1.87 and 1.85 billion years ago during the Svecokarelian orogeny. The candidate area is approximately 6 km long and 2 km wide. The

  4. Execution programme for the initial site investigations at Forsmark

    International Nuclear Information System (INIS)

    2002-05-01

    In the feasibility studies that were completed in 2001, eight sites were identified as potentially suitable for hosting a repository. All the identified sites meet the safety requirements with respect to bedrock conditions that could be checked at that time. The feasibility studies have revealed good potential when it comes to the technical and environmental aspects as well. Based on an integrated evaluation SKB proposed to start site investigations with test drillings at three sites; Forsmark, Simpevarp and Tierp. Site investigations have started at Forsmark and Simpevarp. The municipal council of Tierp voted no to a site investigation in April 2002. The site investigations are divided into two main phases; initial and complete investigations. Initial site investigations are performed to identify the site within a specified area that is deemed to be most suitable for a deep repository and to determine whether the feasibility study's judgement of the suitability of the area holds up in the light of borehole data from repository depth. The initial site investigations are expected to take 1.5-2 years. If the assessment shows that the site has good potential to host a repository, complete site investigations will follow for an expected duration of 3.5-4 years. The purpose of the complete site investigations is to gather all information required to select one of the sites as the main alternative and to apply for a permit for construction of the deep repository at that site. A general programme in which the results from feasibility studies are summarized, the candidate sites presented and the framework of programme for the site investigation phase presented has been published. The general programme, and main references to the programme, specifies which data are required in order to design the repository and carry out a safety assessment, how the investigations should be carried out in order to provide these data, criteria with which the site must comply, as well as

  5. Execution programme for the initial site investigations at Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    In the feasibility studies that were completed in 2001, eight sites were identified as potentially suitable for hosting a repository. All the identified sites meet the safety requirements with respect to bedrock conditions that could be checked at that time. The feasibility studies have revealed good potential when it comes to the technical and environmental aspects as well. Based on an integrated evaluation SKB proposed to start site investigations with test drillings at three sites; Forsmark, Simpevarp and Tierp. Site investigations have started at Forsmark and Simpevarp. The municipal council of Tierp voted no to a site investigation in April 2002. The site investigations are divided into two main phases; initial and complete investigations. Initial site investigations are performed to identify the site within a specified area that is deemed to be most suitable for a deep repository and to determine whether the feasibility study's judgement of the suitability of the area holds up in the light of borehole data from repository depth. The initial site investigations are expected to take 1.5-2 years. If the assessment shows that the site has good potential to host a repository, complete site investigations will follow for an expected duration of 3.5-4 years. The purpose of the complete site investigations is to gather all information required to select one of the sites as the main alternative and to apply for a permit for construction of the deep repository at that site. A general programme in which the results from feasibility studies are summarized, the candidate sites presented and the framework of programme for the site investigation phase presented has been published. The general programme, and main references to the programme, specifies which data are required in order to design the repository and carry out a safety assessment, how the investigations should be carried out in order to provide these data, criteria with which the site must comply, as well as

  6. 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.)

  7. 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

  8. Streamlined approach to waste management at CRL

    International Nuclear Information System (INIS)

    Adams, L.; Campbell, B.

    2011-01-01

    Radioactive, mixed, hazardous and non-hazardous wastes have been and continue to be generated at Chalk River Laboratories (CRL) as a result of research and development activities and operations since the 1940s. Over the years, the wastes produced as a byproduct of activities delivering the core missions of the CRL site have been of many types, and today, over thirty distinct waste streams have been identified, all requiring efficient management. With the commencement of decommissioning of the legacy created as part of the development of the Canadian nuclear industry, the volumes and range of wastes to be managed have been increasing in the near term, and this trend will continue into the future. The development of a streamlined approach to waste management is a key to successful waste management at CRL. Waste management guidelines that address all of the requirements have become complex, and so have the various waste management groups receiving waste, with their many different processes and capabilities. This has led to difficulties for waste generators in understanding all of the requirements to be satisfied for the various CRL waste receivers, whose primary concerns are to be safe and in compliance with their acceptance criteria and license conditions. As a result, waste movement on site can often be very slow, especially for non-routine waste types. Recognizing an opportunity for improvement, the Waste Management organization at CRL has implemented a more streamlined approach with emphasis on early identification of waste type and possible disposition path. This paper presents a streamlined approach to waste identification and waste management at CRL, the implementation methodology applied and the early results achieved from this process improvement. (author)

  9. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E.

    1998-10-02

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina.

  10. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    International Nuclear Information System (INIS)

    Palmer, E.

    1998-01-01

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina

  11. Guideline for environmental site investigations in Manitoba : June 1998

    International Nuclear Information System (INIS)

    1998-06-01

    The procedures for the investigation and characterization of contaminated sites in Manitoba are described in an effort to provide a baseline for developing applicable risk-based remedial action and management plans. This document presents information regarding the methods and protocols for sites where the quality of groundwater, surface water, sediments or soil may have been affected by pollutants as a result of past or present usage of the site. The 1998 document focuses on petroleum impacted sites and also includes the requirements for the investigation of sites potentially impacted by other pollutants. It is based on the principles established by the Canadian Council of Ministers of the Environment for the management of sites in Canada and the requirements of the Manitoba Contaminated Sites Remediation and Consequential Amendments Act. Manitoba's petroleum storage program and the hazardous waste management program, including the disposal or treatment of contaminated soils are also summarized

  12. When is there sufficient information from the Site Investigations?

    International Nuclear Information System (INIS)

    Andersson, Johan; Munier, Raymond; Stroem, Anders; Soederbaeck, Bjoern; Almen, Karl-Erik; Olsson, Lars

    2004-04-01

    SKB has started site investigations for a deep repository for spent nuclear fuel at two different sites in Sweden. The investigations should provide necessary information for a licence application aimed at starting underground exploration. The investigations and analyses of them are supposed to provide the broad knowledge base that is required to achieve the overall goals of the site investigation phase. The knowledge will be utilized to evaluate the suitability of investigated sites for the deep repository and must be comprehensive enough to: Show whether the selected site satisfies requirements on safety and technical aspects. Serve as a basis for adaptation of the deep repository to the characteristics of the site with an acceptable impact on society and the environment. Permit comparisons with other investigated sites. Furthermore, the investigations are discontinued when the reliability of the site description has reached such a level that the body of data for safety assessment and design is sufficient, or until the body of data shows that the rock does not satisfy the requirements. These objectives are valid, but do not provide sufficient and concrete guidance. For this reason SKB has conducted this project which should acquire concrete guidance on how to judge when the surface based Site Investigation Phase does not need to continue. After a general assessment of the problem, the following specific objectives of the current work were identified: Demonstrate concretely how the assessed uncertainties in a Site Description based on a specific level of investigations, together with expected feedback from Safety Assessment and Engineering, can be used to decide whether the site investigations are sufficient - or need to continue. This demonstration will be based on a practical application of relevant aspects of decision analysis tools. Highlight and make concrete the type of feedback to be expected from Safety Assessment and Engineering and show how this feedback

  13. Streamline-based microfluidic device

    Science.gov (United States)

    Tai, Yu-Chong (Inventor); Zheng, Siyang (Inventor); Kasdan, Harvey (Inventor)

    2013-01-01

    The present invention provides a streamline-based device and a method for using the device for continuous separation of particles including cells in biological fluids. The device includes a main microchannel and an array of side microchannels disposed on a substrate. The main microchannel has a plurality of stagnation points with a predetermined geometric design, for example, each of the stagnation points has a predetermined distance from the upstream edge of each of the side microchannels. The particles are separated and collected in the side microchannels.

  14. Remedial Investigation of Hanford Site Releases to the Columbia River

    International Nuclear Information System (INIS)

    Lerch, J.A.

    2009-01-01

    In south-central Washington State, the Columbia River flows through the U.S. Department of Energy Hanford Site. A primary objective of the Hanford Site cleanup mission is protection of the Columbia River, through remediation of contaminated soil and groundwater that resulted from its weapons production mission. Within the Columbia River system, surface water, sediment, and biota samples related to potential Hanford Site hazardous substance releases have been collected since the start of Hanford operations. The impacts of Hanford Site hazardous substance releases to the Columbia River in areas upstream, within, and downstream of the Hanford Site boundary have been previously investigated as mandated by the U.S. Department of Energy requirements under the Atomic Energy Act. The impacts are now being assessed under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 via a remedial investigation. The Remedial Investigation Work Plan for Hanford Site Releases to the Columbia River has been developed and issued to initiate the remedial investigation. The work plan establishes a phased approach to characterize contaminants, assess current risks, and determine whether or not there is a need for any cleanup actions. Field investigation activities began in October 2008 and are anticipated to continue into Fall 2009 over a 120 mile stretch of the Columbia River. Information gained from performing this remedial investigation will ultimately be used to help make final regulatory decisions for cleaning up Hanford Site contamination that exists in and along the Columbia River. (authors)

  15. Parameters of importance to determine during geoscientific site investigation

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [QuantiSci AB (Sweden); Almen, K.E. [KEA GEO-Konsult AB (Sweden); Ericsson, Lars O.; Karlsson, Fred; Stroem, A. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Fredriksson, Anders [ADG Grundteknik AB (Sweden); Stanfors, R. [Roy Stanfors Consulting AB (Sweden)

    1998-06-01

    This document identifies and describes geo-scientific parameters that are of importance in order to carry out performance and safety assessments of a deep repository for spent nuclear fuel, based on the information that can be obtained from a site investigation. The document also discusses data needs for planning and design of the rock works and for description of other environmental aspects. Evaluation of the different parameters is discussed in the document as well. The document was produced by a working group consisting of the authors and various SKB staff and consultants, and comprises a step in the planning of a geo-scientific investigation programme at the sites where site investigations will be conducted. The goals of the work presented in this report can be derived directly from SKBs ongoing RD and D Programme. The programme stipulates that a geo-scientific site investigation programme must be available before a site investigation begins. This programme is supposed to specify the goals, measurement methods and evaluation methodology, as well as the acceptance criteria against which the site is evaluated. It is pointed out that site evaluation is a collective term for an interactive process consisting of different parts 65 refs, 15 figs, 12 tabs

  16. Execution programme for the initial site investigations at Simpevarp

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-10-01

    In the feasibility studies that were completed in 2001, eight sites were identified as potentially suitable for hosting a repository. All the identified sites meet the safety requirements with respect to bedrock conditions that could be checked at that time. The feasibility studies have revealed good potential when it comes to the technical and environmental aspects as well. Based on an integrated evaluation SKB proposed to start site investigations with test drillings at three sites; Simpevarp, Forsmark, and Tierp north. The site investigations have started at Simpevarp and Forsmark. The municipal council of Tierp rejected a site investigation in April 2002. The site investigations are divided into two main phases; initial and complete investigations. Initial Site Investigation is performed to identify the site within a specified area that is deemed to be most suitable for a deep repository and to determine whether the feasibility study's judgement of the suitability of the area holds up in the light of borehole data from repository depth. The Initial Site Investigation is expected to take about 3 years. If the assessment shows that the site has good potential to host a repository, Complete Site Investigation will follow for an expected duration of another 3 years. The purpose of the Complete Site Investigation is to gather all information required to select one of the sites as the main alternative and to apply for a permit for construction of the deep repository at that site. The site-specific programme gives an overview of the whole site investigation phase as well as a detailed description of the initial stage. The results of the initial investigations will determine whether Simpevarp is appropriate for further investigation, i.e. the Complete Site Investigation. This document summarizes the investigations that will be carried out at Simpevarp during the Initial Site Investigations. The document is a working document, which will be successively updated as

  17. Execution programme for the initial site investigations at Simpevarp

    International Nuclear Information System (INIS)

    2002-10-01

    In the feasibility studies that were completed in 2001, eight sites were identified as potentially suitable for hosting a repository. All the identified sites meet the safety requirements with respect to bedrock conditions that could be checked at that time. The feasibility studies have revealed good potential when it comes to the technical and environmental aspects as well. Based on an integrated evaluation SKB proposed to start site investigations with test drillings at three sites; Simpevarp, Forsmark, and Tierp north. The site investigations have started at Simpevarp and Forsmark. The municipal council of Tierp rejected a site investigation in April 2002. The site investigations are divided into two main phases; initial and complete investigations. Initial Site Investigation is performed to identify the site within a specified area that is deemed to be most suitable for a deep repository and to determine whether the feasibility study's judgement of the suitability of the area holds up in the light of borehole data from repository depth. The Initial Site Investigation is expected to take about 3 years. If the assessment shows that the site has good potential to host a repository, Complete Site Investigation will follow for an expected duration of another 3 years. The purpose of the Complete Site Investigation is to gather all information required to select one of the sites as the main alternative and to apply for a permit for construction of the deep repository at that site. The site-specific programme gives an overview of the whole site investigation phase as well as a detailed description of the initial stage. The results of the initial investigations will determine whether Simpevarp is appropriate for further investigation, i.e. the Complete Site Investigation. This document summarizes the investigations that will be carried out at Simpevarp during the Initial Site Investigations. The document is a working document, which will be successively updated as

  18. Hydrogeological Site Descriptive Model - a strategy for its development during Site Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Rhen, Ingvar [SWECO VIAK AB, Goeteborg (Sweden); Follin, Sven [SF GeoLogic AB, Stockholm (Sweden); Hermanson, Jan [Golder Associates, Stockholm (Sweden)

    2003-04-01

    The report is to present a strategy for the development of the Site Descriptive Hydrogeological Model within the SKB Site Investigation Programme. The report, and similar reports from the Geology, Rock Mechanics, Thermal properties, Hydrogeochemistry, Transport Properties and Surface Ecosystem disciplines are intended to guide SKB Site Descriptive Modelling but also to provide the authorities with an overview of how the modelling should be performed. Thus the objectives of this report are to: provide guidelines for the modelling of different sites resulting in consistent handling of modelling issues during the Site Investigations, provide a structure for the modelling sequence that is suitable for the establishment of a Site Descriptive model and provide some necessary details that should be considered in a Site Descriptive model.

  19. Hydrogeological Site Descriptive Model - a strategy for its development during Site Investigations

    International Nuclear Information System (INIS)

    Rhen, Ingvar; Follin, Sven; Hermanson, Jan

    2003-04-01

    The report is to present a strategy for the development of the Site Descriptive Hydrogeological Model within the SKB Site Investigation Programme. The report, and similar reports from the Geology, Rock Mechanics, Thermal properties, Hydrogeochemistry, Transport Properties and Surface Ecosystem disciplines are intended to guide SKB Site Descriptive Modelling but also to provide the authorities with an overview of how the modelling should be performed. Thus the objectives of this report are to: provide guidelines for the modelling of different sites resulting in consistent handling of modelling issues during the Site Investigations, provide a structure for the modelling sequence that is suitable for the establishment of a Site Descriptive model and provide some necessary details that should be considered in a Site Descriptive model

  20. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Wickline, Alfred

    2005-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action

  1. Forsmark site investigation. Programme for long-term observations of geosphere and biosphere after completed site investigations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-06-15

    The site investigation at Forsmark was terminated the last of June, 2007. Hundreds of investigations have been conducted during a period of more than five years. Monitoring of a number of geoscientific parameters and biological objects has been one important part of the site investigation programme. Monitoring is defined as recurrent measurements of the same parameters/objects, so that time series are generated. Long-term monitoring of for example weather parameters, surface water discharge in brooks, and the groundwater head in a large number of boreholes has been conducted during the site investigations. Furthermore, repeated sampling of precipitation, surface water and groundwater in soil and rock for hydrochemical analyses has been carried out, and the groundwater flow in isolated borehole sections has been measured several times. Besides, some biological objects, for example rare bird species, have been invented each year of the site investigation. The measured parameters and the invented objects are characterized by a certain degree of time dependent variability, which is also site-specific. The aim of the monitoring is primarily to establish the 'undisturbed' conditions, the so called 'baseline'. If a deep repository is sited at Forsmark, many site-specific conditions will change, due to natural causes as well as to the construction works. Knowledge about the undisturbed conditions strengthens the ability to reveal and quantify such changes and to distinguish natural changes from those caused by the human activities. Another object of monitoring is to, by the study of the variability pattern of the monitored parameters, elevate the knowledge about the underlying, often complex causes governing the variations. In this way the description of site-specific conditions may be more precise and the prospects of modelling important processes are improved. After completion of the site investigations, a period of about two years will follow, when

  2. Forsmark site investigation. Programme for long-term observations of geosphere and biosphere after completed site investigations

    International Nuclear Information System (INIS)

    2007-06-01

    The site investigation at Forsmark was terminated the last of June, 2007. Hundreds of investigations have been conducted during a period of more than five years. Monitoring of a number of geoscientific parameters and biological objects has been one important part of the site investigation programme. Monitoring is defined as recurrent measurements of the same parameters/objects, so that time series are generated. Long-term monitoring of for example weather parameters, surface water discharge in brooks, and the groundwater head in a large number of boreholes has been conducted during the site investigations. Furthermore, repeated sampling of precipitation, surface water and groundwater in soil and rock for hydrochemical analyses has been carried out, and the groundwater flow in isolated borehole sections has been measured several times. Besides, some biological objects, for example rare bird species, have been invented each year of the site investigation. The measured parameters and the invented objects are characterized by a certain degree of time dependent variability, which is also site-specific. The aim of the monitoring is primarily to establish the 'undisturbed' conditions, the so called 'baseline'. If a deep repository is sited at Forsmark, many site-specific conditions will change, due to natural causes as well as to the construction works. Knowledge about the undisturbed conditions strengthens the ability to reveal and quantify such changes and to distinguish natural changes from those caused by the human activities. Another object of monitoring is to, by the study of the variability pattern of the monitored parameters, elevate the knowledge about the underlying, often complex causes governing the variations. In this way the description of site-specific conditions may be more precise and the prospects of modelling important processes are improved. After completion of the site investigations, a period of about two years will follow, when the investigation

  3. [Organising an investigation site: a national training reference document].

    Science.gov (United States)

    Cornu, Catherine; David, Frédérique; Duchossoy, Luc; Hansel-Esteller, Sylvie; Bertoye, Pierre-Henri; Giacomino, Alain; Mouly, Stéphane; Diebolt, Vincent; Blazejewski, Sylvie

    2014-01-01

    Several surveys have shown a declining performance of French investigators in conducting clinical trials. This is partly due to insufficient and heterogeneous investigator training and site organisation. A multidisciplinary group was set up to propose solutions. We describe the tools developed to improve study site organisation. This working group was made up of clinical research experts from academia, industry, drug regulatory authorities, general practice, and consulting. Methods and tools were developed to improve site organisation. The proposed tools mainly focus on increasing investigators' awareness of their responsibilities, their research environment, the importance of a thorough feasibility analysis, and the implementation of active patient recruitment strategies. These tools should be able to improve site organisation and performances in conducting clinical trials. © 2014 Société Française de Pharmacologie et de Thérapeutique.

  4. Site investigation - equipment for geological, geophysical, hydrogeological and hydrochemical characterization

    International Nuclear Information System (INIS)

    Almen, K.E.; Fridh, B.; Johansson, B.E.; Sehlstedt, M.

    1986-11-01

    The investigations are performed within a site investigation program. In total about 60,000 m of cored 56 mm boreholes have been drilled and investigated at eight study sites. A summarized description of the main investigation methods is included. Instruments for geophysical investigations contains equipment for ground measurements as well as for borehole logging. The Geophysical investigations including the borehole radar measurements, are indirect methods for the geological and hydrogeological characterization of the rock formation. Great effort has been laid on the development of hydrogeological instruments for hydraulic tests and groundwater head measurements. In order to obtain hydrochemical investigations with high quality, a complete system for sampling and analysis of ground water has been developed. (orig./PW)

  5. Streamlining Smart Meter Data Analytics

    DEFF Research Database (Denmark)

    Liu, Xiufeng; Nielsen, Per Sieverts

    2015-01-01

    of the so-called big data possible. This can improve energy management, e.g., help utilities improve the management of energy and services, and help customers save money. As this regard, the paper focuses on building an innovative software solution to streamline smart meter data analytic, aiming at dealing......Today smart meters are increasingly used in worldwide. Smart meters are the advanced meters capable of measuring customer energy consumption at a fine-grained time interval, e.g., every 15 minutes. The data are very sizable, and might be from different sources, along with the other social......-economic metrics such as the geographic information of meters, the information about users and their property, geographic location and others, which make the data management very complex. On the other hand, data-mining and the emerging cloud computing technologies make the collection, management, and analysis...

  6. Oskarshamn site investigation. Programme for further investigations of bedrock, soil, water and environment in Laxemar subarea

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    SKB (the Swedish Nuclear Fuel and Waste Management Co), has been conducting a site investigation at Simpevarp and Laxemar in Oskarshamn for siting of a final repository for spent nuclear fuel. An equivalent investigation is being conducted in Forsmark in Ohmmeter's. The initial part of the site investigations had been completed for the both of the subareas Simpevarp and Laxemar in the autumn of 2004. Based on the results of these investigations, SKB preliminarily prioritized the Laxemar subarea for further investigations. A programme was presented for the first stage of the complete site investigation in the Laxemar subarea, along with the main features of the remainder of the site investigation. The programme included investigations up until the summer of 2005 and was particularly aimed at obtaining answers to several vital questions so that the subsequent investigations could be focused on the rock areas judged to be most suitable for a final repository. These investigations have now been completed. This report presents the programme for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, analyses and evaluations of data from completed investigations, and the needs for additional data to be able to evaluate the site as a siting alternative for the final repository. The account mainly covers the investigations on the site. All other work - analyses, site descriptive modelling, facility design, safety assessments and studies and assessments of consequences for the environment, human health and society - are only mentioned to the extent necessary in order to place the investigations in their context. The direction of the site investigation in Oskarshamn and the investigation programme presented in this report is based on SKB's preliminary decision to prioritize the Laxemar subarea for further investigations. A final decision on the direction of the site

  7. Oskarshamn site investigation. Programme for further investigations of bedrock, soil, water and environment in Laxemar subarea

    International Nuclear Information System (INIS)

    2006-03-01

    SKB (the Swedish Nuclear Fuel and Waste Management Co), has been conducting a site investigation at Simpevarp and Laxemar in Oskarshamn for siting of a final repository for spent nuclear fuel. An equivalent investigation is being conducted in Forsmark in Ohmmeter's. The initial part of the site investigations had been completed for the both of the subareas Simpevarp and Laxemar in the autumn of 2004. Based on the results of these investigations, SKB preliminarily prioritized the Laxemar subarea for further investigations. A programme was presented for the first stage of the complete site investigation in the Laxemar subarea, along with the main features of the remainder of the site investigation. The programme included investigations up until the summer of 2005 and was particularly aimed at obtaining answers to several vital questions so that the subsequent investigations could be focused on the rock areas judged to be most suitable for a final repository. These investigations have now been completed. This report presents the programme for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, analyses and evaluations of data from completed investigations, and the needs for additional data to be able to evaluate the site as a siting alternative for the final repository. The account mainly covers the investigations on the site. All other work - analyses, site descriptive modelling, facility design, safety assessments and studies and assessments of consequences for the environment, human health and society - are only mentioned to the extent necessary in order to place the investigations in their context. The direction of the site investigation in Oskarshamn and the investigation programme presented in this report is based on SKB's preliminary decision to prioritize the Laxemar subarea for further investigations. A final decision on the direction of the site

  8. A geotechnical investigation of a deep ocean site

    International Nuclear Information System (INIS)

    Freeman, T.J.; Schuttenhelm, R.T.E.

    1990-01-01

    A site investigation in deep water often relies solely on laboratory tests to evaluate the geotechnical properties of the sediments. This imposes two fundamental limitations on the investigation: The maximum depth to which the properties can be profiled and the uncertainty of sample disturbance and de-pressurization effects on the measured data. This paper uses results from investigations performed in a water depth of 5.4 km at an abyssal plain site, Great Meteor East (GME), to illustrate how ambiguities can arise in laboratory measurements of strength, and discusses how a simple in-situ test, the expendable penetrator, can be used to corroborate the laboratory data

  9. The Nirex Sellafield site investigation: the role of geophysical interpretation

    International Nuclear Information System (INIS)

    Muir Wood, R.; Woo, G.; MacMillan, G.

    1992-01-01

    This report reviews the methods by which geophysical data are interpreted, and used to characterize the 3-D geology of a site for potential storage of radioactive waste. The report focuses on the NIREX site investigation at Sellafield, for which geophysical observations provide a significant component of the structural geological understanding. In outlining the basic technical principles of seismic data processing and interpretation, and borehole logging, an attempt has been made to identify errors, uncertainties, and the implicit use of expert judgement. To enhance the reliability of a radiological probabilistic risk assessment, recommendations are proposed for independent use of the primary NIREX geophysical site investigation data in characterizing the site geology. These recommendations include quantitative procedures for undertaking an uncertainty audit using a combination of statistical analysis and expert judgement. (author)

  10. When is there sufficient information from the Site Investigations?

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden); Munier, Raymond; Stroem, Anders; Soederbaeck, Bjoern [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Almen, Karl-Erik [KEA Geo-konsult (Sweden); Olsson, Lars [Geostatistik AB, Tumba (Sweden)

    2004-04-01

    SKB has started site investigations for a deep repository for spent nuclear fuel at two different sites in Sweden. The investigations should provide necessary information for a licence application aimed at starting underground exploration. The investigations and analyses of them are supposed to provide the broad knowledge base that is required to achieve the overall goals of the site investigation phase. The knowledge will be utilized to evaluate the suitability of investigated sites for the deep repository and must be comprehensive enough to: Show whether the selected site satisfies requirements on safety and technical aspects. Serve as a basis for adaptation of the deep repository to the characteristics of the site with an acceptable impact on society and the environment. Permit comparisons with other investigated sites. Furthermore, the investigations are discontinued when the reliability of the site description has reached such a level that the body of data for safety assessment and design is sufficient, or until the body of data shows that the rock does not satisfy the requirements. These objectives are valid, but do not provide sufficient and concrete guidance. For this reason SKB has conducted this project which should acquire concrete guidance on how to judge when the surface based Site Investigation Phase does not need to continue. After a general assessment of the problem, the following specific objectives of the current work were identified: Demonstrate concretely how the assessed uncertainties in a Site Description based on a specific level of investigations, together with expected feedback from Safety Assessment and Engineering, can be used to decide whether the site investigations are sufficient - or need to continue. This demonstration will be based on a practical application of relevant aspects of decision analysis tools. Highlight and make concrete the type of feedback to be expected from Safety Assessment and Engineering and show how this feedback

  11. Salmon Site Remedial Investigation Report, Appendix B (Part 2)

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  12. Salmon Site Remedial Investigation Report, Appendix B (Part 1)

    International Nuclear Information System (INIS)

    1999-01-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

  13. Geological and geotechnical investigations for nuclear power plants sites

    International Nuclear Information System (INIS)

    Alves, P.R.R.

    1984-09-01

    This dissertation presents a general methodology for the tasks of geological and geotechnical investigations, to be performed in the proposed sites for construction of nuclear Power Plants. In this work, items dealing with the standards applied to licensing of Nuclear Power Plants, with the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. This dissertation also provides an aid to the writing of Technical Reports, which are part of the documentation an owner of a Nuclear Power Plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. Moreover, this work can contribute to the planning of field and laboratory studies, needed to determine the parameters of the area under investigation, for the siting of Nuclear Power Plants. (Author) [pt

  14. Geochemical investigation of UMTRAP designated site at Durango, Colorado

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.

    1983-09-01

    This report is the result of a geochemical investigation of the former uranium mill and tailings site at Durango, Colorado. This is one in a series of site specific geochemical investigations performed on the inactive uranium mill tailings included in the UMTRA Project. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results will be used to model contaminant migration and to develop criteria for long-term containment media such as a cover system which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. The solid samples are water extracted remove easily soluble salts and acids extracted to remove cabonates and hydroxides. The water extracts and solid samples were analyzed for the major and trace elements. A limited number of samples were analyzed for radiological components. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Three major conclusions are: (1) carbonate salts and low TDS characterize the tailings; (2) the adjacent area and raffinate ponds contain contaminants deposited by a single event of fluid permeation of the soils; and (3) the Animas River adjacent to the site has elevated gross alpha activity attributed to 226 Ra in the sediments derived from the tailings or milling activities

  15. 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

    SKB's goal is to commence surface based 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 for spent nuclear fuel. The purpose of the international workshop on site characterisation held at Aespoe April 2001 was to: present the SKB site investigation and evaluation programme to a group of international experts; discuss whether the available toolbox of investigation methods for surface based site investigations is appropriate and state-of-the-art in an international perspective; and by working group sessions discuss the level of ambition in the programme for site investigation for each discipline. This report summarises the conclusions of the workshop in general terms. Many of the detailed comments and ideas obtained at the workshop have already inspired and will also directly inspire the on-going planning work for site characterisation. The core activity at the workshop was the work performed by working groups. They addressed what should be considered for a site characterisation programme, based on the generic planning made so far by SKB. The working groups also outlined site specific characterisation programmes for the sites suggested by SKB. The tasks were strictly confined to technical and scientific modelling issues. The working group chairmen presented the working group results at the workshop and have also submitted short memos to SKB. The present document is a compilation of these memos. The SKB generic programme as presented in the existing top level documents, 'Requirements and Criteria and Overall Programme', received general endorsement and was appreciated for being comprehensive and systematic. For example, it contains comprehensive lists of parameters to be measured. However, there is need for prioritisation and sequencing. This is actually included in the current planning process at SKB where the generic programme later this year will be adapted to

  16. Integrated account of method, site selection and programme prior to the site investigation phase

    International Nuclear Information System (INIS)

    2000-12-01

    In order to dispose of the spent nuclear fuel in a safe manner, SKB plans to site a deep repository and an encapsulation plant with associated canister fabrication and transportation system. After an integrated evaluation of feasibility studies and other material, SKB will proceed with investigations of the rock and studies regarding establishment of the deep disposal system in the municipality of Oskarshamn or in Northern Uppland. The plans also include further study of the prospects for a deep repository in the municipality of Nykoeping. In the municipality of Oskarshamn, SKB plans further studies of a siting of the deep repository at Simpevarp. There SKB wants to initiate site investigations with test drilling. For the encapsulation plant, SKB wants to continue studying a siting at CLAB. In Northern Uppland, SKB plans to study two siting alternatives for the deep repository. One is Forsmark in the municipality of Oesthammar, where SKB wants to initiate a site investigation with test drilling. The other is Tierp north of Skutskaer, where SKB intends to start test drilling in an area north of Tierp. First, however, a suitable drilling area with possible transport solutions needs to be defined. This alternative requires the participation of the municipalities of both Tierp and Aelvkarleby. A siting of the encapsulation plant in Northern Uppland will also be studied. For the municipality of Nykoeping, SKB plans to conduct a new safety assessment for the Fjaellveden area, based on data from previous investigations as well as additional studies of how a deep repository could be arranged. SKB will thereby gather data from yet another geographic and geological region beyond those that are prioritized. No test drilling is planned in Nykoeping. The goal of the site investigation phase is to obtain all permits needed to build the planned facilities. It will take an estimated 7 - 8 years to assemble the requisite supporting material, carry out consultations, compile siting

  17. ACHP | News | ACHP Issues Program Comment to Streamline Communication

    Science.gov (United States)

    Program Comment to Streamline Communication Facilities Construction and Modification ACHP Issues Program Comment to Streamline Communication Facilities Construction and Modification The Advisory Council on

  18. Forsmark site investigation. Interpretation of topographic lineaments 2002

    International Nuclear Information System (INIS)

    Isaksson, Hans

    2003-04-01

    SKB performs site investigations for localization of a deep repository for high level radioactive waste. The site investigations are performed in two municipalities; Oesthammar and Oskarshamn. The Forsmark investigation area is situated in Oesthammar, close to the Forsmark nuclear power plant. The purpose of interpretation of lineaments from topographic data is to identify linear features (lineaments), which may correspond to deformation zones in the bedrock. The data will be combined with interpretations of lineaments from airborne geophysical data in order to produce an integrated lineament interpretation for the Forsmark area. This integrated interpretation will be combined with geological data in order to establish a bedrock geological map of the Forsmark area. The area for the lineament interpretation is the same as that selected for the bedrock mapping activities during 2002, i.e. the land area around Forsmark

  19. Ecological investigations at the Pantex Plant Site, 1992

    International Nuclear Information System (INIS)

    Cushing, C.E.; Mazaika, R.R.; Phillips, R.C.

    1993-09-01

    In 1992, Pantex requested that Pacific Northwest Laboratory (PNL) conduct a series of ecological surveys to provide baseline information for designing detailed ecological studies on the various ecosystems present at the Pantex plant site near Amarillo, Texas. To this end, PNL scientist and technicians visited the site at different times to conduct investigations and collect samples: July 6--13: birds, small mammals, general habitat assessment; August 10--14: wetland vegetation, birds, small mammals, Playa invertebrates; and September 7--11: birds, small mammals. This report presents the results of these three surveys

  20. Prioritization to limit sampling and drilling in site investigations

    International Nuclear Information System (INIS)

    Burton, J.C.

    1992-01-01

    One of the major goals of the Environmental Research Division of Argonne National Laboratory is to develop and provide governmental agencies with technically sound, cost-effective frameworks for environmental site characterization and remedial programs. An example of the development of such a framework for preremedial site characterization is presented in this paper. Specifically, this paper presents portions of an expanded site investigation program developed for landfills suspected of containing hazardous waste. The work was sponsored by the New Mexico State Office of the US Department of Interior's Bureau of Land Management (BLM). The emphasis of the BLM program was on identifying initial characterization procedures that would decrease the need for sampling and drilling on a random grid

  1. Accelerated Logistics: Streamlining the Army's Supply Chain

    National Research Council Canada - National Science Library

    Wang, Mark

    2000-01-01

    ...) initiative, the Army has dramatically streamlined its supply chain, cutting order and ship times for repair parts by nearly two-thirds nationwide and over 75 percent at several of the major Forces Command (FORSCOM) installations...

  2. Corrective Action Investigation Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Grant Evenson

    2006-01-01

    Corrective Action Unit (CAU) 139 is located in Areas 3, 4, 6, and 9 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 139 is comprised of the seven corrective action sites (CASs) listed below: (1) 03-35-01, Burn Pit; (2) 04-08-02, Waste Disposal Site; (3) 04-99-01, Contaminated Surface Debris; (4) 06-19-02, Waste Disposal Site/Burn Pit; (5) 06-19-03, Waste Disposal Trenches; (6) 09-23-01, Area 9 Gravel Gertie; and (7) 09-34-01, Underground Detection Station. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives with the exception of CASs 09-23-01 and 09-34-01. Regarding these two CASs, CAS 09-23-01 is a gravel gertie where a zero-yield test was conducted with all contamination confined to below ground within the area of the structure, and CAS 09-34-01 is an underground detection station where no contaminants are present. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for the other five CASs where information is insufficient. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 4, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 139

  3. Creating customer value by streamlining business processes.

    Science.gov (United States)

    Vantrappen, H

    1992-02-01

    Much of the strategic preoccupation of senior managers in the 1990s is focusing on the creation of customer value. Companies are seeking competitive advantage by streamlining the three processes through which they interact with their customers: product creation, order handling and service assurance. 'Micro-strategy' is a term which has been coined for the trade-offs and decisions on where and how to streamline these three processes. The article discusses micro-strategies applied by successful companies.

  4. Investigation of tritium in groundwater at Site 300

    International Nuclear Information System (INIS)

    Buddemeier, R.W.

    1985-01-01

    In 1984, landfill monitoring wells at Site 300, a Lawrence Livermore National Laboratory (LLNL) explosive test site, revealed the presence of groundwater contaminated with tritium. These tritium levels were in excess of the State of California drinking water standard. A major investigation was initiated that included a search of records concerning tritium use, disposal, and previous analyses, and a survey of tritium levels in soil, vegetation, and water in contaminated and potentially contaminated areas. Over 50 boreholes were drilled for this investigation to characterize the local hydrogeology and tritium distributions, and a network of soil moisture and groundwater monitoring points was installed. This report presents the work completed through the end of September 1985: the records search; records for drilling completed as part of this study; characterization of the geology, hydrology, and tritium distributions in the contaminated area; and an initial assessment of the probable tritium sources, pathways, and migration rates. 19 refs

  5. Investigation of tritium in groundwater at Site 300

    Energy Technology Data Exchange (ETDEWEB)

    Buddemeier, R.W.

    1985-12-30

    In 1984, landfill monitoring wells at Site 300, a Lawrence Livermore National Laboratory (LLNL) explosive test site, revealed the presence of groundwater contaminated with tritium. These tritium levels were in excess of the State of California drinking water standard. A major investigation was initiated that included a search of records concerning tritium use, disposal, and previous analyses, and a survey of tritium levels in soil, vegetation, and water in contaminated and potentially contaminated areas. Over 50 boreholes were drilled for this investigation to characterize the local hydrogeology and tritium distributions, and a network of soil moisture and groundwater monitoring points was installed. This report presents the work completed through the end of September 1985: the records search; records for drilling completed as part of this study; characterization of the geology, hydrology, and tritium distributions in the contaminated area; and an initial assessment of the probable tritium sources, pathways, and migration rates. 19 refs.

  6. Site descriptive modeling as a part of site characterization in Sweden - Concluding the surface based investigations

    International Nuclear Information System (INIS)

    Andersson, Johan; Winberg, Anders; Skagius, Kristina; Stroem, Anders; Lindborg, Tobias

    2007-01-01

    The Swedish Nuclear Fuel and Waste Management Co., SKB, is currently finalizing its surface based site investigations for the final repository for spent nuclear fuel in the municipalities of Oestharmnar (the Forsmark area) and Oskarshamn (the Simpevar/Laxemar area). The investigation data are assessed into a Site Descriptive Model, constituting a synthesis of geology, rock mechanics, thermal properties, hydrogeology, hydro-geochemistry, transport properties and a surface system description. Site data constitute a wide range of different measurement results. These data both need to be checked for consistency and to be interpreted into a format more amenable for three-dimensional modeling. The three-dimensional modeling (i.e. estimating the distribution of parameter values in space) is made in a sequence where the geometrical framework is taken from the geological models and in turn used by the rock mechanics, thermal and hydrogeological modeling. These disciplines in turn are partly interrelated, and also provide feedback to the geological modeling, especially if the geological description appears unreasonable when assessed together with the other data. Procedures for assessing the uncertainties and the confidence in the modeling have been developed during the course of the site modeling. These assessments also provide key input to the completion of the site investigation program. (authors)

  7. Modelling of water-rock interaction at TVO investigation sites

    International Nuclear Information System (INIS)

    Pitkaenen, P.; Leino-Forsman, H.

    1992-12-01

    The geochemistry of the groundwater at the Kivetty, Syyry and Olkiluoto site investigation areas in Finland for nuclear waste disposal is evaluated. The hydrogeological data is collected from boreholes drilled down to 100-m depth into crystalline bedrock. The interpretation is based on groundwater chemistry and isotope data, mineralogical data, and the structure and hydrology of the bedrock, using correlation diagrams and the thermodynamic calculations (PHREEQE,EQ3NR). The hydrogeochemistry and major processes controlling the groundwater chemistry are discussed

  8. Forsmark site investigation. Programme for further investigations of geosphere and biosphere

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-01

    Since the beginning of 2002, SKB (the Swedish Nuclear Fuel and Waste Management Co) has been conducting a site investigation in Forsmark in the municipality of Oesthammar for siting of the deep repository for spent nuclear fuel. An equivalent investigation is also being conducted at Simpevarp and Laxemar in Oskarshamn Municipality. SKB's goal is to submit an application under the Environmental Code and the Nuclear Activities Act for siting of the deep repository at one of these sites by the end of 2008/beginning of 2009. When the application is submitted, everything of importance for the deep repository's safety, constructability and environmental impact shall have been investigated and analyzed. The investigations shall also provide data as a basis for selecting a site and configuring the facility to suit conditions on the site.SKB submitted a programme for the initial site investigation in Forsmark at the end of 2001. The investigations described there have now been completed. This report describes the programme that has now been prepared for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, the data needed for evaluation of the site, plus experience and results from the work to date. The programme has been prepared with the support of investigation data as of August 2004. The investigations described here will, as before, be conducted with great consideration given to residents, property owners and natural and cultural values so that they are not unnecessarily exposed to impact or disturbances. Just as before, the programme will be continuously adapted to the knowledge that is gradually accumulated on the site. All important changes will be reported to the authorities and other concerned parties. The investigations that have been conducted (as of August 2004) and their results can be summarized in the following points: The surface characterization

  9. Forsmark site investigation. Programme for further investigations of geosphere and biosphere

    International Nuclear Information System (INIS)

    2005-01-01

    Since the beginning of 2002, SKB (the Swedish Nuclear Fuel and Waste Management Co) has been conducting a site investigation in Forsmark in the municipality of Oesthammar for siting of the deep repository for spent nuclear fuel. An equivalent investigation is also being conducted at Simpevarp and Laxemar in Oskarshamn Municipality. SKB's goal is to submit an application under the Environmental Code and the Nuclear Activities Act for siting of the deep repository at one of these sites by the end of 2008/beginning of 2009. When the application is submitted, everything of importance for the deep repository's safety, constructability and environmental impact shall have been investigated and analyzed. The investigations shall also provide data as a basis for selecting a site and configuring the facility to suit conditions on the site.SKB submitted a programme for the initial site investigation in Forsmark at the end of 2001. The investigations described there have now been completed. This report describes the programme that has now been prepared for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, the data needed for evaluation of the site, plus experience and results from the work to date. The programme has been prepared with the support of investigation data as of August 2004. The investigations described here will, as before, be conducted with great consideration given to residents, property owners and natural and cultural values so that they are not unnecessarily exposed to impact or disturbances. Just as before, the programme will be continuously adapted to the knowledge that is gradually accumulated on the site. All important changes will be reported to the authorities and other concerned parties. The investigations that have been conducted (as of August 2004) and their results can be summarized in the following points: The surface characterization of the

  10. MX Siting Investigation. MX System Siting Summary Report. General Introduction. Volume I. Part I.

    Science.gov (United States)

    1982-01-18

    LINEAR CONNECT CRN MIX SITING INVESTIGATION DEPARTMENT OF THE AIR FORCE VOUTS USING VALLEY CLUSTERING CONCEPT IN IOC, BMO/AFRCE- wIX VOUTS IN DRY LAKE...species, such as the jackrabbit, may be the center of important food webs , and a decrease in its numbers may greatly affect many other species. The

  11. Site characterization and validation - Borehole radar investigations stage 3

    International Nuclear Information System (INIS)

    Sandberg, E.; Olsson, O.; Falk, L.

    1989-11-01

    The borehole radar investigation program Stage 3 of the SCV-site has comprised single hole reflection measurements with centre frequencies of 22 and 60 MHz. Single hole reflection measurement with both omni-directional and directional antennas have been performed in the boreholes C1, C2, C3 and the D-holes. Crosshole tomographic measurements as well as cross- hole reflection measurement have been made between the bore- holes C1-C2, W1-C1 and W1-C2. The range obtained in the single hole reflection measurements was approximately 100 m for the lower frequency and about 60-70 m for the centre frequency 60 MHz. In the crosshole measurements transmitter-receiver separations from 20 to 120 m have been used. The Stage 3 radar investigations have essentially confirmed the three dimensional description of the structures at the SCV-site. The conceptual model of the site which was produced based on the Stage 1 data included three major zones, two minor zones and a circular feature. The major features are considered to be the most significant at the site and are all observed in the Stage 3 boreholes close to their predicted locations. The circular feature has also been found in two of the additional tomograms at the predicted location. The results indicate that the zones are not homogeneous but rather that they are highly irregular containing parts of considerably increased fracturing and parts where their contrast to the background rock is quite small. The zones appear to be approximately planar at least at the scale of the site. At a smaller scale the zones can appear quite irregular

  12. Geochemical investigation of UMTRAP designated site at Grand Junction, Colorado

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.

    1983-09-01

    This report is the result of a geochemical investigation of the former uranium mill and tailings site at Grand Junction, Colorado. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results should be used to model contaminant migration and to develop criteria for long-term containment media, such as a cover system which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a sampling of waters in two seasons and solid material from the background, the area adjacent to the site, and the site. The solid samples were water extracted to remove easily soluble salts and acid extracted to remove carbonates and hydroxides. The water extracts and solid samples were analyzed for the major and trace elements. A limited number of samples were analyzed for radiological components. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Four major conclusions are: (1) trace element concentrations in shallow subsurface waters adjacent to the tailings temporally vary up to an order of magnitude; (2) the riverbank soils and borehole waters are contaminated with uranium, radium, and trace elements from discharge of tailings solids and solutions during the active time of the mill; however, the movement of contaminants toward the Colorado River does not appear to be significant; (3) the Colorado River adjacent to the tailings is not contaminated; and (4) trace metals have accumulated at both the tailings/cover and tailings/soil interface because of precipitation reactions caused by chemical differences between the two materials

  13. Good clinical practice regulatory inspections: Lessons for Indian investigator sites

    Directory of Open Access Journals (Sweden)

    R Marwah

    2010-01-01

    Full Text Available Regulatory inspections are important to evaluate the integrity of the data submitted to health authorities (HAs, protect patient safety, and assess adequacy of site/sponsor quality systems to achieve the same. Inspections generally occur after submission of data for marketing approval of an investigational drug. In recent years, there has been a significant increase in number of inspections by different HAs, including in India. The assessors/inspectors generally do a thorough review of site data before inspections. All aspects of ICH-GCP, site infrastructure, and quality control systems are assessed during the inspection. Findings are discussed during the close out meeting and a detailed inspection report issued afterward, which has to be responded to within 15-30 days with effective Corrective and Preventive Action Plan (CAPA. Protocol noncompliance, inadequate/inaccurate records, inadequate drug accountability, informed consent issues, and adverse event reporting were some of the most common findings observed during recent Food and Drug Administration (FDA inspections. Drug development is being increasingly globalized and an increased number of patients enrolled in studies submitted as part of applications come from all over the world including India. Because of the steep increase in research activity in the country, inexperienced sites, and more stakeholders, increased efforts will be required to ensure continuous quality and compliance. HAs have also made clear that enforcement will be increased and be swift, aggressive, and effective.

  14. Site Safety Plan for Lawrence Livermore National Laboratory CERCLA investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bainer, R.; Duarte, J.

    1993-07-01

    The safety policy of LLNL is to take every reasonable precaution in the performance of work to protect the environment and the health and safety of employees and the public, and to prevent property damage. With respect to hazardous agents, this protection is provided by limiting human exposures, releases to the environment, and contamination of property to levels that are as low as reasonably achievable (ALARA). It is the intent of this Plan to supply the broad outline for completing environmental investigations within ALARA guidelines. It may not be possible to determine actual working conditions in advance of the work; therefore, planning must allow the opportunity to provide a range of protection based upon actual working conditions. Requirements will be the least restrictive possible for a given set of circumstances, such that work can be completed in an efficient and timely fashion. Due to the relatively large size of the LLNL Site and the different types of activities underway, site-specific Operational Safety Procedures (OSPs) will be prepared to supplement activities not covered by this Plan. These site-specific OSPs provide the detailed information for each specific activity and act as an addendum to this Plan, which provides the general plan for LLNL Main Site operation.

  15. Site characterization and validation - hydrochemical investigations. Stage 3

    International Nuclear Information System (INIS)

    Laaksoharju, M.

    1990-02-01

    The objective for the Stage 3 hydrochemical investigations was to classify groundwater and to determine the different flow paths within the investigated SCV-site by using water analyses from the C and D boreholes. The water was divided into three classes shallow (A), mixed (B) and deep groundwater (C) based on Cl and HCO 3 concentration. The local geohydrological situation in the SCV-site can be divided into a disturbed situation and an undisturbed situation. Opening of the boreholes and smapling causes a disturbance of hydrochemical conditions. Three water types were found in the important water conductors, the GB and the GH zones. Shallow water (A-type) is flowing downwards while deep groundwater (C-type) is flowing upwards driven by the pumping of the mine. Where the two water types meet a zone of approximately 30 m thickness with mixed (B-type) water is formed. The flow situation is revealed by the geohydrological measurements. At undisturbed conditions shallow water (A-type) is flowing down in the investigated zones. The B and C water types are then found at a deeper level than during disturbed conditions. A regional model can be constructed based on the described chemical and geohydrological investigations. Shallow water from the top and deep groundwater from below are drawn towards the mine by the pumping. Where these waters meet mixed water is formed. (orig./HP)

  16. Site safety plan for Lawrence Livermore National Laboratory CERCLA investigations at site 300. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Kilmer, J.

    1997-08-01

    Various Department of Energy Orders incorporate by reference, health and safety regulations promulgated by the Occupational Safety and Health Administration (OSHA). One of the OSHA regulations, 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response, requires that site safety plans are written for activities such as those covered by work plans for Site 300 environmental investigations. Based upon available data, this Site Safety Plan (Plan) for environmental restoration has been prepared specifically for the Lawrence Livermore National Laboratory Site 300, located approximately 15 miles east of Livermore, California. As additional facts, monitoring data, or analytical data on hazards are provided, this Plan may need to be modified. It is the responsibility of the Environmental Restoration Program and Division (ERD) Site Safety Officer (SSO), with the assistance of Hazards Control, to evaluate data which may impact health and safety during these activities and to modify the Plan as appropriate. This Plan is not `cast-in-concrete.` The SSO shall have the authority, with the concurrence of Hazards Control, to institute any change to maintain health and safety protection for workers at Site 300.

  17. Site Investigation for Detection of KIJANG Reactor Core Center

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Tae-Hyun; Kim, Jun Yeon; Kim, Jeeyoung [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    It was planned for the end of March 2017 and extended to April 2018 according to the government budget adjustment. The KJRR project is intended for filling the self-sufficiency of RI demand including Mo-99, increasing the NTD capacity and developing technologies related to the research reactor. In project, site investigation is the first activity that defines seismologic and related geologic aspects of the site. Site investigation was carried out from Oct. 2012 to Jan. 2014 and this study is intended to describe detail procedures in locating the reactor core center. The location of the reactor core center was determined by collectively reviewing not only geological information but also information from architects engineering. EL 50m was selected as ground level by levering construction cost. Four recommended locations (R-1a - R-1d) are displayed for the reactor core center. R-1a was found optimal in consideration of medium rock contour, portion of medium rock covering reactor buildings, construction cost, physical protection and electrical resistivity. It is noted that engineering properties of the medium rock is TCR/RQD 100/53, elastic modulus 7,710 - 8,720MPa, permeability coefficient 2.92E-06cm/s, and S-wave velocity 1,380m/s, sound for foundations of reactor buildings.

  18. Seismic and geologic investigations of the Sandia Livermore Laboratory site

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    This report describes results of a seismic and geologic investigation in the vicinity of Sandia Laboratories property and Sandia's Tritium Building at Livermore, California. The investigation was done to define any seismically capable faults in the immediate area and to obtain necessary information to support estimates of future possible or probable ground motions. The work included a variety of geophysical measurements, trenching, seismologic studies, geologic examination, and evaluation of possible ground surface rupture at the site. Ground motions due to the maximum potential earthquake are estimated, and probability of exceedance for various levels of peak ground acceleration is calculated. Descriptions of the various calculations and investigative techniques used and the data obtained are presented. Information obtained from other sources relevant to subsurface geology and faulting is also given. Correlation and evaluation of the various lines of evidence and conclusions regarding the seismic hazard to the Tritium Building are included

  19. The value of DCIP geophysical surveys for contaminated site investigations

    DEFF Research Database (Denmark)

    Balbarini, Nicola; Rønde, Vinni Kampman; Maurya, Pradip Kumar

    an old factory site by combining traditional geological, hydrological, and contaminant concentration data with DCIP surveys. The plume consisted of xenobiotic organic compounds and inorganics. The study assesses benefits and limitations of DCIP geophysics for contaminated site investigations. A 3D......Geophysical methods are increasingly being used in contaminant hydrogeology to map lithology, hydraulic properties, and contaminant plumes with a high ionic strength. Advances in the Direct Current resistivity and Induced Polarization (DCIP) method allow the collection of high resolution three...... water and below the streambed. Surface DCIP surveys supported the characterization of the spatial variability in geology, hydraulic conductivity and contaminant concentration. Though DCIP data interpretation required additional borehole data, the DCIP survey reduced the number of boreholes required...

  20. Oskarshamn site investigation. Monitoring of shallow groundwater chemistry 2009

    Energy Technology Data Exchange (ETDEWEB)

    Ericsson, Ulf (Medins Biologi AB, Moelnlycke (Sweden))

    2010-06-15

    In 2009 sampling of shallow ground water in water wells in soil has been performed in a regular programme at eight sites within the site investigation area at Oskarshamn. The purpose of the activity is to monitor (long term observation) and characterise the shallow ground water in the site investigation area. Some physical and chemical parameters were measured directly in the field but most parameters were analysed at different laboratories. The ground water sampling activity consisted of one programme, chemical programme class 5 (reduced). The large number of sites and parameters analysed have generated a large amount of data, which will later be used for advanced analysis and modelling. In this report the evaluation aims to give a simple overview of the results and to describe the quality of the data sampled 2009. As an addition radon activity was measured at fourteen sites in the area. Seven of these sites were the same as in the regular programme. The results showed a large variation between the wells. The concentrations of major ions and conductivity ranged from low to high or very high values. The concentration of HCO{sub 3} also varied extensively throughout the investigation area, but since the concentrations were above 60 mg/l in most wells the results indicate a good ground water quality with respect to acidification. The concentration of heavy metals and trace elements also varied. High concentration of Pb in some of the wells indicated pollution. Since Pb had a similar relation to Al as most other elements it was argued that high concentrations of lead probably can be explained by the natural composition of minerals within the site investigation area. The ratio of delta18O showed a good relationship with the conductivity. The activity of tritium (3H) was markedly lower in two of the wells. This might be an indication of older groundwater in these wells. The average hydrogen isotope ratio of deuterium (delta2H) varied with similar values in most wells

  1. Oskarshamn site investigation. Monitoring of shallow groundwater chemistry 2009

    International Nuclear Information System (INIS)

    Ericsson, Ulf

    2010-06-01

    In 2009 sampling of shallow ground water in water wells in soil has been performed in a regular programme at eight sites within the site investigation area at Oskarshamn. The purpose of the activity is to monitor (long term observation) and characterise the shallow ground water in the site investigation area. Some physical and chemical parameters were measured directly in the field but most parameters were analysed at different laboratories. The ground water sampling activity consisted of one programme, chemical programme class 5 (reduced). The large number of sites and parameters analysed have generated a large amount of data, which will later be used for advanced analysis and modelling. In this report the evaluation aims to give a simple overview of the results and to describe the quality of the data sampled 2009. As an addition radon activity was measured at fourteen sites in the area. Seven of these sites were the same as in the regular programme. The results showed a large variation between the wells. The concentrations of major ions and conductivity ranged from low to high or very high values. The concentration of HCO 3 also varied extensively throughout the investigation area, but since the concentrations were above 60 mg/l in most wells the results indicate a good ground water quality with respect to acidification. The concentration of heavy metals and trace elements also varied. High concentration of Pb in some of the wells indicated pollution. Since Pb had a similar relation to Al as most other elements it was argued that high concentrations of lead probably can be explained by the natural composition of minerals within the site investigation area. The ratio of δ 18 O showed a good relationship with the conductivity. The activity of tritium ( 3 H) was markedly lower in two of the wells. This might be an indication of older groundwater in these wells. The average hydrogen isotope ratio of deuterium (δ 2 H) varied with similar values in most wells. The

  2. Geochemical investigations at Maxey Flats radioactive waste disposal site

    International Nuclear Information System (INIS)

    Dayal, R.; Pietrzak, R.F.; Clinton, J.

    1984-09-01

    As part of the NRC efforts to develop a data base on source term characteristics for low level wastes, Brookhaven National Laboratory (BNL) has produced and analyzed a large amount of data on trench leachate chemistry at existing shallow land burial sites. In this report, we present the results of our investigations at the Maxey Flats, Kentucky disposal site. In particular, data on trench leachate chemistry are reviewed and discussed in terms of mechanisms and processes controlling the composition of trench solutes. Particular emphasis is placed on identifying both intra- and extra-trench factors and processes contributing to source term characteristics, modifications, and uncertainties. BNL research on the Maxey Flats disposal site has provided important information not only on the source term characteristics and the factors contributing to uncertainties in the source term but also some generic insights into such geochemical processes and controls as the mechanics of leachate formation, microbial degradation and development of anoxia, organic complexation and radionuclide mobility, redox inversion and modification of the source term, solubility constraints on solute chemistry, mineral authigenesis, corrosion products and radionuclide scavenging, and the role of organic complexants in geochemical partitioning of radionuclides. A knowledge of such processes and controls affecting the geochemical cycling of radionuclides as well as an understanding of the important factors that contribute to variability and uncertainties in the source term is essential for evaluating the performance of waste package and the site, making valid predictions of release for dose calculations, and for planning site performance monitoring as well as remedial actions. 43 references, 47 figures, 30 tables

  3. Contaminated site investigation using nuclear technique: a case study of temporary transformer storage sites in Ghana

    International Nuclear Information System (INIS)

    Sanu, J. K.

    2013-07-01

    Recent introduction of man-made toxic chemicals, and the massive relocation of natural materials to different environmental compartment like soil, ground water and atmosphere, has resulted in severe pressure on the self- cleansing capacity of recipient ecosystems. Various accomulated pollutants and contaminants such as polychlorinated biphenyls (PCBs) are of much concern relative to both human and ecosystemm exposure and potential health impact. PCBs which are resistant to degradation and bioremediation accumulated in different niches of the biosphere. This significantly affects the ecological balances and cause adverse health effect on both human and the environment. Temporal transformer storage sites at four locations in Ghana (Tema, Temale, Bolgatanga and Wa) were investigated for PCB contamination using nuclear techniques. Analysis of soil samples from four temporal transformer storage sites revealed that the soil samples from Tema, Tamale, Bolgatanga and Wa were generally sandy with pH and EC ranging between 6.24 - 7.29 and 44.60 - 188.30 respectively. The PCB levels detected in the soil samples from the various locations varied considerably with mean ranging between 7.69 and 51.92 mg/kg. The highest mean PCB level was recorded at the Tema temporal transformer storage site (51.92 mg/kg), whilst the least mean level of 7.69 mg/kg was recorded at Wa storage site. At Tamale the individual levels range between 3.57 mg/kg and 38.70 mg/kg while at Bolgatanga it was 6.85 - 16.30 mg/kg and Wa, 6.08 - 14.70mg/kg. About 9% of soil samples from temporal transformer storage sites analysed had total PCBs concentrations above the 25mg/kg and 33 mg/kg level recommended by the Canadian Council of Ministers of environment (CCME) and EPA Ghana respectively for the protection of environment and human health. Generally, the Levels of PCBs in soil samples were found to decrease with increasing depth at all the temporal transformer storage sites. Results obtained using the EPA's L

  4. Techniques for site investigations for underground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    1985-01-01

    The report provides a more detailed description of the capabilities and applications of the various earth science investigation techniques outlined in the IAEA Technical Reports Series Nos. 177, 215 and 216. These methods are generally appropriate during at least one of the stages of the assessment or selection of a site for any type of waste disposal facility, in shallow ground or in deep geological formations. This report is addressed to technical authorities responsible for or involved in planning, approving, executing and reviewing national waste disposal programmes. It may also help administrative authorities in this field to select appropriate techniques for obtaining the majority of the required information at minimum cost

  5. Geological Site Descriptive Model. A strategy for the model development during site investigations

    International Nuclear Information System (INIS)

    Munier, Raymond; Stenberg, Leif; Stanfors, Roy; Milnes, Allan Geoffrey; Hermanson, Jan; Triumf, Carl-Axel

    2003-04-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is at present conducting site investigations as a preliminary to building an underground nuclear waste disposal facility in Sweden. This report presents a methodology for constructing, visualising and presenting 3-dimensional geological models, based on data from the site investigations. The methodology integrates with the overall work-flow of the site investigations, from the collection of raw data to the complete site description, as proposed in several earlier technical reports. Further, it is specifically designed for interaction with SICADA - SKB's Site Characterisation Database - and RVS - SKB's Rock Visualisation System. This report is one in a series of strategy documents intended to demonstrate how modelling is to be performed within each discipline. However, it also has a wider purpose, since the geological site descriptive model provides the basic geometrical framework for all the other disciplines. Hence, the wider aim is to present a practical and clear methodology for the analysis and interpretation of input data for use in the construction of the geology-based 3D geometrical model. In addition to the various aspects of modelling described above, the methodology presented here should therefore also provide: guidelines and directives on how systematic interpretation and integration of geo-scientific data from the different investigation methods should be carried out; guidelines on how different geometries should be created in the geological models; guidelines on how the assignment of parameters to the different geological units in RVS should be accomplished; guidelines on the handling of uncertainty at different points in the interpretation process. In addition, it should clarify the relation between the geological model and other models used in the processes of site characterisation, repository layout and safety analysis. In particular, integration and transparency should be promoted. The

  6. Geological Site Descriptive Model. A strategy for the model development during site investigations

    Energy Technology Data Exchange (ETDEWEB)

    Munier, Raymond; Stenberg, Leif [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Stanfors, Roy [Roy Stanfors Consulting, Lund (Sweden); Milnes, Allan Geoffrey [GEA Consulting, Uppsala (Sweden); Hermanson, Jan [Golder Associates, Stockholm (Sweden); Triumf, Carl-Axel [Geovista, Luleaa (Sweden)

    2003-04-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is at present conducting site investigations as a preliminary to building an underground nuclear waste disposal facility in Sweden. This report presents a methodology for constructing, visualising and presenting 3-dimensional geological models, based on data from the site investigations. The methodology integrates with the overall work-flow of the site investigations, from the collection of raw data to the complete site description, as proposed in several earlier technical reports. Further, it is specifically designed for interaction with SICADA - SKB's Site Characterisation Database - and RVS - SKB's Rock Visualisation System. This report is one in a series of strategy documents intended to demonstrate how modelling is to be performed within each discipline. However, it also has a wider purpose, since the geological site descriptive model provides the basic geometrical framework for all the other disciplines. Hence, the wider aim is to present a practical and clear methodology for the analysis and interpretation of input data for use in the construction of the geology-based 3D geometrical model. In addition to the various aspects of modelling described above, the methodology presented here should therefore also provide: guidelines and directives on how systematic interpretation and integration of geo-scientific data from the different investigation methods should be carried out; guidelines on how different geometries should be created in the geological models; guidelines on how the assignment of parameters to the different geological units in RVS should be accomplished; guidelines on the handling of uncertainty at different points in the interpretation process. In addition, it should clarify the relation between the geological model and other models used in the processes of site characterisation, repository layout and safety analysis. In particular, integration and transparency should be

  7. Review of data types for the SKB site investigation programme

    Energy Technology Data Exchange (ETDEWEB)

    Klos, Richard

    2002-11-01

    SKB is currently undertaking a detailed site investigation programme (SIP) to characterise the geology and surface ecosystems in areas around potential sites for a planned repository for spent nuclear fuel. This report reviews site specific and generic data types needed to characterise biosphere processes relevant to the evaluation of long-term radiological safety in the context of assessments of future impacts arising from the deep geologic disposal of spent nuclear fuel. Focus is on the types of data that make up the different elements of radiological assessment models and how the data used relate to site-specific characteristics. The relevance of the SIP to the development of assessment models for long-term assessment is addressed, including the representation of the geosphere-biosphere interface. Reference to SKB's programme is made in order to determine how well the current programme will meet the needs of assessment models that will be developed and used in the assessment of long-term safety. The review also provides SSI with a basis for the planning of further SSI R and D work. The process, by which site-specific information is converted into a form suitable for use in numerical assessment models, can be quite complex. An overview of assessment model concepts is provided and the links between these and real-word site information considered. Focusing on the needs of assessment models, the review provides a summary of the main types of analyses and site-specific models that are needed for safety evaluations. Review of the SIP indicates that information from the programme feeds into a set of detailed site description models. However there is a gap between the descriptive components and the detailed model descriptions needed to configure numerical assessment models. Details of system evolution are not clearly dealt with in the programme. The SIP focuses on a detailed description of the site the present day. However, radiological impacts are not expected to

  8. Review of data types for the SKB site investigation programme

    International Nuclear Information System (INIS)

    Klos, Richard

    2002-11-01

    SKB is currently undertaking a detailed site investigation programme (SIP) to characterise the geology and surface ecosystems in areas around potential sites for a planned repository for spent nuclear fuel. This report reviews site specific and generic data types needed to characterise biosphere processes relevant to the evaluation of long-term radiological safety in the context of assessments of future impacts arising from the deep geologic disposal of spent nuclear fuel. Focus is on the types of data that make up the different elements of radiological assessment models and how the data used relate to site-specific characteristics. The relevance of the SIP to the development of assessment models for long-term assessment is addressed, including the representation of the geosphere-biosphere interface. Reference to SKB's programme is made in order to determine how well the current programme will meet the needs of assessment models that will be developed and used in the assessment of long-term safety. The review also provides SSI with a basis for the planning of further SSI R and D work. The process, by which site-specific information is converted into a form suitable for use in numerical assessment models, can be quite complex. An overview of assessment model concepts is provided and the links between these and real-word site information considered. Focusing on the needs of assessment models, the review provides a summary of the main types of analyses and site-specific models that are needed for safety evaluations. Review of the SIP indicates that information from the programme feeds into a set of detailed site description models. However there is a gap between the descriptive components and the detailed model descriptions needed to configure numerical assessment models. Details of system evolution are not clearly dealt with in the programme. The SIP focuses on a detailed description of the site the present day. However, radiological impacts are not expected to reach

  9. Phase I Source Investigation, Heckathorn Superfund Site, Richmond, California

    Energy Technology Data Exchange (ETDEWEB)

    Kohn, Nancy P; Evans, Nathan R

    2002-12-18

    This report represents Phase I of a multi-phase approach to a source investigation of DDT at the Heckathorn Superfund Site, Richmond, California, the former site of a pesticide packaging plant, and the adjacent waterway, the Lauritzen Channel. Potential identified sources of contamination were from sloughed material from undredged areas (such as side banks) and from outfall pipes. Objectives of Phase I included the (1) evaluation of pesticide concentrations associated with discharge from outfalls, (2) identification of additional outfalls in the area, (3) identification of type, quantity, and distribution of sediment under the Levin pier, (4) quantification of pesticide concentrations in sediment under the pier, and (5) evaluation of sediment structure and slope stability under the pier. Field operations included the collection of sediment directly from inside the mouths of outfall pipes, when possible, or the deployment of specially designed particle traps where direct sampling was problematic. Passive water samplers were placed at the end of known outfall pipes and analyzed for DDT and other pesticides of concern. Underwater dive surveys were conducted beneath the Levin pier to document type, slope, and thickness of sediment. Samples were collected at locations of interest and analyzed for contaminants. Also sampled was soil from bank areas, which were suspected of potentially contributing to continued DDT contamination of the Lauritzen Channel through erosion and groundwater leaching. The Phase I Source Investigation was successful in identifying significant sources of DDT contamination to Lauritzen Channel sediment. Undredged sediment beneath the Levin pier that has been redistributed to the channel is a likely source. Two outfalls tested bear further investigation. Not as well-defined are the contributions of bank erosional material and groundwater leaching. Subsequent investigations will be based on the results of this first phase.

  10. Site characterization investigations at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Ketelle, R.H.

    1985-01-01

    The geologic and geohydrologic characterization and assessment techniques currently used at ORNL are integrated into a systematic approach. The investigations are multi-faceted, and involve investigators with a variety of expertise. Characterization studies are designed to obtain the data requirements of pathways analysis and facility design in addition to the detailed site description. The approach effectively minimizes the redundancy and lack of coordination which often arise when the study is broken down into totally independent tasks. The geologic environment of the Oak Ridge Reservation is one of structural and stratigraphic complexity which requires a comprehensive and systematic approach to characterize. Recent characterization studies have included state-of-the-science techniques in the areas of unsaturated zone testing, geochemical tests to determine attenuation properties of soils, and numerical analyses of site performance. The results of these studies and analyses are changing the technology of shallow land burial by indicating that chemically stable waste forms are required to limit radionuclide migration to acceptable levels. 11 refs., 1 tab

  11. A Hypothesis-Driven Approach to Site Investigation

    Science.gov (United States)

    Nowak, W.

    2008-12-01

    Variability of subsurface formations and the scarcity of data lead to the notion of aquifer parameters as geostatistical random variables. Given an information need and limited resources for field campaigns, site investigation is often put into the context of optimal design. In optimal design, the types, numbers and positions of samples are optimized under case-specific objectives to meet the information needs. Past studies feature optimal data worth (balancing maximum financial profit in an engineering task versus the cost of additional sampling), or aim at a minimum prediction uncertainty of stochastic models for a prescribed investigation budget. Recent studies also account for other sources of uncertainty outside the hydrogeological range, such as uncertain toxicity, ingestion and behavioral parameters of the affected population when predicting the human health risk from groundwater contaminations. The current study looks at optimal site investigation from a new angle. Answering a yes/no question under uncertainty directly requires recasting the original question as a hypothesis test. Otherwise, false confidence in the resulting answer would be pretended. A straightforward example is whether a recent contaminant spill will cause contaminant concentrations in excess of a legal limit at a nearby drinking water well. This question can only be answered down to a specified chance of error, i.e., based on the significance level used in hypothesis tests. Optimal design is placed into the hypothesis-driven context by using the chance of providing a false yes/no answer as new criterion to be minimized. Different configurations apply for one-sided and two-sided hypothesis tests. If a false answer entails financial liability, the hypothesis-driven context can be re-cast in the context of data worth. The remaining difference is that failure is a hard constraint in the data worth context versus a monetary punishment term in the hypothesis-driven context. The basic principle

  12. Hydrogeochemical investigation of six geothermal sites in Honduras, Central America

    Energy Technology Data Exchange (ETDEWEB)

    Goff, F.E.; Truesdell, A.H.; Grigsby, C.O.; Janik, C.J.; Shevenell, L.A.; Paredes, J.R.; Gutierrez, J.W.; Trujillo, Jr.; Counce, D.A.

    1987-06-01

    We conducted detailed hydrogeochemical investigations at six geothermal sites in western Honduras: Azacualpa, El Olivar, Pavana, Platanares, Sambo Creek, and San Ignacio. None of the sites is associated with Quaternary silicic volcanism, although El Olivar lies adjacent to a small Quaternary basalt field and Pavana is part of a belt of hot spring activity parallel to and 35 km east of the Central American volcanic arc. None of the sites contains acid-sulfate waters indicative of vapor-dominated conditions. Thermal fluids are characterized by pH between 7 and 10, Cl<125 mg/l, HCO/sub 3/>Cl, SO/sub 4/greater than or equal toCl, Bless than or equal to17 mg/l, Liless than or equal to4 mg/l, and Asless than or equal to1.25 mg/l. Stable isotope analyses of the water show that recharge to the geothermal systems generally occurs from areas of higher elevation adjacent to the sites. Tritium contents of apparently undiluted thermal fluids range from 0 to 0.4 T.U., indicating residence times of fluids in the systems of more than 500 y. Various geochemical indicators show that mixing of hot and cold end-member fluids occurs in the system at Platanares and, to a lesser degree, in the systems at San Ignacio and Azacualpa. No mixing is apparent in the fluids discharging at Pavana, Sambo Creek, or El Olivar. Boiling is the dominant process responsible for subtle geochemical variations at Azacualpa and, possibly, San Ignacio. Our best estimates of subsurface reservoir temperatures are 225/sup 0/C at Platanares, 190/sup 0/C at San Ignacio, 185/sup 0/C at Azacualpa, 155/sup 0/C at Sambo Creek, 150/sup 0/C at Pavana, and 120/sup 0/C at El Olivar. The estimated power output of the three hottest sites is 45 thermal megawatts at Platanares, 14 thermal megawatts at San Ignacio, and 13 thermal megawatts at Azacualpa.

  13. The Lusi eruption site: insights from surface and subsurface investigations

    Science.gov (United States)

    Mazzini, A.

    2017-12-01

    The Indonesian Lusi eruption has been spewing boiling water, gas, and sediments since the 29th of May 2006. Initially, numerous aligned eruptions sites appeared along the Watukosek fault system (WFS) that was reactivated after the Yogyakarta earthquake occurring the 27th of May in the Java Island. Within weeks several villages were submerged by boiling mud. The most prominent eruption site was named Lusi. To date Lusi is still active and an area of 7 km2is covered by mud. Since its birth Lusi erupted with a pulsating behaviour. In the framework of the ERC grant "Lusi Lab" we conducted several years of monitoring and regional investigations coupling surface sampling and subsurface imaging in the region around Lusi. Ambient noise tomography studies, obtained with a local network of 31 stations, revealed for the first time subsurface images of the Lusi region and the adjacent Arjuno-Welirang (AW) volcanic complex. Results show that below the AW volcanic complex are present 5km deep magma chambers that are connected, through a defined corridor, with the roots of the Lusi eruption site. The Lusi subsurface shows the presence of a defined vertical hydrothermal plume that extends to at least 5km. Chemical analyses of the seeping fluids sampled from 1) the Lusi plume (using a specifically designed drone), 2) the region around Lusi, and 3) the fumaroles and the hydro thermal springs of AW, revealed striking similarities. More specifically a mantellic signature of the Lusi fluids confirms the scenario that Lusi represents a magmatic-driven hydrothermal system hosted in sedimentary basin. Seismic profiles interpretation, surface mapping, and fluid sampling show that the WFS, connecting AW and extending towards the NE of Java, acted as a preferential pathway for the igneous intrusion and fluids migration towards the subsurface. Petrography and dating of the clasts erupted at Lusi record high temperatures and indicate that the roots of the active conduit extend to at least 5km

  14. Hydrogeochemical site descriptive model - a strategy for the model development during site investigations

    International Nuclear Information System (INIS)

    Smellie, John; Laaksoharju, Marcus; Tullborg, Eva-Lena

    2002-12-01

    In 2002, SKB commenced site characterisation investigations using deep boreholes at different sites. As an integral part of the planning work SKB has prepared a strategy to develop a Hydrogeochemical Site Descriptive Model; similar strategies have been developed for the other major geoscience disciplines. The main objectives of the Hydrogeochemical Site Descriptive Model are to describe the chemistry and distribution of the groundwater in the bedrock and overburden and the hydrogeochemical processes involved in its origin and evolution. This description is based primarily on measurements of the groundwater composition but incorporates the use of available geological and hydrogeological site descriptive models. The SKB hydrogeochemistry programme is planned to fulfil two basic requirements: 1) to provide representative and quality assured data for use as input parameter values in calculating long-term repository safety, and 2) to understand the present undisturbed hydrogeochemical conditions and how these conditions will change in the future. Parameter values for safety analysis include pH, Eh, S, SO 4 , HCO 3 , HPO 4 and TDS (mainly cations), together with colloids, fulvic and humic acids, other organics, bacteria and nitrogen. These values will be used to characterise the groundwater environment at, above and below repository depths. In the hydrogeochemical site investigation programme the number and location of the sampling points will be constrained by: a) geology (e.g. topography, overburden types, bedrock structures etc), b) hydrogeology (e.g. groundwater recharge/discharge areas, residence times), c) reliability (e.g. undisturbed vs disturbed groundwater chemical conditions), and d) resources (e.g. number and type of samples, and also available personnel, may be restricted by budgetary and schedule concerns). Naturally a balance is required between these constraints and the scientific aims of the programme. The constraints should never detrimentally affect

  15. Final work plan : environmental site investigation at Sylvan Grove, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Science Division)

    2012-07-15

    In 1998, carbon tetrachloride was found above the maximum contaminant level (MCL) of 5 {micro}g/L in groundwater from one private livestock well at Sylvan Grove, Kansas, by the Kansas Department of Health and Environment (KDHE). The 1998 KDHE sampling was conducted under the U.S. Department of Agriculture (USDA) private well sampling program. The Commodity Credit Corporation (CCC), a USDA agency, operated a grain storage facility in Sylvan Grove from 1954 to1966. Carbon tetrachloride is the contaminant of primary concern at sites associated with former CCC/USDA grain storage operations. Sylvan Grove is located in western Lincoln County, approximately 60 mi west of Salina (Figure 1.1). To determine whether the former CCC/USDA facility at Sylvan Grove is a potential contaminant source and its possible relationship to the contamination in groundwater, the CCC/USDA has agreed to conduct an investigation, in accordance with the Intergovernmental Agreement between the KDHE and the Farm Service Agency (FSA) of the USDA. This Work Plan presents historical data related to previous investigations, grain storage operations, local private wells and public water supply (PWS) wells, and local geologic and hydrogeologic conditions at Sylvan Grove. The findings from a review of all available documents are discussed in Section 2. On the basis of the analyses of historical data, the following specific technical objectives are proposed for the site investigation at Sylvan Grove: (1) Evaluate the potential source of carbon tetrachloride at the former CCC/USDA facility; (2) Determine the relationship of potential contamination (if present) at the former CCC/USDA facility to contamination identified in 1998 in groundwater samples from one private well to the west; and (3) Delineate the extent of potential contamination associated with the former CCC/USDA facility. The detailed scope of work is outlined in Section 3. The results of the proposed work will provide the basis for determining

  16. Literacies for Surveillance: Social Network Sites and Background Investigations

    Directory of Open Access Journals (Sweden)

    Sarah Jackson Young

    2015-09-01

    Full Text Available In September 2013, civilian contractor Aaron Alexis entered the Washington Navy Yard and murdered twelve people before being fatally shot by police. This incident, together with an incident three months earlier involving Edward Snowden, caused the U.S. government to critically examine their background investigation (BI process; because both Snowden and Alexis had supposedly slipped through the cracks of their investigations, there must be some flaw in the BI procedure. The U.S. Committee on Oversight and Reform concluded that rules forbidding “background checkers from looking at the Internet or social media when performing checks” was one of the main factors contributing to defective BIs (Report, 2014. Since the report’s release, the Director of National Intelligence has been debating and trialing whether information from the Internet should be used to form a data double for BIs (Kopp, 2014; Rockwell, 2014. Using this conversation as a discussion catalyst, I argue that due to the nature of the data double, if the United States were to adopt the use of social networking sites (SNSs for security clearance purposes, neglecting to take into account basic principles of SNSs into the process of BIs may lead to misinformation and unfavorable adjudication. Ultimately, being literate about the social practices involved in SNSs and surveillance would benefit not only investigators, but anyone, including academics, looking at individuals in online spaces.

  17. Geologic investigations of drill hole sloughing problems, Nevada Test Site

    International Nuclear Information System (INIS)

    Drellack, S.L. Jr.; Davies, W.J.; Gonzales, J.L.; Hawkins, W.L.

    1983-01-01

    Severe sloughing zones encountered while drilling large diameter emplacement holes in Yucca Flat, Nevada Test Site, have been identified, correlated and predicted through detailed geologic investigations. In central and southeastern Area 7 and in northern Area 3, the unstable zones are a very fine-grained, well-sorted, unconsolidated sand deposit, probably eolian in origin, which will readily flow into large diameter drill holes. Other areas exhibit hole erosion related to poor induration or extensive zeolitization of the Tertiary tuff units which are very friable and porous. By examining drill hole samples, geophysical logs, caliper logs and drilling histories, these problem zones can be characterized, correlated and then projected into nearby sites. Maps have been generated to show the depth, thickness and areal extent of these strata. In some cases, they are local and have a lenticular geometry, while in others they are quite extensive. The ability to predict such features can enhance the quality of the hole construction and completion operations to avoid costly delays and the loss of valuable testing real estate. The control of hole enlargements will also eliminate related containment concerns, such as stemming uncertainties

  18. New geochemical investigations in Platanares and Azacualpa geothermal sites (Honduras)

    Science.gov (United States)

    Barberi, Franco; Carapezza, Maria Luisa; Cioni, Roberto; Lelli, Matteo; Menichini, Matia; Ranaldi, Massimo; Ricci, Tullio; Tarchini, Luca

    2013-05-01

    Platanares and Azacualpa geothermal sites of Honduras are located in an inner part of the Caribbean Plate far from the active volcanic front of Central America. Here geology indicates that there are not the conditions for the occurrence of shallow magmatic heat sources for high-enthalpy geothermal resources. Geothermal perspectives are related to the possibility of a deep circulation of meteoric water along faults and the storage of the heated fluid in fractured permeable reservoirs. Geochemical geothermometers indicate a temperature for the deeper part of the geothermal reservoir close to 200 °C for Platanares and of 150-170 °C for Azacualpa. Calcite scaling, with subordinate silica deposition has to be expected in both sites. CO2 soil flux investigations have been carried out in both areas and reveal the presence of positive anomalies likely corresponding to the presence at depth of fractured degassing geothermal reservoirs. Compared with the geothermal areas of Central Italy whose reservoirs are hosted in carbonate rocks, e.g. Latera (Chiodini et al., 2007), the CO2 soil flux measured in Honduras is significantly lower (mean of 17 g/m2day at Platanares and of 163 g/m2day at Azacualpa) probably because of the dominant silicate nature of the deep reservoirs.

  19. Oskarshamn site investigation. Bedrock geology - overview and excursion guide

    Energy Technology Data Exchange (ETDEWEB)

    Wahlgren, Carl-Henric (Geological Survey of Sweden, Uppsala (Sweden))

    2010-09-15

    Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark and Laxemar-Simpevarp (this guide) areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at eight representative outcrops or outcrop areas at the ground surface in the site investigation area at Laxemar-Simpevarp and at one locality north of this area, i.e. at a total of nine localities

  20. Forsmark site investigation. Bedrock geology - overview and excursion guide

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, Michael B. (Geological Survey of Sweden, Uppsala (Sweden))

    2010-09-15

    Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark (this guide) and Laxemar-Simpevarp areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel in Finland. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at ten representative outcrops or outcrop areas at the ground surface in the site investigation area at Forsmark. All localities are located within or immediately adjacent to the proposed repository volume selected by SKB

  1. Forsmark site investigation. Bedrock geology - overview and excursion guide

    International Nuclear Information System (INIS)

    Stephens, Michael B.

    2010-09-01

    Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark (this guide) and Laxemar-Simpevarp areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel in Finland. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at ten representative outcrops or outcrop areas at the ground surface in the site investigation area at Forsmark. All localities are located within or immediately adjacent to the proposed repository volume selected by SKB

  2. The development and site investigation of fume diluter

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bok Youn; Kang, Chang Hee; Jo, Young Do; Lim, Sang Taek [Korea Institute of Geology Mining and Materials, Taejon (Korea, Republic of)

    1996-12-01

    It is third project year on `Application of mobile diesel equipment in underground mines` for providing appropriate measures to improve underground working environment contaminated by the diesel exhaust pollutants. For reducing the exhaust temperature bellow 70 deg. C to prevent production of the governing pollutant (NO{sub 2}), the fume diluter is verified the most effective device through the site investigation. Therefore, the fume diluter is strongly recommended instead of catalytic converter which is employed presently. The performances derived from the tests are as follows; 1) This device increased air flow to 6.7-8.4 times of the original exhaust, 2) Exhaust temperature can be reduced to 66 deg. C from 161 deg. C, 3) All the pollutants can be reduced to bellow than 30 % of exhaust concentration, 4) This device requires less cost and no maintenance. (author). 4 tabs., 4 figs.

  3. Oskarshamn site investigation. Bedrock geology - overview and excursion guide

    International Nuclear Information System (INIS)

    Wahlgren, Carl-Henric

    2010-09-01

    Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark and Laxemar-Simpevarp (this guide) areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at eight representative outcrops or outcrop areas at the ground surface in the site investigation area at Laxemar-Simpevarp and at one locality north of this area, i.e. at a total of nine localities

  4. Streamlining the Bankability Process using International Standards

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, Sarah [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Repins, Ingrid L [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Kelly, George [Sunset Technology, Mount Airy, MD; Ramu, Govind [SunPower, San Jose, California; Heinz, Matthias [TUV Rheinland, Cologne, Germany; Chen, Yingnan [CGC (China General Certification Center), Beijing; Wohlgemuth, John [PowerMark, Union Hall, VA; Lokanath, Sumanth [First Solar, Tempe, Arizona; Daniels, Eric [Suncycle USA, Frederick MD; Hsi, Edward [Swiss RE, Zurich, Switzerland; Yamamichi, Masaaki [RTS, Trumbull, CT

    2017-09-27

    NREL has supported the international efforts to create a streamlined process for documenting bankability and/or completion of each step of a PV project plan. IECRE was created for this purpose in 2014. This poster describes the goals, current status of this effort, and how individuals and companies can become involved.

  5. Hydrogeochemical site descriptive model - a strategy for the model development during site investigations

    Energy Technology Data Exchange (ETDEWEB)

    Smellie, John [Conterra AB, Uppsala (Sweden); Laaksoharju, Marcus [GeoPoint AB, Sollentuna (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden)

    2002-12-01

    In 2002, SKB commenced site characterisation investigations using deep boreholes at different sites. As an integral part of the planning work SKB has prepared a strategy to develop a Hydrogeochemical Site Descriptive Model; similar strategies have been developed for the other major geoscience disciplines. The main objectives of the Hydrogeochemical Site Descriptive Model are to describe the chemistry and distribution of the groundwater in the bedrock and overburden and the hydrogeochemical processes involved in its origin and evolution. This description is based primarily on measurements of the groundwater composition but incorporates the use of available geological and hydrogeological site descriptive models. The SKB hydrogeochemistry programme is planned to fulfil two basic requirements: 1) to provide representative and quality assured data for use as input parameter values in calculating long-term repository safety, and 2) to understand the present undisturbed hydrogeochemical conditions and how these conditions will change in the future. Parameter values for safety analysis include pH, Eh, S, SO{sub 4}, HCO{sub 3}, HPO{sub 4} and TDS (mainly cations), together with colloids, fulvic and humic acids, other organics, bacteria and nitrogen. These values will be used to characterise the groundwater environment at, above and below repository depths. In the hydrogeochemical site investigation programme the number and location of the sampling points will be constrained by: a) geology (e.g. topography, overburden types, bedrock structures etc), b) hydrogeology (e.g. groundwater recharge/discharge areas, residence times), c) reliability (e.g. undisturbed vs disturbed groundwater chemical conditions), and d) resources (e.g. number and type of samples, and also available personnel, may be restricted by budgetary and schedule concerns). Naturally a balance is required between these constraints and the scientific aims of the programme. The constraints should never

  6. Seismic tomography investigation of the Down Ampney fault research site

    International Nuclear Information System (INIS)

    Jackson, P.D.; Greenwood, P.G.; Raines, M.G.; Rainsbury, M.P.

    1991-01-01

    High resolution tomographic cross-hole seismic surveys have been designed and undertaken for fault characterisation in mudrocks at a higher resolution than is currently used in site investigations. Compressional waves were generated at a frequency of 1.04 kHz and a wavelength of 1.6 m in the formation, and were used to tomographically image a normally faulted clay sequence (Oxford Clay and Kellaways Beds) overlying limestone. The fault plane and lithologies are clearly visible in the tomograms, a 10% difference in velocity between the Oxford Clay and Kellaways Beds, being particularly prominent. A zone of 5% lower ''tomographic - velocity'' was observed to correspond with the fault zone within the Oxford Clay (as predicted from the geological logging of the core) which indicates substantial alteration that could be fluid affected. Geological constraints were found to be a crucial imput to the tomographic inversion, and examples show erroneous results that can arise. Seismic attenuation was very low (reflection observed from 80 m depth) and larger ranges could have been used to investigate larger scale geological structures. (author)

  7. Site investigation SFR. Vegetation in streams in the Forsmark area

    International Nuclear Information System (INIS)

    Andersson, Eva; Aquilonius, Karin; Sivars Becker, Lena; Borgiel, Mikael

    2011-09-01

    The streams in the model area of Forsmark have previously been thoroughly investigated regarding water chemistry, hydrology, bottom substrate, flooding, percentage coverage of macrophytes and fish migration. Retention of radionuclides in a stream ecosystem is assumed to occur by sorption to sediments or by uptake of radionuclides by macrophytes and it is therefore of interest to know the biomass and production of macrophytes in the streams included in a safety assessment. The general aim of this study was to examine the relation between biomass and the percentage cover of vegetation in streams in the Forsmark area. In this study streams within and nearby the candidate area in Forsmark was investigated. The somewhat larger streams Forsmarksaan and Olandsaan nearby the candidate area, are assumed to be more similar to future streams developing in Forsmark due to landrise, than the smaller streams present in the candidate area today. In total 22 vegetation samples were gathered in order to estimate the biomass at the sites. Percentage coverage of macrophytes, and dominating species were noted and the above ground macrophytes were sampled for biomass analysis. In the smaller streams, the biomass varied between 6 and almost 358 g dry weight per square metre. In the larger streams, the dry biomass varied between 0 and 247 g dry weight per square meter. There were no significant difference between macrophyte biomass in smaller and the larger stream. In total 13 macrophyte species were found. The biomass dry weight at 100% covering degree varied depending on macrophyte species. Although this was a rather small study, it is evident that the biomasses do vary a wide range between sampling squares in the area. However, although it may be difficult to use this data set to estimate the biomass in a specific square meter in the stream section, the relation between biomass weight and covering degree is sufficient to be used when fitting biomass to macrophyte coverage for entire

  8. Site investigation SFR. Vegetation in streams in the Forsmark area

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Eva (Svensk Nuclear Fuel and Waste Management Co. (Sweden)); Aquilonius, Karin; Sivars Becker, Lena (Studsvik Nuclear AB (Sweden)); Borgiel, Mikael (Sveriges Vattenekologer AB (Sweden))

    2011-09-15

    The streams in the model area of Forsmark have previously been thoroughly investigated regarding water chemistry, hydrology, bottom substrate, flooding, percentage coverage of macrophytes and fish migration. Retention of radionuclides in a stream ecosystem is assumed to occur by sorption to sediments or by uptake of radionuclides by macrophytes and it is therefore of interest to know the biomass and production of macrophytes in the streams included in a safety assessment. The general aim of this study was to examine the relation between biomass and the percentage cover of vegetation in streams in the Forsmark area. In this study streams within and nearby the candidate area in Forsmark was investigated. The somewhat larger streams Forsmarksaan and Olandsaan nearby the candidate area, are assumed to be more similar to future streams developing in Forsmark due to landrise, than the smaller streams present in the candidate area today. In total 22 vegetation samples were gathered in order to estimate the biomass at the sites. Percentage coverage of macrophytes, and dominating species were noted and the above ground macrophytes were sampled for biomass analysis. In the smaller streams, the biomass varied between 6 and almost 358 g dry weight per square metre. In the larger streams, the dry biomass varied between 0 and 247 g dry weight per square meter. There were no significant difference between macrophyte biomass in smaller and the larger stream. In total 13 macrophyte species were found. The biomass dry weight at 100% covering degree varied depending on macrophyte species. Although this was a rather small study, it is evident that the biomasses do vary a wide range between sampling squares in the area. However, although it may be difficult to use this data set to estimate the biomass in a specific square meter in the stream section, the relation between biomass weight and covering degree is sufficient to be used when fitting biomass to macrophyte coverage for entire

  9. Hydrodynamic Drag on Streamlined Projectiles and Cavities

    KAUST Repository

    Jetly, Aditya

    2016-04-19

    The air cavity formation resulting from the water-entry of solid objects has been the subject of extensive research due to its application in various fields such as biology, marine vehicles, sports and oil and gas industries. Recently we demonstrated that at certain conditions following the closing of the air cavity formed by the initial impact of a superhydrophobic sphere on a free water surface a stable streamlined shape air cavity can remain attached to the sphere. The formation of superhydrophobic sphere and attached air cavity reaches a steady state during the free fall. In this thesis we further explore this novel phenomenon to quantify the drag on streamlined shape cavities. The drag on the sphere-cavity formation is then compared with the drag on solid projectile which were designed to have self-similar shape to that of the cavity. The solid projectiles of adjustable weight were produced using 3D printing technique. In a set of experiments on the free fall of projectile we determined the variation of projectiles drag coefficient as a function of the projectiles length to diameter ratio and the projectiles specific weight, covering a range of intermediate Reynolds number, Re ~ 104 – 105 which are characteristic for our streamlined cavity experiments. Parallel free fall experiment with sphere attached streamlined air cavity and projectile of the same shape and effective weight clearly demonstrated the drag reduction effect due to the stress-free boundary condition at cavity liquid interface. The streamlined cavity experiments can be used as the upper bound estimate of the drag reduction by air layers naturally sustained on superhydrophobic surfaces in contact with water. In the final part of the thesis we design an experiment to test the drag reduction capacity of robust superhydrophobic coatings deposited on the surface of various model vessels.

  10. Integrated site investigation and groundwater monitoring in an urban environment

    Science.gov (United States)

    Weatherl, R. K.

    2017-12-01

    Understanding groundwater dynamics around cities and other areas of human influence is of crucial importance for water resource management and protection, especially in a time of environmental and societal change. The human environment presents a unique challenge in terms of hydrological characterization, as the water cycle is generally artificialized and emissions of treated waste and chemical products into the surface- and groundwater system tend to disrupt the natural aqueous signature in significant ways. This project presents an integrated approach for robust characterization and monitoring of an urban aquifer which is actively exploited for municipal water supply. The study is carried out in the town of Fehraltorf, in the canton of Zürich, Switzerland. This particular town encompasses industrial and agricultural zones in addition to its standard urban setting. A minimal amount of data exist at this site, and the data that do exist are spatially and temporally sparse. Making use of traditional hydrogeological methods alongside evolving and emerging technologies, we aim to identify sources of contamination and to define groundwater flow and solute transport through space and time. Chemical and physical indicator parameters are identified for tracing contaminations including micropollutants and plant nutrients. Wireless sensors are installed for continuous on-line monitoring of essential parameters (electrical conductivity, temperature, water level). A wireless sensor network has previously been installed in the sewer system of the study site, facilitating investigation into interactions between sewer water and groundwater. Our approach illustrates the relations between land use, climate, rainfall dynamics, and the groundwater signature through time. At its conclusion, insights gained from this study will be used by municipal authorities to refine protective zones around pumping wells and to direct resources towards updating practices and replacing

  11. Multiagency radiation survey and site investigation manual (MARSSIM): Survey design

    International Nuclear Information System (INIS)

    Abelquist, E.W.; Berger, J.D.

    1996-01-01

    This paper describes the MultiAgency Radiation Survey and Site Investigation Manual (MARSSIM) strategy for designing a final status survey. The purpose of the final status survey is to demonstrate that release criteria established by the regulatory agency have been met. Survey design begins with identification of the contaminants and determination of whether the radionuclides of concern exist in background. The decommissioned site is segregated into Class 1, Class 2, and Class 3 areas, based on contamination potential, and each area is further divided into survey units. Appropriate reference areas for indoor and outdoor background measurements are selected. Survey instrumentation and techniques are selected in order to assure that the instrumentation is capable of detecting the contamination at the derived concentration guideline level (DCGL). Survey reference systems are established and the number of survey data points is determined-with the required number of data points distributed on a triangular grid Pattern. Two suitistical tests are used to evaluate data from final status surveys. For contaminants that are b, present in background, the Wilcoxon Rank Sum test is used; for contaminants that are not present in background, the Wilcoxon Signed Rank (or Sign) test is used. The number of data points needed to satisfy these nonparametric tests is based on the contaminant DCGL value, the expected Standard deviation of the contaminant in background and in the survey unit, and the acceptable probability of making Type I and Type II decision errors. The MARSSIM also requires a reasonable level of assurance that any small areas of elevated residual radioactivity that could be significant relative to regulatory limits are not missed during the final status survey. Measurements and sampling on a specified grid size are used to obtain an adequate assurance level that small locations of elevated radioactivity will Still satisfy DCGLs-applicable to small areas

  12. Engineering rock mass classification of the Olkiluoto investigation site

    Energy Technology Data Exchange (ETDEWEB)

    Aeikaes, K. [ed.; Hagros, A.; Johansson, E. [Saanio and Riekkola Consulting Engineers, Helsinki (Finland)] [and others

    2000-06-01

    Olkiluoto in Eurajoki is being investigated as a possible site for the final disposal of spent nuclear fuel from the Finnish nuclear power plants. The selection of the depth, placement and layout of the repository is affected by the constructability of the bedrock. The constructability, in turn, is influenced by several properties of the host rock, such as its Ethology, the extent of fracturing, its hydrogeological properties and rock engineering characteristics and also by the magnitude and orientation of the in situ stresses and the chemistry of the groundwater. The constructability can be evaluated by the application of a rock classification system in which the properties of the host rock are assessed against common rock engineering judgements associated with underground construction. These judgements are based partly on measurements of in situ stresses and the properties of the bedrock determined from rock samples, but an important aspect is also the practical experience which has been gained during underground excavation in similar conditions and rock types. The aim of the engineering rock mass classification was to determine suitable bedrock volumes for the construction of the repository and has used data from the site characterisation programme carried out at Olkiluoto, which consisted of both surface studies and borehole investigations. The classification specifies three categories of constructability - normal, demanding and very demanding. In addition, rock mass quality has also been classified according to the empirical Q-system to enable a comparison to be made. The rock mass parameters that determine the constructability of the bedrock at Olkiluoto depend primarily on the depth and the Ethology, as well as on whether construction takes place in intact or in fractured rock. The differences in the characteristics of intact rock within a single rock type have been shown to be small. The major lithological unit at Olkiluoto, the mica gneiss, lies in the

  13. Getting ready for inspection of investigational site at short notice

    Directory of Open Access Journals (Sweden)

    Rajendra Talele

    2010-01-01

    Full Text Available India is becoming an attractive destination for drug development and clinical research. This is evidenced by the three fold increment in clinical trial applications in last four years to the office of Drugs Controller General of India (DCGI. This upward trend is collaborative efforts of all stake holders and the quality of Indian data. Therefore to sustain this trend, it is important that stake holders such as Regulators, Sponsor, CRO, Monitor, Investigators and trial subjects required maintaining high standards of data and conduct of clinical trials. Indian regulations and the role of DCGI in quality check for Indian clinical trials is always a topic of discussion in various forums. A recent move by DCGI for conducting random inspections of investigational sites and companies at short notice, checking their compliance in accordance with the guidelines, and taking action against non-complier is welcomed. This will certainly increase over quality of the clinical trials. Quality of clinical trial conduct is measured on essential documents for their appropriateness and its correctness. It is observed that the stakeholders engaged in multitasking often overlook the requirements or appropriateness of the document due to their focused approach on a specific activity which is on priority. This can lead to serious quality problem and issues. Understanding of the process and documents reviewed by auditor is important to maintain such high quality. The proper planning and time management working on essential documents can minimize the quality issues, and we can be always ready for any type of inspection, announced or unannounced, or "short notice".

  14. Site investigation equipment developed by Teollisuuden Voima Oy

    International Nuclear Information System (INIS)

    Oehberg, A.

    1991-02-01

    Teollisuuden Voima Oy (TVO) carries out site investigations in Finland for final disposal of nuclear high level waste during 1987-2000. In order to carry out the investigations some essential equipment have been designed and constructed. The biggest insufficiency among different measuring methods was among water sampling and hydraulic testing. There are some common specifications which all of these equipment has to fulfil. The two most important are that they have to be operatable in deep slim boreholes down to 1000 meters depth with 56 mm in diameter. The main purpose of the Hydraulic Testing Unit is to determine hydraulic conductivity in crystalline rock, where water can flow primarily through fractures. In most commonly used configurations, measurement range is from 10 - 11 to 10 - 5 m/s with constant-head method. Although constant-head method is principally used, almost any known hydraulic method is possible with existing hardware. Most functions are controlled by the computer. The whole system is built into an electrically heated trailer. The system consists of inflatable packers, stainless steel rods, pressure transducers and datalogging devices. The maximum number of monitoring sections is seven. In addition to that as many blind sections as is needed to prevent vertical flow in boreholes can be installed. Water sampling is possible either with a double packer method or in conjunction with the hydraulic head monitoring equipment. The first possibility involves using the laboratory trailer and the second one using a separate pumping unit plus the laboratory trailer in a later phase when sampling is to be conducted. In the laboratory trailer there are all the measuring devices needed to control different chemical parameters (pH, Eh, pS, O 2 , conductivity and temperature) during pumping

  15. Waste site grouping for 200 Areas soil investigations

    International Nuclear Information System (INIS)

    1997-01-01

    The purpose of this document is to identify logical waste site groups for characterization based on criteria established in the 200 Areas Soil Remediation Strategy (DOE-RL 1996a). Specific objectives of the document include the following: finalize waste site groups based on the approach and preliminary groupings identified in the 200 Areas Soil Remediation Strategy; prioritize the waste site groups based on criteria developed in the 200 Areas Soil Remediation Strategy; select representative site(s) that best represents typical and worse-case conditions for each waste group; develop conceptual models for each waste group. This document will serve as a technical baseline for implementing the 200 Areas Soil Remediation Strategy. The intent of the document is to provide a framework, based on waste site groups, for organizing soil characterization efforts in the 200 Areas and to present initial conceptual models

  16. Geophysical investigations of the Olonium Roman site (Northern Como Lake)

    Science.gov (United States)

    Arlsan, Ermanno; Biella, Giancarlo; Boniolo, Graziano; Caporusso, Donatella; de Franco, Roberto; Lozej, Alfredo; Veronese, Luigi

    1999-03-01

    The study area is located at S. Agata (Gera Lario), a small center at the northern end of Como Lake, near the junction of Valchiavenna and Valtellina Valleys. This site played a strategic role since ancient times, providing the control on the communications routes to both the Como Lake and the Spluga and Septimer alpine passes. Since the end of the last century archaeological findings are reported in literature, also supported, from the early XI century, by archival documents confirming the existence of the `Olonium' settlement, an administrative and fiscal center of primary importance, as well as a parish amongst the most influential in the Como Lake area. Within an area of 45,000 m 2 an electrical survey has been carried out in conjunction with magnetic and GPR investigations. These studies have indicated the presence of a number of sub-areas characterized by significant anomalies defined by the overlapping of the results obtained from two or more geophysical methods. In two of such sub-areas, excavation tests have been conducted, which have brought to light a number of archaeological findings of interest. In one of the two sub-areas, which is characterized by the superimposition of electrical and radar anomalies, a deposit of large pebbles has been found. The origin of this deposit has not been ascertained, whether it is of fluvial origin, related to the deviation of the Adda river in the Pian di Spagna region in Roman times, or it is part of reclamation works, still of Roman times, of paleolacustrine marshes. The overlapping stratigraphy, however, suggests the development of fluvial channels between Roman and Low-Medieval times. In the other sub-area, excavations were carried out on sites defined by electrical and radar anomalies, and confirmed by the results from magnetic survey. The excavations brought to light, below the fluvial deposits, a large medieval edifice, which could be identified as the S. Stefano church abandoned in 1444. The church is built on

  17. Corrective Action Investigation Plan for Corrective Action Unit 573: Alpha Contaminated Sites, Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick

    2014-05-01

    Corrective Action Unit (CAU) 573 is located in Area 5 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 573 is a grouping of sites where there has been a suspected release of contamination associated with non-nuclear experiments and nuclear testing. This document describes the planned investigation of CAU 573, which comprises the following corrective action sites (CASs): • 05-23-02, GMX Alpha Contaminated Area • 05-45-01, Atmospheric Test Site - Hamilton These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives.

  18. Final report : Hanover environmental site investigation, 2009-2010.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Science Division)

    2011-06-07

    The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride were detected in two private lawn and garden wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In July 2007, the CCC/USDA sampled indoor air at nine residences on or adjacent to its former facility to address the residents concerns. Low levels of carbon tetrachloride were detected at four of the nine homes. Consequently, the CCC/USDA has conducted investigations, under the direction of the KDHE, to determine the source and extent of the carbon tetrachloride contamination that might be associated with the former facility. In July 2007, the CCC/USDA sampled indoor air at nine residences on or adjacent to its former facility to address the residents concerns regarding vapor intrusion (VI). Low levels of carbon tetrachloride were detected at four of the nine homes. Because carbon tetrachloride found in private wells and indoor air at Hanover might be linked to historical use of fumigants containing carbon tetrachloride at its former grain storage facility, the CCC/USDA has conducted investigations to determine the source and extent of the carbon tetrachloride contamination that may be associated with the former facility. The results of the comprehensive investigation at Hanover indicate that no unacceptable risk to human health currently exists from exposure to surface and subsurface soils by either ingestion, inhalation or dermal contact. No risk is

  19. Thermal Site Descriptive Model. A strategy for the model development during site investigations. Version 1.0

    International Nuclear Information System (INIS)

    Sundberg, Jan

    2003-04-01

    Site investigations are in progress for the siting of a deep repository for spent nuclear fuel. As part of the planning work, strategies are developed for site descriptive modelling regarding different disciplines, amongst them the thermal conditions. The objective of the strategy for a thermal site descriptive model is to guide the practical implementation of evaluating site specific data during the site investigations. It is understood that further development may be needed. The model describes the thermal properties and other thermal parameters of intact rock, fractures and fracture zones, and of the rock mass. The methodology is based on estimation of thermal properties of intact rock and discontinuities, using both empirical and theoretical/numerical approaches, and estimation of thermal processes using mathematical modelling. The methodology will be used and evaluated for the thermal site descriptive modelling at the Aespoe Hard Rock Laboratory

  20. Alternative DFN model based on initial site investigations at Simpevarp

    Energy Technology Data Exchange (ETDEWEB)

    Darcel, C. [Itasca Consultants, Ecully (France); Davy, S.A.P.; Bour, O.; Dreuzy, J.R. de [Geosciences, Rennes (France)

    2004-12-01

    In this report, we provide a first-order analysis of the fracture network at the Simpevarp site. The first order model is the fracture distribution function, noted, fdf, which provides the number of fractures having a given orientation and length, and belonging to a given volume of observation. The first-order distribution model does not describe higher-order correlation between fracture parameters, such as a possible dependency of fracture length distribution with orientations. We also check that most of the information is contained in this 1st-order distribution model, and that dividing the fracture networks into different sets do not bring a better statistical description. The fracture distribution function contains 3 main distributions: the probability distribution of fracture orientations, the dependency on the size of the sampling domain that may exhibit non-trivial scaling in case of fractal correlations, and the fracture-length density distribution, which appears to be well fitted by a power law. The main scaling parameters are the fractal dimension and the power-law exponent of the fracture length distribution. The former was found to be about equal to the embedding dimension, meaning that fractal correlations are weak and can be neglected in the DFN model. The latter depends on geology, that is either lithology or grain size, with values that ranges from 3.2 for granite-like outcrops to 4 for diorite or monzodiorite outcrops, as well as for the large-scale lineament maps. When analyzing the consistency of the different datasets (boreholes, outcrops, lineament maps), we found that two different DFNs can be described: the first one is derived from the fdf of the outcrop with fine-grained size lithology, and is valid across all scales investigated in this study, from the highly-fractured cores to large-scale maps; the second one is derived from the fdf of the outcrops with coarse-grained size lithology, and is found consistent with cores that present the

  1. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

    Energy Technology Data Exchange (ETDEWEB)

    Wickline, Alfred

    2005-12-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting

  2. 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)

  3. Preliminary site investigation for LL and IL radwaste disposal for Qinshan NPP

    International Nuclear Information System (INIS)

    Huang Yawen; Chen Zhangru

    1993-01-01

    With the purpose of selecting a disposal site for the low- and intermediate-level radwastes arising from Qinshan NPP, site investigations were carried out in several districts of Zhejiang Province. Investigation objectives included the circumstances of geology, hydrogeology, environmental ecology, and social economy. On the basis of collected data, five possible sites were recommended for policy-making reference and further investigation

  4. 2015 Advanced Site Investigation and Monitoring Report Riverton, Wyoming, Processing Site September 2016

    Energy Technology Data Exchange (ETDEWEB)

    Frazier, William [U.S. Dept. of Energy, Washington, DC (United States). Office of Legacy Management (LM); Campbell, Sam [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)

    2016-09-01

    The U.S. Department of Energy conducted initial groundwater characterization of the Riverton, Wyoming, Processing Site in the 1990s. The characterization culminated in a Site Observational Work Plan in 1998 that recommended a natural flushing compliance strategy. Results of verification monitoring indicated that natural flushing was generally progressing as expected until June 2010, when significant increases in contaminant concentrations were measured in several monitoring wells downgradient of the site after the area flooded. In response to the unexpected results following the flood, an enhanced characterization of the surficial aquifer was conducted in 2012, which included installation of 103 boreholes along nine transects with a Geoprobe, collection of 103 water samples and 65 soil samples, laboratory tests on the soil samples, and additional groundwater modeling. This advanced site investigation report summarizes additional investigation in 2015 through the use of backhoe trenching, sonic drilling, multilevel monitoring wells, direct-push drilling, and temporary well points to collect soil and groundwater samples. Additional surface water measurements were made included the installation of a stilling well and the measurement of stream elevation along the Wind River to approximate upgradient groundwater heads. Groundwater sampling included the addition of geochemical constituents and isotopes that have not been sampled in the past to better understand post-flood conditions and the possibility of additional or ongoing contaminant sources. This sampling was performed to (1) better define the contaminant plumes, (2) verify the occurrence of persistent secondary contaminant sources, (3) better understand the reason for the contaminant spikes after a 2010 flood, and (4) assess contaminant plume stagnation near the Little Wind River. This report provides data analyses and interpretations for the 2015 site investigation that addresses these issues and provides

  5. Thermal site descriptive model. A strategy for the model development during site investigations - version 2

    Energy Technology Data Exchange (ETDEWEB)

    Back, Paer-Erik; Sundberg, Jan [Geo Innova AB (Sweden)

    2007-09-15

    This report presents a strategy for describing, predicting and visualising the thermal aspects of the site descriptive model. The strategy is an updated version of an earlier strategy applied in all SDM versions during the initial site investigation phase at the Forsmark and Oskarshamn areas. The previous methodology for thermal modelling did not take the spatial correlation fully into account during simulation. The result was that the variability of thermal conductivity in the rock mass was not sufficiently well described. Experience from earlier thermal SDMs indicated that development of the methodology was required in order describe the spatial distribution of thermal conductivity in the rock mass in a sufficiently reliable way, taking both variability within rock types and between rock types into account. A good description of the thermal conductivity distribution is especially important for the lower tail. This tail is important for the design of a repository because it affects the canister spacing. The presented approach is developed to be used for final SDM regarding thermal properties, primarily thermal conductivity. Specific objectives for the strategy of thermal stochastic modelling are: Description: statistical description of the thermal conductivity of a rock domain. Prediction: prediction of thermal conductivity in a specific rock volume. Visualisation: visualisation of the spatial distribution of thermal conductivity. The thermal site descriptive model should include the temperature distribution and thermal properties of the rock mass. The temperature is the result of the thermal processes in the repository area. Determination of thermal transport properties can be made using different methods, such as laboratory investigations, field measurements, modelling from mineralogical composition and distribution, modelling from density logging and modelling from temperature logging. The different types of data represent different scales, which has to be

  6. Thermal site descriptive model. A strategy for the model development during site investigations - version 2

    International Nuclear Information System (INIS)

    Back, Paer-Erik; Sundberg, Jan

    2007-09-01

    This report presents a strategy for describing, predicting and visualising the thermal aspects of the site descriptive model. The strategy is an updated version of an earlier strategy applied in all SDM versions during the initial site investigation phase at the Forsmark and Oskarshamn areas. The previous methodology for thermal modelling did not take the spatial correlation fully into account during simulation. The result was that the variability of thermal conductivity in the rock mass was not sufficiently well described. Experience from earlier thermal SDMs indicated that development of the methodology was required in order describe the spatial distribution of thermal conductivity in the rock mass in a sufficiently reliable way, taking both variability within rock types and between rock types into account. A good description of the thermal conductivity distribution is especially important for the lower tail. This tail is important for the design of a repository because it affects the canister spacing. The presented approach is developed to be used for final SDM regarding thermal properties, primarily thermal conductivity. Specific objectives for the strategy of thermal stochastic modelling are: Description: statistical description of the thermal conductivity of a rock domain. Prediction: prediction of thermal conductivity in a specific rock volume. Visualisation: visualisation of the spatial distribution of thermal conductivity. The thermal site descriptive model should include the temperature distribution and thermal properties of the rock mass. The temperature is the result of the thermal processes in the repository area. Determination of thermal transport properties can be made using different methods, such as laboratory investigations, field measurements, modelling from mineralogical composition and distribution, modelling from density logging and modelling from temperature logging. The different types of data represent different scales, which has to be

  7. Geochemical investigation of UMTRAP designated site at Canonsburg, Pennsylvania

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.; Freeman, T.

    1981-05-01

    UMTRAP is an acronym for Uranium Mill Tailings Remedial Action Project. The Canonsburg, Pennsylvania site was utilized from 1911 to 1922 and from 1930 to 1942, first to remove radium from sedimentary uranium ore, and later to remove uranium from ore as well as process various materials, ceasing operations in 1957. Of the three areas, Area A is the former mill site and is occupied in part by present industrial activities. Area B is comprised of mill residues mixed with sediment dredged from Chartiers Creek, a disturbed terrace along Chartiers Creek, and a ditch on the north side. The ditch contains water with the highest concentrations of contaminants measured in the Canonsburg site. It is believed that unprocessed ore is deposited here and effluent from leaks in a sewer line across the north edge of Areas A and B carry contaminants from heavily contaminated drains in the buildings of Area A. Area C contains the former liquid disposal lagoon, and the central part of the area is highly contaminated to a depth of about 3 meters. Area C contains the most concentrated waste material with maximum levels (except for the ditch on the north side of Area B) of all the contaminants distributed throughout the area. Contamination outside the site is limited. The presence of contaminants in the ditches, in the soils on the river bank, and below the tailings pile is not attributed to migration processes, but rather to the presence of ore materials and concentrated wastes mechanically dispersed throughout the area

  8. Investigation of anatomical anomalies in Hanford Site mule deer

    Energy Technology Data Exchange (ETDEWEB)

    Tiller, B.L.; Cadwell, L.L.; Poston, T.M. [and others

    1997-03-01

    Rocky Mountain mule deer (Odocoileus hemionus hemionus), common residents of the Hanford Site, are an important part of the shrub-steppe ecosystem as well as being valued for aesthetics and hunting. Because mule deer have been protected from hunting on the Site for 50 years, the herd has developed unique population characteristics, including a large number of old animals and males with either large or atypically developed antlers, in contrast to other herds in the semi-arid regions of the Northwest. Hanford Site mule deer have been studied since 1991 because of the herd`s unique nature and high degree of public interest. A special study of the mule deer herd was initiated in 1993 after observations were made of a relatively large number of male deer with atypical, velvet-covered antlers. This report specifically describes our analyses of adult male deer found on the Site with atypical antlers. The report includes estimates of population densities and composition; home ranges, habitat uses, and dietary habits; natural and human-induced causes of mortality; and the herd`s overall health and reproductive status.

  9. Investigation of anatomical anomalies in Hanford Site mule deer

    International Nuclear Information System (INIS)

    Tiller, B.L.; Cadwell, L.L.; Poston, T.M.

    1997-03-01

    Rocky Mountain mule deer (Odocoileus hemionus hemionus), common residents of the Hanford Site, are an important part of the shrub-steppe ecosystem as well as being valued for aesthetics and hunting. Because mule deer have been protected from hunting on the Site for 50 years, the herd has developed unique population characteristics, including a large number of old animals and males with either large or atypically developed antlers, in contrast to other herds in the semi-arid regions of the Northwest. Hanford Site mule deer have been studied since 1991 because of the herd's unique nature and high degree of public interest. A special study of the mule deer herd was initiated in 1993 after observations were made of a relatively large number of male deer with atypical, velvet-covered antlers. This report specifically describes our analyses of adult male deer found on the Site with atypical antlers. The report includes estimates of population densities and composition; home ranges, habitat uses, and dietary habits; natural and human-induced causes of mortality; and the herd's overall health and reproductive status

  10. Perspectives of investigation and development of Semipalatinsk Test Site

    International Nuclear Information System (INIS)

    Kadyrzhanov, K.K.; Lukashenko, S.N.

    2008-01-01

    Full text: Since the Semipalatinsk Test Site has been stopped and up until now, National Nuclear Center of the Republic of Kazakhstan (NNC RK) in cooperation with other specialist from Kazakhstan and international scientific community have accumulated large scope of information about current radiological situation at Semipalatinsk Nuclear Test Site (SNTS) and adjacent territories. There were revealed all important spots of radioactive contamination, identified main pathways and mechanisms for present and potential proliferation of radioactive substances. Obtained data assure us that present-day SNTS provides no negative impact on population on adjacent to the Site territories excluding people in the water basin of the river Shagan. Compliance with regulatory requirements and special rules for SNTS territory assures radiation safety at commercial activities on the Site. At the same time, the radiological situation does not remain stable; there were revealed the processes of radionuclide migration what requires regular monitoring of radiological situation at SNTS. Taking into account the scale of the Site and the variety of tests performed there, the information available about SNTS can not be completely exhaustive but enables us to propose a scientifically grounded plan for further research and practical measures aimed at remediation and reclamation of lands. implementation of such measures should return up to 80% of the lands to commercial use. SNTS is one of the world largest nuclear test sites with decisive contribution to creation and development of nuclear weapon. To considerable extent, these were works at SNTS which established nuclear parity between the superpowers one of the crucial factors in the history of human civilization in the 20 century. Also taking into account the interest to SNTS paid by international organizations, it is reasonable to initiate a procedure and recognize SNTS as a landmark including it in the UNESCO List of Cultural and Nature

  11. Lightroom 5 streamlining your digital photography process

    CERN Document Server

    Sylvan, Rob

    2014-01-01

    Manage your images with Lightroom and this beautifully illustrated guide Image management can soak up huge amounts of a photographer's time, but help is on hand. This complete guides teaches you how to use Adobe Lightroom 5 to import, manage, edit, and showcase large quantities of images with impressive results. The authors, both professional photographers and Lightroom experts, walk you through step by step, demonstrating real-world techniques as well as a variety of practical tips, tricks, and shortcuts that save you time. Streamline image management tasks like a pro, and get back to doing

  12. The investigation of leukaemia incidence around sites of special interest

    International Nuclear Information System (INIS)

    Urquhart, J.

    1991-01-01

    The study of the incidence of leukaemia and non-Hodgkin's lymphoma around sites of special interest has created many methodological and philosophical problems. Not least of these is the construction of boundaries of space and time to delineate areas of study around a point source of interest. Studies such as those of the incidence of childhood leukaemia around Dounreay have made use of arbitrarily selected fixed geographic boundaries. The Poisson maximum method proposed by Stone and Bithell provides an alternative approach in which no prior selection of geographic boundaries is required. The application of an adaptation of this method to each of the Scottish nuclear sites confirmed the results found for Dounreay by other methods. No excess incidence was observed around the Hunterston Nuclear Installation and an observed excess incidence around Chapelcross was not statistically significant. The further development of statistical techniques which do not require the arbitrary selection of boundaries will facilitate the monitoring of the incidence of disease around sites of special interest and perhaps permit it to be carried out in a less combative climate than has hitherto been the case. (author)

  13. Site description of the SFR area at Forsmark at completion of the site investigation phase. SDM-PSU Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-05-15

    The site descriptive model (SDM) presented in this report is an integrated model for bedrock geology, rock mechanics, bedrock hydrogeology and bedrock hydrogeochemistry of the site investigated in the SFR extension project (PSU). A description of the surface system is also included in the report. However, the surface system is not integrated with the other disciplines as new data regarding the surface system will not be available until after the completion of SDM-PSU. It is noted that SDM-PSU does not include all disciplines handled in SDM-Site Forsmark (SKB 2008b), the focus is to produce a site description that meets the needs of the SFR extension project. The overall objective of the SFR extension project is to have the application for the extension ready by 2013. This report presents an integrated site model incorporating the historic data acquired from the investigations for and construction of the existing SFR facility (1980-1986), as well as from the recent investigations for the planned extension of SFR (2008-2009). It also provides a summary of the abundant underlying data and the discipline-specific models that support the integrated site model. The description relies heavily on background reports concerning detailed data analyses and modelling in the different disciplines. It is noteworthy that the investigations conducted during the SFR extension project were guided by the choice of site prior to the investigations, which was based on the experience gained during the construction of the existing SFR facility.

  14. Site description of the SFR area at Forsmark at completion of the site investigation phase. SDM-PSU Forsmark

    International Nuclear Information System (INIS)

    2013-05-01

    The site descriptive model (SDM) presented in this report is an integrated model for bedrock geology, rock mechanics, bedrock hydrogeology and bedrock hydrogeochemistry of the site investigated in the SFR extension project (PSU). A description of the surface system is also included in the report. However, the surface system is not integrated with the other disciplines as new data regarding the surface system will not be available until after the completion of SDM-PSU. It is noted that SDM-PSU does not include all disciplines handled in SDM-Site Forsmark (SKB 2008b), the focus is to produce a site description that meets the needs of the SFR extension project. The overall objective of the SFR extension project is to have the application for the extension ready by 2013. This report presents an integrated site model incorporating the historic data acquired from the investigations for and construction of the existing SFR facility (1980-1986), as well as from the recent investigations for the planned extension of SFR (2008-2009). It also provides a summary of the abundant underlying data and the discipline-specific models that support the integrated site model. The description relies heavily on background reports concerning detailed data analyses and modelling in the different disciplines. It is noteworthy that the investigations conducted during the SFR extension project were guided by the choice of site prior to the investigations, which was based on the experience gained during the construction of the existing SFR facility

  15. Forsmark site investigation. Investigation of marine and lacustrine sediment in lakes. Field data 2003

    Energy Technology Data Exchange (ETDEWEB)

    Hedenstroem, Anna [SGU, Uppsala (Sweden)

    2003-04-01

    The aim of this activity is to describe the aerial and stratigraphical distribution of marine and lacustrine sediment i.e. sediment overlaying the glacial till and/or bedrock surface, in lakes in the Forsmark area. The investigation is carried out within areas where mapping of unconsolidated Quaternary deposits is presently carried out. Since small and shallow lakes cover a large part of the region, this work will give important information on the distribution and stratigraphy of sedimentary deposits not included in the regular mapping of unconsolidated Quaternary deposits within the site investigation programme. Samples were also collected for laboratory analyses of grain size distribution, mineralogical composition as well as the total content of C, N and S and calcium carbonate. The analyses will be carried out on selected samples of representative sedimentary units in order to characterise the chemical and physical properties of the unconsolidated deposits. The analytical data will be useful for the hydrogeological modelling and for models of the Quaternary evolution of the area. The mineralogical analyses of clay may provide information on the origin of the clay particles. One stratigraphic sequence from Lake Eckarfjaerden will be stored for later analyses, e.g. pollen analysis. This report includes field data from spring 2003. Together, the field data and the forthcoming results from the laboratory analyses will form the basis for construction of stratigraphical profiles to be presented in a following report in the fall 2003.

  16. Forsmark site investigation. Investigation of marine and lacustrine sediment in lakes. Field data 2003

    International Nuclear Information System (INIS)

    Hedenstroem, Anna

    2003-04-01

    The aim of this activity is to describe the aerial and stratigraphical distribution of marine and lacustrine sediment i.e. sediment overlaying the glacial till and/or bedrock surface, in lakes in the Forsmark area. The investigation is carried out within areas where mapping of unconsolidated Quaternary deposits is presently carried out. Since small and shallow lakes cover a large part of the region, this work will give important information on the distribution and stratigraphy of sedimentary deposits not included in the regular mapping of unconsolidated Quaternary deposits within the site investigation programme. Samples were also collected for laboratory analyses of grain size distribution, mineralogical composition as well as the total content of C, N and S and calcium carbonate. The analyses will be carried out on selected samples of representative sedimentary units in order to characterise the chemical and physical properties of the unconsolidated deposits. The analytical data will be useful for the hydrogeological modelling and for models of the Quaternary evolution of the area. The mineralogical analyses of clay may provide information on the origin of the clay particles. One stratigraphic sequence from Lake Eckarfjaerden will be stored for later analyses, e.g. pollen analysis. This report includes field data from spring 2003. Together, the field data and the forthcoming results from the laboratory analyses will form the basis for construction of stratigraphical profiles to be presented in a following report in the fall 2003

  17. Investigating a high ozone episode in a rural mountain site

    International Nuclear Information System (INIS)

    Monteiro, A.; Strunk, A.; Carvalho, A.; Tchepel, O.; Miranda, A.I.; Borrego, C.; Saavedra, S.; Rodríguez, A.; Souto, J.; Casares, J.; Friese, E.; Elbern, H.

    2012-01-01

    A very high ozone episode with observed hourly values above 350 μg m −3 occurred in July 2005 at the Lamas d’Olo air quality monitoring station, located in a mountainous area in the north of Portugal. Aiming to identify the origin and formation of this ozone-rich episode, a statistical analysis and a modelling approach were applied. A cross-spectrum analysis in the frequency domain and a synoptic analysis of the meteorological and air quality time series were performed. In order to go further in this analysis, a numerical modelling approach was applied. The results indicate that the transport of ozone and its precursors is the main responsible for the high ozone concentrations. Together with the local mountain breeze and subsidence conditions, the sea-breeze circulation transporting pollutants from the coastal urban and industrialized areas that reach the site during late afternoon turn out to be the driving forces for the ozone peaks. - Highlights: ► A very high ozone episode occurred in a rural mountain site of Portugal in 2004. ► Data cross-spectrum analysis in the frequency domain was performed. ► A numerical modelling approach was also applied. ► The sea-breeze circulation transported pollutants from the urban and industrialized coast. ► The mountain breeze and subsidence conditions were also driving forces for ozone peaks. - The sea-breeze transporting pollutants from the coast, the mountain breeze and subsidence conditions, were the driving forces for the ozone episode occurred in a rural mountain site.

  18. Integrated site investigation procedure for environment protection toward sustainable development

    International Nuclear Information System (INIS)

    Omar, R C; Roslan, R; Baharuddin, I N Z

    2013-01-01

    The spatial configuration of cities and their relationship to the urban environment has recently been the subject of empirical, theoretical and policy research. An awareness of environmental issues can assist policy makers, planners, developers and others to recognize the constraints imposed upon development due the physical environment especially in areas, which are susceptible to erosion, flooding and landslide. This paper highlights the key requirements for considering an assessment to protect our urban environment by incorporating three main factor i.e. policy practice, planning process and engineering investigation. Base on this three main factor the framework of the assessment is carried out. The assessment can be divided into three different categories, namely as investigation for planning, investigation for urban development and specialized investigation and mitigation. The minimum requirements for the planning and urban development investigation are listed. These guidelines suggest the level at which the various types of investigation should be carried out as well as the range of application, the scope and methodology to be used for different investigation. It is hoped that this procedure will provide guidance in the establishment and protection of urban ecosystem toward sustainable development.

  19. Streamlining environmental product declarations: a stage model

    Science.gov (United States)

    Lefebvre, Elisabeth; Lefebvre, Louis A.; Talbot, Stephane; Le Hen, Gael

    2001-02-01

    General public environmental awareness and education is increasing, therefore stimulating the demand for reliable, objective and comparable information about products' environmental performances. The recently published standard series ISO 14040 and ISO 14025 are normalizing the preparation of Environmental Product Declarations (EPDs) containing comprehensive information relevant to a product's environmental impact during its life cycle. So far, only a few environmentally leading manufacturing organizations have experimented the preparation of EPDs (mostly from Europe), demonstrating its great potential as a marketing weapon. However the preparation of EPDs is a complex process, requiring collection and analysis of massive amounts of information coming from disparate sources (suppliers, sub-contractors, etc.). In a foreseeable future, the streamlining of the EPD preparation process will require product manufacturers to adapt their information systems (ERP, MES, SCADA) in order to make them capable of gathering, and transmitting the appropriate environmental information. It also requires strong functional integration all along the product supply chain in order to ensure that all the information is made available in a standardized and timely manner. The goal of the present paper is two fold: first to propose a transitional model towards green supply chain management and EPD preparation; second to identify key technologies and methodologies allowing to streamline the EPD process and subsequently the transition toward sustainable product development

  20. WAG 2 remedial investigation and site investigation site-specific work plan/health and safety checklist for the sediment transport modeling task

    International Nuclear Information System (INIS)

    Holt, V.L.; Baron, L.A.

    1994-05-01

    This site-specific Work Plan/Health and Safety Checklist (WP/HSC) is a supplement to the general health and safety plan (HASP) for Waste Area Grouping (WAG) 2 remedial investigation and site investigation (WAG 2 RI ampersand SI) activities [Health and Safety Plan for the Remedial Investigation and Site Investigation of Waste Area Grouping 2 at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (ORNL/ER-169)] and provides specific details and requirements for the WAG 2 RI ampersand SI Sediment Transport Modeling Task. This WP/HSC identifies specific site operations, site hazards, and any recommendations by Oak Ridge National Laboratory (ORNL) health and safety organizations [i.e., Industrial Hygiene (IH), Health Physics (HP), and/or Industrial Safety] that would contribute to the safe completion of the WAG 2 RI ampersand SI. Together, the general HASP for the WAG 2 RI ampersand SI (ORNL/ER-169) and the completed site-specific WP/HSC meet the health and safety planning requirements specified by 29 CFR 1910.120 and the ORNL Hazardous Waste Operations and Emergency Response (HAZWOPER) Program Manual. In addition to the health and safety information provided in the general HASP for the WAG 2 RI ampersand SI, details concerning the site-specific task are elaborated in this site-specific WP/HSC, and both documents, as well as all pertinent procedures referenced therein, will be reviewed by all field personnel prior to beginning operations

  1. Self streamlining wind tunnel: Further low speed testing and final design studies for the transonic facility

    Science.gov (United States)

    Wolf, S. W. D.

    1978-01-01

    Work was continued with the low speed self streamlining wind tunnel (SSWT) using the NACA 0012-64 airfoil in an effort to explain the discrepancies between the NASA Langley low turbulence pressure tunnel (LTPT) and SSWT results obtained with the airfoil stalled. Conventional wind tunnel corrections were applied to straight wall SSWT airfoil data, to illustrate the inadequacy of standard correction techniques in circumstances of high blockage. Also one SSWT test was re-run at different air speeds to investigate the effects of such changes (perhaps through changes in Reynold's number and freestream turbulence levels) on airfoil data and wall contours. Mechanical design analyses for the transonic self-streamlining wind tunnel (TSWT) were completed by the application of theoretical airfoil flow field data to the elastic beam and streamline analysis. The control system for the transonic facility, which will eventually allow on-line computer operation of the wind tunnel, was outlined.

  2. Strategies for ensuring quality data from Indian investigational sites

    Directory of Open Access Journals (Sweden)

    Antal K Hajos

    2011-01-01

    Full Text Available The topic of ensuring quality and compliance is and must be a top priority in the conduct of clinical trials, as warranted by regulatory guidelines as well as the inherent responsibility of the professionals conducting such research. Fast-growing emerging clinical geographies such as India demand special attention due to rapid growth and associated factors that may put study quality at risk. In this paper, we used the basic principle of PDCA (Plan, Do, Check, and Adjust to structure the processes of a clinical trial from protocol to final analysis in order to highlight the interactive nature of involved people and processes required to ensure quality of data and site functioning.

  3. Unsaturated zone investigation at the radioactive waste storage facility site

    Energy Technology Data Exchange (ETDEWEB)

    Skuratovic, Zana; Mazeika, Jonas; Petrosius, Rimantas; Jakimaviciute-Maseliene, Vaidote [Nature Research Centre, Akademijos St. 2, LT-08412, Vilnius (Lithuania); Klizas, Petras; Mokrik, Robert [Vilnius University, M.K. Ciurlionio St. 21/27, LT-03101 Vilnius (Lithuania)

    2014-07-01

    Unsaturated zone is an important part of water circulation cycle and an integral part of many hydrological and hydrogeological factors and processes. The soils of unsaturated zone are regarded as the first natural barrier to a large extent able to limit the spread of contaminants. Nuclear waste disposal site (Maisiagala radioactive waste storage facility site) was analysed in terms of the moisture movement through the unsaturated zone. Extensive data sets of the hydraulic properties, water content and isotope composition have been collected and summarized. The main experimental and observational tasks included the collection of soil samples; determination of the physical properties and the hydraulic conductivity values of soil samples, moisture extraction from the soil sample for isotopic studies; observation of the groundwater dynamics at the Maisiagala piezometer; groundwater sampling for isotopic analysis ({sup 3}H, {sup 18}O/{sup 16}O, {sup 2}H/{sup 1}H ); and monthly precipitation isotopic analysis. Distribution features of globally widespread radionuclide tritium ({sup 3}H) and the water molecule tracer isotopes in precipitation, unsaturated zone soil moisture profiles and groundwater were determined. It was used the well-known unsaturated flow and transport model of HYDRUS-1D (Simunek et al., 2008). In this study, van Genuchten equations for the retention and conductivity estimations have been used. The retention characteristics and van Genuchten model parameters were estimated internally by HYDRUS based on the empirical equations involved in the program. Basic inputs of the tritium transport simulation are the tritium input function and meteorological variables (precipitation and potential evapotranspiration). In order to validate the representativeness of the hydraulic parameters, the model has been used to estimate the tritium distribution in the unsaturated zone, which properly represents the dynamics of the unsaturated zone. The uniformity of the daily

  4. Available climatological and oceanographical data for site investigation program

    International Nuclear Information System (INIS)

    Lindell, S.; Ambjoern, C.; Juhlin, B.; Larsson-McCann, S.; Lindquist, K.

    2000-03-01

    Information on available data, measurements and models for climate, meteorology, hydrology and oceanography for six communities have been analysed and studied. The six communities are Nykoeping, Oesthammar, Oskarshamn, Tierp, Hultsfred and Aelvkarleby all of them selected by Svensk Kaernbraenslehantering AB, SKB, for a pre-study on possibilities for deep disposal of used nuclear fuel. For each of them a thorough and detailed register of available climatological data together with appropriate statistical properties are listed. The purpose is to compare the six communities concerning climatological and oceanographical data available and analyse the extent of new measurements or model applications needed for all of the selected sites. Statistical information on precipitation, temperature and runoff has good coverage in all of the six communities. If new information concerning any of these variables is needed in sites where no data collection exist today new installation can be made. Data on precipitation in form of snow and days with snow coverage is also available but to a lesser extent. This concerns also days with ground frost and average ground frost level where there is no fully representation of data. If more information is wanted concerning these variables new measurements or model calculations must be initiated. Data on freeze and break-up of ice on lakes is also insufficient but this variable can be calculated with good result by use of one-dimensional models. Data describing air pressure tendency and wind velocity and direction is available for all communities and this information should be sufficient for the purpose of SKB. This is also valid for the variables global radiation and duration of sunshine where no new data should be needed. Measured data on evaporation is normally not available in Sweden more than in special research basins. Actual evaporation is though a variable that easily can be calculated by use of models. There are many lakes in the six

  5. Available climatological and oceanographical data for site investigation program

    Energy Technology Data Exchange (ETDEWEB)

    Lindell, S.; Ambjoern, C.; Juhlin, B.; Larsson-McCann, S.; Lindquist, K. [Swedish Meteorological and Hydrological Inst., Norrkoeping (Sweden)

    2000-03-15

    Information on available data, measurements and models for climate, meteorology, hydrology and oceanography for six communities have been analysed and studied. The six communities are Nykoeping, Oesthammar, Oskarshamn, Tierp, Hultsfred and Aelvkarleby all of them selected by Svensk Kaernbraenslehantering AB, SKB, for a pre-study on possibilities for deep disposal of used nuclear fuel. For each of them a thorough and detailed register of available climatological data together with appropriate statistical properties are listed. The purpose is to compare the six communities concerning climatological and oceanographical data available and analyse the extent of new measurements or model applications needed for all of the selected sites. Statistical information on precipitation, temperature and runoff has good coverage in all of the six communities. If new information concerning any of these variables is needed in sites where no data collection exist today new installation can be made. Data on precipitation in form of snow and days with snow coverage is also available but to a lesser extent. This concerns also days with ground frost and average ground frost level where there is no fully representation of data. If more information is wanted concerning these variables new measurements or model calculations must be initiated. Data on freeze and break-up of ice on lakes is also insufficient but this variable can be calculated with good result by use of one-dimensional models. Data describing air pressure tendency and wind velocity and direction is available for all communities and this information should be sufficient for the purpose of SKB. This is also valid for the variables global radiation and duration of sunshine where no new data should be needed. Measured data on evaporation is normally not available in Sweden more than in special research basins. Actual evaporation is though a variable that easily can be calculated by use of models. There are many lakes in the six

  6. Streamline topologies near simple degenerate critical points in two-dimensional flow away from boundaries

    DEFF Research Database (Denmark)

    Brøns, Morten; Hartnack, Johan Nicolai

    1998-01-01

    Streamline patterns and their bifurcations in two-dimensional incompressible flow are investigated from a topological point of view. The velocity field is expanded at a point in the fluid, and the expansion coefficients are considered as bifurcation parameters. A series of non-linear coordinate c...

  7. Streamline topologies near simple degenerate critical points in two-dimensional flow away from boundaries

    DEFF Research Database (Denmark)

    Brøns, Morten; Hartnack, Johan Nicolai

    1999-01-01

    Streamline patterns and their bifurcations in two-dimensional incompressible flow are investigated from a topological point of view. The velocity field is expanded at a point in the fluid, and the expansion coefficients are considered as bifurcation parameters. A series of nonlinear coordinate ch...

  8. Investigation of user behavior on social networking sites.

    Science.gov (United States)

    Waheed, Hajra; Anjum, Maria; Rehman, Mariam; Khawaja, Amina

    2017-01-01

    Social networking sites (SNS) are used for social and professional interaction with people. SNS popularity has encouraged researchers to analyze the relationship of activities performed on SNS with user behavior. In doing so, the term "user behavior" is rather used ambiguously with different interpretations, which makes it difficult to identify studies on user behavior in relation to SNS. This phenomenon has encouraged this thorough research on the characteristics of user behavior being discussed in the literature. Therefore, in this study, we aim to identify, analyze, and classify the characteristics associated with user behavior to answer the research questions designed to conduct this research. A mapping study (also called scoping study), which is a type of systematic literature review, is employed to identify potential studies from digital databases through a developed protocol. Thematic analysis is carried out for the classification of user behavior. We identified 116 primary studies for full analysis. This study found seven characteristics associated with behavior that have direct influence on SNS use and nine factors that have an indirect effect. All studies were conducted largely under seven areas that set the context of these studies. Findings show that the research on SNS is still in its early stage. The range of topics covered in the analyzed studies is quite expansive, although the depth in terms of number of studies under each topic is quite limited. This study reports that activities performed on SNS are either associated with user behavior or reflect personality characteristics. The findings of this study could be used by practitioners to evaluate their SNS platforms and develop more user-centered applications. These studies can also help organizations to understand better the needs of their employees.

  9. Investigation of user behavior on social networking sites.

    Directory of Open Access Journals (Sweden)

    Hajra Waheed

    Full Text Available Social networking sites (SNS are used for social and professional interaction with people. SNS popularity has encouraged researchers to analyze the relationship of activities performed on SNS with user behavior. In doing so, the term "user behavior" is rather used ambiguously with different interpretations, which makes it difficult to identify studies on user behavior in relation to SNS. This phenomenon has encouraged this thorough research on the characteristics of user behavior being discussed in the literature. Therefore, in this study, we aim to identify, analyze, and classify the characteristics associated with user behavior to answer the research questions designed to conduct this research. A mapping study (also called scoping study, which is a type of systematic literature review, is employed to identify potential studies from digital databases through a developed protocol. Thematic analysis is carried out for the classification of user behavior. We identified 116 primary studies for full analysis. This study found seven characteristics associated with behavior that have direct influence on SNS use and nine factors that have an indirect effect. All studies were conducted largely under seven areas that set the context of these studies. Findings show that the research on SNS is still in its early stage. The range of topics covered in the analyzed studies is quite expansive, although the depth in terms of number of studies under each topic is quite limited. This study reports that activities performed on SNS are either associated with user behavior or reflect personality characteristics. The findings of this study could be used by practitioners to evaluate their SNS platforms and develop more user-centered applications. These studies can also help organizations to understand better the needs of their employees.

  10. In Silico Investigation of the Neurotensin Receptor 1 Binding Site

    DEFF Research Database (Denmark)

    Lückmann, Michael; Holst, Birgitte; Schwartz, Thue W.

    2016-01-01

    structure of NTSR1 in complex with NTS8-13 has been detd., providing novel insights into peptide ligand recognition by 7TM receptors. SR48692, a potent and selective small mol. antagonist has previously been used extensively as a tool compd. to study NTSR1 receptor signaling properties. To investigate......The neurotensin receptor 1 (NTSR1) belongs to the family of 7TM, G protein-coupled receptors, and is activated by the 13-amino-acid peptide neurotensin (NTS) that has been shown to play important roles in neurol. disorders and the promotion of cancer cells. Recently, a high-resoln. x-ray crystal...

  11. Quantum mechanical streamlines. I - Square potential barrier

    Science.gov (United States)

    Hirschfelder, J. O.; Christoph, A. C.; Palke, W. E.

    1974-01-01

    Exact numerical calculations are made for scattering of quantum mechanical particles hitting a square two-dimensional potential barrier (an exact analog of the Goos-Haenchen optical experiments). Quantum mechanical streamlines are plotted and found to be smooth and continuous, to have continuous first derivatives even through the classical forbidden region, and to form quantized vortices around each of the nodal points. A comparison is made between the present numerical calculations and the stationary wave approximation, and good agreement is found between both the Goos-Haenchen shifts and the reflection coefficients. The time-independent Schroedinger equation for real wavefunctions is reduced to solving a nonlinear first-order partial differential equation, leading to a generalization of the Prager-Hirschfelder perturbation scheme. Implications of the hydrodynamical formulation of quantum mechanics are discussed, and cases are cited where quantum and classical mechanical motions are identical.

  12. A streamlined failure mode and effects analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ford, Eric C., E-mail: eford@uw.edu; Smith, Koren; Terezakis, Stephanie; Croog, Victoria; Gollamudi, Smitha; Gage, Irene; Keck, Jordie; DeWeese, Theodore; Sibley, Greg [Department of Radiation Oncology and Molecular Radiation Sciences, Johns Hopkins University, Baltimore, MD 21287 (United States)

    2014-06-15

    Purpose: Explore the feasibility and impact of a streamlined failure mode and effects analysis (FMEA) using a structured process that is designed to minimize staff effort. Methods: FMEA for the external beam process was conducted at an affiliate radiation oncology center that treats approximately 60 patients per day. A structured FMEA process was developed which included clearly defined roles and goals for each phase. A core group of seven people was identified and a facilitator was chosen to lead the effort. Failure modes were identified and scored according to the FMEA formalism. A risk priority number,RPN, was calculated and used to rank failure modes. Failure modes with RPN > 150 received safety improvement interventions. Staff effort was carefully tracked throughout the project. Results: Fifty-two failure modes were identified, 22 collected during meetings, and 30 from take-home worksheets. The four top-ranked failure modes were: delay in film check, missing pacemaker protocol/consent, critical structures not contoured, and pregnant patient simulated without the team's knowledge of the pregnancy. These four failure modes hadRPN > 150 and received safety interventions. The FMEA was completed in one month in four 1-h meetings. A total of 55 staff hours were required and, additionally, 20 h by the facilitator. Conclusions: Streamlined FMEA provides a means of accomplishing a relatively large-scale analysis with modest effort. One potential value of FMEA is that it potentially provides a means of measuring the impact of quality improvement efforts through a reduction in risk scores. Future study of this possibility is needed.

  13. Streamlining the license renewal review process

    International Nuclear Information System (INIS)

    Dozier, J.; Lee, S.; Kuo, P.T.

    2001-01-01

    The staff of the NRC has been developing three regulatory guidance documents for license renewal: the Generic Aging Lessons Learned (GALL) report, Standard Review Plan for License Renewal (SRP-LR), and Regulatory Guide (RG) for Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses. These documents are designed to streamline the license renewal review process by providing clear guidance for license renewal applicants and the NRC staff in preparing and reviewing license renewal applications. The GALL report systematically catalogs aging effects on structures and components; identifies the relevant existing plant programs; and evaluates the existing programs against the attributes considered necessary for an aging management program to be acceptable for license renewal. The GALL report also provides guidance for the augmentation of existing plant programs for license renewal. The revised SRP-LR allows an applicant to reference the GALL report to preclude further NRC staff evaluation if the plant's existing programs meet the criteria described in the GALL report. During the review process, the NRC staff will focus primarily on existing programs that should be augmented or new programs developed specifically for license renewal. The Regulatory Guide is expected to endorse the Nuclear Energy Institute (NEI) guideline, NEI 95-10, Revision 2, entitled 'Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule', which provides guidance for preparing a license renewal application. This paper will provide an introduction to the GALL report, SRP-LR, Regulatory Guide, and NEI 95-10 to show how these documents are interrelated and how they will be used to streamline the license renewal review process. This topic will be of interest to domestic power utilities considering license renewal and international ICONE participants seeking state-of-the-art information about license renewal in the United States

  14. A streamlined failure mode and effects analysis

    International Nuclear Information System (INIS)

    Ford, Eric C.; Smith, Koren; Terezakis, Stephanie; Croog, Victoria; Gollamudi, Smitha; Gage, Irene; Keck, Jordie; DeWeese, Theodore; Sibley, Greg

    2014-01-01

    Purpose: Explore the feasibility and impact of a streamlined failure mode and effects analysis (FMEA) using a structured process that is designed to minimize staff effort. Methods: FMEA for the external beam process was conducted at an affiliate radiation oncology center that treats approximately 60 patients per day. A structured FMEA process was developed which included clearly defined roles and goals for each phase. A core group of seven people was identified and a facilitator was chosen to lead the effort. Failure modes were identified and scored according to the FMEA formalism. A risk priority number,RPN, was calculated and used to rank failure modes. Failure modes with RPN > 150 received safety improvement interventions. Staff effort was carefully tracked throughout the project. Results: Fifty-two failure modes were identified, 22 collected during meetings, and 30 from take-home worksheets. The four top-ranked failure modes were: delay in film check, missing pacemaker protocol/consent, critical structures not contoured, and pregnant patient simulated without the team's knowledge of the pregnancy. These four failure modes hadRPN > 150 and received safety interventions. The FMEA was completed in one month in four 1-h meetings. A total of 55 staff hours were required and, additionally, 20 h by the facilitator. Conclusions: Streamlined FMEA provides a means of accomplishing a relatively large-scale analysis with modest effort. One potential value of FMEA is that it potentially provides a means of measuring the impact of quality improvement efforts through a reduction in risk scores. Future study of this possibility is needed

  15. A streamlined failure mode and effects analysis.

    Science.gov (United States)

    Ford, Eric C; Smith, Koren; Terezakis, Stephanie; Croog, Victoria; Gollamudi, Smitha; Gage, Irene; Keck, Jordie; DeWeese, Theodore; Sibley, Greg

    2014-06-01

    Explore the feasibility and impact of a streamlined failure mode and effects analysis (FMEA) using a structured process that is designed to minimize staff effort. FMEA for the external beam process was conducted at an affiliate radiation oncology center that treats approximately 60 patients per day. A structured FMEA process was developed which included clearly defined roles and goals for each phase. A core group of seven people was identified and a facilitator was chosen to lead the effort. Failure modes were identified and scored according to the FMEA formalism. A risk priority number,RPN, was calculated and used to rank failure modes. Failure modes with RPN > 150 received safety improvement interventions. Staff effort was carefully tracked throughout the project. Fifty-two failure modes were identified, 22 collected during meetings, and 30 from take-home worksheets. The four top-ranked failure modes were: delay in film check, missing pacemaker protocol/consent, critical structures not contoured, and pregnant patient simulated without the team's knowledge of the pregnancy. These four failure modes had RPN > 150 and received safety interventions. The FMEA was completed in one month in four 1-h meetings. A total of 55 staff hours were required and, additionally, 20 h by the facilitator. Streamlined FMEA provides a means of accomplishing a relatively large-scale analysis with modest effort. One potential value of FMEA is that it potentially provides a means of measuring the impact of quality improvement efforts through a reduction in risk scores. Future study of this possibility is needed.

  16. Investigation of the site selection examples adopted local participation. The site selection processes in Belgium, UK and Switzerland

    International Nuclear Information System (INIS)

    Kageyama, Hitoshi; Suzuki, Shinji; Hirose, Ikuro; Yoshioka, Tatsuji

    2014-06-01

    In late years, local participation policies are being adopted in foreign countries at site selection for the disposal of the radioactive waste. We performed documents investigation about the examples of the site selection processes of Belgium, the U.K., and Switzerland to establish the site selection policy in Japan. In Belgium, after the failure of the site selection for the disposal of short-lived low and intermediate level radioactive waste (LILW) in an early stage, the idea of the local partnership (LP) was developed and three independent LPs were established between the implementing body and each municipality. About 7 years later, one site was decided as the disposal site in the cabinet meeting of the federal government. In the U.K., after the failure of the site selection for the rock characterization facility, the government policy was changed and the consultation process comprised of six phases was started. Though the process had been carried out for over 4 years since one combined partnership was established between the implementing body and the municipalities involved, they had to withdraw from the consulting process because a county council had not accepted that the process would step forward to the 4th phase. In Switzerland, the implementing body selected one site for LILW disposal at an early stage, but the project was denied by the referendum in the Canton having jurisdiction over the site area. After that the Federal Parliament established new Nuclear Energy Act and Nuclear Energy Ordinance precluding the veto of Canton. Now the site selection project is being carried out according to the process comprised of three phases with local participation policy. Reviewing the merits and demerits of each example through this investigation, we confirmed if we are to adopt local participation policy in our country in future, further prudent study would be necessary, considering current and future social conditions in Japan. (author)

  17. Field site investigation: Effect of mine seismicity on groundwater hydrology

    International Nuclear Information System (INIS)

    Ofoegbu, G.I.; Hsiung, S.; Chowdhury, A.H.

    1995-04-01

    The results of a field investigation on the groundwater-hydrologic effect of mining-induced earthquakes are presented in this report. The investigation was conducted at the Lucky Friday Mine, a silver-lead-zinc mine in the Coeur d'Alene Mining District of Idaho. The groundwater pressure in sections of three fracture zones beneath the water table was monitored over a 24-mo period. The fracture zones were accessed through a 360-m-long inclined borehole, drilled from the 5,700 level station of the mine. The magnitude, source location, and associated ground motions of mining-induced seismic events were also monitored during the same period, using an existing seismic instrumentation network for the mine, augmented with additional instruments installed specifically for the project by the center for Nuclear Waste Regulatory Analyses (CNWRA). More than 50 seismic events of Richter magnitude 1.0 or larger occurred during the monitoring period. Several of these events caused the groundwater pressure to increase, whereas a few caused it to decrease. Generally, the groundwater pressure increased as the magnitude of seismic event increased; for an event of a given magnitude, the groundwater pressure increased by a smaller amount as the distance of the observation point from the source of the event increased. The data was examined using regression analysis. Based on these results, it is suggested that the effect of earthquakes on groundwater flow may be better understood through mechanistic modeling. The mechanical processes and material behavior that would need to be incorporated in such a model are examined. They include a description of the effect of stress change on the permeability and water storage capacity of a fracture rock mass; transient fluid flow; and the generation and transmission of seismic waves through the rock mass

  18. Corrective Action Investigation Plan for Corrective Action Unit 554: Area 23 Release Site, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Boehlecke, Robert F.

    2004-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 554: Area 23 Release Site, Nevada Test Site, Nevada. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental samples. Corrective Action Unit 554 is located in Area 23 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 554 is comprised of one Corrective Action Site (CAS), which is: 23-02-08, USTs 23-115-1, 2, 3/Spill 530-90-002. This site consists of soil contamination resulting from a fuel release from underground storage tanks (USTs). Corrective Action Site 23-02-08 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation prior to evaluating corrective action alternatives and selecting the appropriate corrective action for this CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document for CAU 554. Corrective Action Site 23-02-08 will be investigated based on the data quality objectives (DQOs) developed on July 15, 2004, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; and contractor personnel. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 554. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to CAS 23-02-08. The scope of the corrective action investigation

  19. Volatile Organic Compound Investigation Results, 300 Area, Hanford Site, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Robert E.; Williams, Bruce A.; Smith, Ronald M.

    2008-07-07

    Unexpectedly high concentrations of volatile organic compounds (VOC) were discovered while drilling in the unconfined aquifer beneath the Hanford Site’s 300 Area during 2006. The discovery involved an interval of relatively finer-grained sediment within the unconfined aquifer, an interval that is not sampled by routine groundwater monitoring. Although VOC contamination in the unconfined aquifer has been identified and monitored, the concentrations of newly discovered contamination are much higher than encountered previously, with some new results significantly higher than the drinking water standards. The primary contaminant is trichloroethene, with lesser amounts of tetrachloroethene. Both chemicals were used extensively as degreasing agents during the fuels fabrication process. A biological degradation product of these chemicals, 1,2-dichloroethene, was also detected. To further define the nature and extent of this contamination, additional characterization drilling was undertaken during 2007. Four locations were drilled to supplement the information obtained at four locations drilled during the earlier investigation in 2006. The results of the combined drilling indicate that the newly discovered contamination is limited to a relatively finer-grained interval of Ringold Formation sediment within the unconfined aquifer. The extent of this contamination appears to be the area immediately east and south of the former South Process Pond. Samples collected from the finer-grained sediment at locations along the shoreline confirm the presence of the contamination near the groundwater/river interface. Contamination was not detected in river water that flows over the area where the river channel potentially incises the finer-grained interval of aquifer sediment. The source for this contamination is not readily apparent. A search of historical documents and the Hanford Waste Information Data System did not provide definitive clues as to waste disposal operations and

  20. 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

  1. 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

  2. Corrective Action Investigation Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    Grant Evenson

    2006-04-01

    Corrective Action Unit (CAU) 139 is located in Areas 3, 4, 6, and 9 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 139 is comprised of the seven corrective action sites (CASs) listed below: (1) 03-35-01, Burn Pit; (2) 04-08-02, Waste Disposal Site; (3) 04-99-01, Contaminated Surface Debris; (4) 06-19-02, Waste Disposal Site/Burn Pit; (5) 06-19-03, Waste Disposal Trenches; (6) 09-23-01, Area 9 Gravel Gertie; and (7) 09-34-01, Underground Detection Station. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives with the exception of CASs 09-23-01 and 09-34-01. Regarding these two CASs, CAS 09-23-01 is a gravel gertie where a zero-yield test was conducted with all contamination confined to below ground within the area of the structure, and CAS 09-34-01 is an underground detection station where no contaminants are present. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for the other five CASs where information is insufficient. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 4, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 139.

  3. WAG 2 remedial investigation and site investigation site-specific work plan/health and safety checklist for the soil and sediment task

    International Nuclear Information System (INIS)

    Holt, V.L.; Burgoa, B.B.

    1993-12-01

    This document is a site-specific work plan/health and safety checklist (WP/HSC) for a task of the Waste Area Grouping 2 Remedial Investigation and Site Investigation (WAG 2 RI ampersand SI). Title 29 CFR Part 1910.120 requires that a health and safety program plan that includes site- and task-specific information be completed to ensure conformance with health- and safety-related requirements. To meet this requirement, the health and safety program plan for each WAG 2 RI ampersand SI field task must include (1) the general health and safety program plan for all WAG 2 RI ampersand SI field activities and (2) a WP/HSC for that particular field task. These two components, along with all applicable referenced procedures, must be kept together at the work site and distributed to field personnel as required. The general health and safety program plan is the Health and Safety Plan for the Remedial Investigation and Site Investigation of Waste Area Grouping 2 at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (ORNL/ER-169). The WP/HSCs are being issued as supplements to ORNL/ER-169

  4. Verification study on technology for site investigation for geological disposal. Confirmation of the applicability of survey methods through establishing site descriptive models in accordance with stepwise investigation approach

    International Nuclear Information System (INIS)

    Kondo, Hirofumi; Suzuki, Koichi; Hasegawa, Takuma; Hamada, Takaomi; Yoshimura, Kimitaka

    2014-01-01

    The Yokosuka Demonstration and Validation Project, which uses the Yokosuka Central Research Institute of Electric Power Industry (CRIEPI) site, a Neogene sedimentary and coastal environment, has been conducted since the 2006 fiscal year as a cooperative research project between NUMO (Nuclear Waste Management Organization of Japan) and CRIEPI. The objectives of this project were to examine and refine the basic methodology of the investigation and assessment in accordance with the conditions of geological environment at each stage of investigations from the surface (Preliminary Investigation and the first half of Detailed Investigation conducted by NUMO) for high level radioactive waste geological disposal. Within investigation technologies at these early stages, a borehole survey is an important means of directly obtaining various properties of the deep geological environment. On the other hand, surface geophysical prospecting data provide information about the geological and resistivity structures at depth for planning borehole surveys. During the 2006-2009 fiscal years, a series of on-site surveys and tests, including borehole surveys of YDP-1 (depth: 350 m) and YDP-2 (depth: 500 m), were conducted in this test site. Furthermore, seismic surveys (including seismic reflection method) and electromagnetic surveys (including magnetotelluric method) were conducted within the expanded CRIEPI site in the 2010 fiscal year to obtain information about the geological structure, and the resistivity structure reflecting the distribution of the salt water/fresh water boundary, respectively, to a depth of over several hundred meters. The validity of existing survey and testing methods for stepwise investigations (from surface to borehole surveys) for obtaining properties of the geological environment (in various conditions relating to differences in the properties of the Miura and the Hayama Groups at this site) was confirmed through establishing site descriptive models based on

  5. Development of the web-based site investigation flow diagram in repository development program

    International Nuclear Information System (INIS)

    Yamamoto, Shuichi; Yoshimura, Kimitaka; Ohuchi, Jin; Tsuboya, Takao; Ando, Kenichi

    2005-01-01

    In siting a repository for high level radioactive wastes (HLW), it is essential for consensus building intelligibly and visually present why and how the area is selected as a suitable site. However 'information asymmetry' exists especially between society and an implementation body because various types of investigation, analysis and assessment are implemented in site characterization on the basis of a wide variety of advanced science and technology. Communication between experts (e.g. surveyors and modelers) is also important for efficient and reliable site investigation/ characterization. The Web-based Site Investigation Flow Diagram (SIFD) has been developed as a tool for information sharing among stake holders and society-jointed decision making. To test applicability of the SIFD, virtual site characterization ('dry run') is performed using the existing site investigation data. It is concluded that the web-based SIFD enhance traceability and transparency of the site investigation/ characterization, and therefore it would be a powerful communication tool among experts for efficient and reliable site investigation/characterization and among stake holders for consensus building

  6. Site investigations for repositories for solid radioactive wastes in shallow ground

    International Nuclear Information System (INIS)

    1982-01-01

    This report provides an overview and technical guidelines for investigations on a national level for the selection and confirmation of a repository site that will provide adequately safe performance for disposal of solid radioactive wastes that are low- or intermediate-level and short-lived. It also provides basic information on technical activities to be undertaken and on techniques that are available for such investigations in the various steps in selecting suitable sites. The report supplements the information given in Shallow Ground Disposal of Radioactive Wastes: A Guidebook, IAEA Safety Series No. 53 (1981). This report focuses mainly on different aspects of earth sciences and the various investigative techniques relative to earth sciences that may be necessary for site investigations. Some major related studies in other fields are discussed briefly. It is assumed that no previous investigations have been undertaken, and the report proceeds through area site selection to the stage when the site is confirmed as suitable for a waste repository

  7. “Doing the Wrong Things Right” Site Investigations in Soft Soil

    Science.gov (United States)

    Jamilus, M. H.; Lim, A. J. M. S.; Azhar, A. T. S.; Azmi, M. A. M.

    2016-11-01

    Site investigation is a very important process by which geotechnical, geological and other relevant information which might affect the construction or performance of a civil engineering or building project is acquired. However, common practice in site investigations is not always in accordance to the standard that has been defined. Reliability on the information obtained depends upon several factors that involves correct procedures and competent workers and also supervision. Several examples on site investigation methods are discussed in this paper. Explanation on the difference between the site investigation methods used for real practices in the field and how it should be done are discussed in detail. Therefore, it is hoped that site investigation should always be uniquely planned and should be an interactive and flexible process of discovery and changes according to the condition of the soil.

  8. Site investigations for repositories for solid radioactive wastes in shallow ground

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    This report provides an overview and technical guidelines for investigations on a national level for the selection and confirmation of a repository site that will provide adequately safe performance for disposal of solid radioactive wastes that are low- or intermediate-level and short-lived. It also provides basic information on technical activities to be undertaken and on techniques that are available for such investigations in the various steps in selecting suitable sites. The report supplements the information given in Shallow Ground Disposal of Radioactive Wastes: A Guidebook, IAEA Safety Series No. 53 (1981). This report focuses mainly on different aspects of earth sciences and the various investigative techniques relative to earth sciences that may be necessary for site investigations. Some major related studies in other fields are discussed briefly. It is assumed that no previous investigations have been undertaken, and the report proceeds through area site selection to the stage when the site is confirmed as suitable for a waste repository.

  9. Streamlining cardiovascular clinical trials to improve efficiency and generalisability.

    Science.gov (United States)

    Zannad, Faiez; Pfeffer, Marc A; Bhatt, Deepak L; Bonds, Denise E; Borer, Jeffrey S; Calvo-Rojas, Gonzalo; Fiore, Louis; Lund, Lars H; Madigan, David; Maggioni, Aldo Pietro; Meyers, Catherine M; Rosenberg, Yves; Simon, Tabassome; Stough, Wendy Gattis; Zalewski, Andrew; Zariffa, Nevine; Temple, Robert

    2017-08-01

    Controlled trials provide the most valid determination of the efficacy and safety of an intervention, but large cardiovascular clinical trials have become extremely costly and complex, making it difficult to study many important clinical questions. A critical question, and the main objective of this review, is how trials might be simplified while maintaining randomisation to preserve scientific integrity and unbiased efficacy assessments. Experience with alternative approaches is accumulating, specifically with registry-based randomised controlled trials that make use of data already collected. This approach addresses bias concerns while still capitalising on the benefits and efficiencies of a registry. Several completed or ongoing trials illustrate the feasibility of using registry-based controlled trials to answer important questions relevant to daily clinical practice. Randomised trials within healthcare organisation databases may also represent streamlined solutions for some types of investigations, although data quality (endpoint assessment) is likely to be a greater concern in those settings. These approaches are not without challenges, and issues pertaining to informed consent, blinding, data quality and regulatory standards remain to be fully explored. Collaboration among stakeholders is necessary to achieve standards for data management and analysis, to validate large data sources for use in randomised trials, and to re-evaluate ethical standards to encourage research while also ensuring that patients are protected. The rapidly evolving efforts to streamline cardiovascular clinical trials have the potential to lead to major advances in promoting better care and outcomes for patients with cardiovascular disease. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  10. Site investigations for final disposal of high-level nuclear waste

    International Nuclear Information System (INIS)

    Aeikaes, T.; Laine, T.

    1982-12-01

    Research concerning disposal of high-level nuclear waste of the Industrial Power Company Ltd has focused on deep underground disposal in Finnish precambrian bedrock. The present target is to have a repository for high-level waste in operation by 2020. Selection of the repository site is based on site investigations. In addition to geosciences, selection of appropriate site includes many branches of studies; engineering, safety analysis, ecology, transport, demography etc. The investigations required for site selection for high-level waste have been arranged in a sequence of four phases. The aim of the phases is that investigations become more and more detailed as the selection process continues. Phase I of the investigations is the characterization of potential areas. This comprises establishment of criteria for site selection and identification of areas that meet selection criteria. Objective of these studies is to determine areas for phase II field investigations. The studies are largely made by reviewing existing data and remote-sensing techniques. Phase II field investigations will be undertaken between 1986-1992. The number of potential candidates for repository site is reduced to few preferred areas by preceeding generic study. The site selection process culminates in phase III in site confirmation studies carried out at 2...3 most suitable sites during 1992-2010. This is then followed by phase IV, which comprises very detailed investigations at the selected site. An alternative for these investigations is to undertake them by using pilot shaft and drifts. Active development is taking place in all phases concerning investigation methods, criteria, parameters, data processing and modelling. The applicability of the various investigation methods and techniques is tested in a deep borehole in phase I. The co-operation with countries with similar geological conditions makes it possible to compare results obtained by different techniques

  11. 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

  12. WAG 2 remedial investigation and site investigation site-specific work plan/health and safety checklist for the ecological assessment task, Kingfisher Study

    International Nuclear Information System (INIS)

    Holt, V.L.; Baron, L.A.

    1994-05-01

    This report provides specific details and requirements for the WAG 2 remedial investigation and site investigation Ecological Assessment Task, Kingfisher Study, including information that will contribute to safe completion of the project. The report includes historical background; a site map; project organization; task descriptions and hazard evaluations; controls; and monitoring, personal protective equipment, decontamination, and medical surveillance program requirements. The report also includes descriptions of site personnel and their certifications as well as suspected WAG 2 contaminants and their characteristics. The primary objective of the WAG 2 Kingfisher Study is to assess the feasibility of using kingfishers as biological monitors of contaminants on the Oak Ridge Reservation (ORR). Kingfisher sample collection will be used to determine the levels of contaminants and degree of bioaccumulation within a common piscivorous bird feeding on contaminated fish from streams on the ORR

  13. WSSRAP chemical plant geotechnical investigations for the Weldon Spring Site Remedial Action Project, Weldon Spring, Missouri

    International Nuclear Information System (INIS)

    1990-12-01

    This document has been prepared for the United states Department of Energy (DOE) Weldon Spring Site Remedial Action Project (WSSRAP) by the Project Management Contractor (PMC), which consists of MK-Ferguson Company (MKF) and Morrison Knudsen Corporation Environmental Services Group (MKES) with Jacobs Engineering Group (JEG) as MKF's predesignated subcontractor. This report presents the results of site geotechnical investigations conducted by the PMC in the vicinity of the Weldon Spring chemical plant and raffinate pits (WSCP/RP) and in potential on-site and off-site clayey material borrow sources. The WSCP/RP is the proposed disposal cell (DC) site. 39 refs., 24 figs., 12 tabs

  14. SRP baseline hydrogeologic investigation: Aquifer characterization. Groundwater geochemistry of the Savannah River Site and vicinity

    Energy Technology Data Exchange (ETDEWEB)

    Strom, R.N.; Kaback, D.S.

    1992-03-31

    An investigation of the mineralogy and chemistry of the principal hydrogeologic units and the geochemistry of the water in the principal aquifers at Savannah River Site (SRS) was undertaken as part of the Baseline Hydrogeologic Investigation. This investigation was conducted to provide background data for future site studies and reports and to provide a site-wide interpretation of the geology and geochemistry of the Coastal Plain Hydrostratigraphic province. Ground water samples were analyzed for major cations and anions, minor and trace elements, gross alpha and beta, tritium, stable isotopes of hydrogen, oxygen, and carbon, and carbon-14. Sediments from the well borings were analyzed for mineralogy and major and minor elements.

  15. Confined Site Construction: A qualitative investigation of critical issues affecting management of Health and Safety

    OpenAIRE

    Spillane, John P.; Oyedele, Lukumon O.; Von Meding, Jason; Konanahalli, Ashwini; Jaiyeoba, Babatunde E.; Tijani, Iyabo K.

    2011-01-01

    The construction industry is inherently risky, with a significant number of accidents and disasters occurring, particularly on confined construction sites. This research investigates and identifies the various issues affecting successful management of health and safety in confined construction sites. The rationale is that identifying the issues would assist the management of health and safety particularly in inner city centres which are mostly confined sites. Using empiricism epistemology, th...

  16. Corrective Action Investigation Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

    International Nuclear Information System (INIS)

    Matthews, Patrick

    2011-01-01

    Corrective Action Unit 366 comprises the six corrective action sites (CASs) listed below: (1) 11-08-01, Contaminated Waste Dump No.1; (2) 11-08-02, Contaminated Waste Dump No.2; (3) 11-23-01, Radioactively Contaminated Area A; (4) 11-23-02, Radioactively Contaminated Area B; (5) 11-23-03, Radioactively Contaminated Area C; and (6) 11-23-04, Radioactively Contaminated Area D. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed July 6, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 366. The presence and nature of contamination at CAU 366 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample locations to the dose-based final action level (FAL). The TED will be calculated by summing the estimates of internal and external dose. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at each sample location will be used to measure external radiological dose. Based on historical documentation of the releases

  17. Why Do You Adopt Social Networking Sites? Investigating the Driving Factors through Structural Equation Modelling

    Science.gov (United States)

    Jan, Muhammad Tahir

    2017-01-01

    Purpose: The purpose of this paper is to investigate those factors that are associated with the adoption of social networking sites from the perspective of Muslim users residing in Malaysia. Design/methodology/approach: A complete self-administered questionnaire was collected from 223 Muslim users of social networking sites in Malaysia. Both…

  18. Sorption of radionuclides on geological samples from the Bradwell, Elstow, Fulbeck and Killingholme site investigations

    International Nuclear Information System (INIS)

    Berry, J.A.; Coates, H.A.; Green, A.; Littleboy, A.K.

    1988-06-01

    The sorption of chloride, caesium, calcium, nickel and americium on geological samples collected during the site investigations at Bradwell, Elstow, Fulbeck and Killingholme has been studied. Through-diffusion and batch sorption techniques were used and experiments were designed to give a direct comparison between the sorptive behaviour of material from each site. (author)

  19. Data Summary Report for teh Remedial Investigation of Hanford Site Releases to the Columbia River, Hanford Site, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Hulstrom, L.

    2011-02-07

    This data summary report summarizes the investigation results to evaluate the nature and distribution of Hanford Site-related contaminants present in the Columbia River. As detailed in DOE/RL-2008-11, more than 2,000 environmental samples were collected from the Columbia River between 2008 and 2010. These samples consisted of island soil, sediment, surface water, groundwater upwelling (pore water, surface water, and sediment), and fish tissue.

  20. Corrective Action Investigation Plan for Corrective Action Unit 190: Contaminated Waste Sites Nevada Test Site, Nevada, Rev. No.: 0

    International Nuclear Information System (INIS)

    Wickline, Alfred

    2006-01-01

    Corrective Action Unit (CAU) 190 is located in Areas 11 and 14 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 190 is comprised of the four Corrective Action Sites (CASs) listed below: (1) 11-02-01, Underground Centrifuge; (2) 11-02-02, Drain Lines and Outfall; (3) 11-59-01, Tweezer Facility Septic System; and (4) 14-23-01, LTU-6 Test Area. These sites are being investigated because existing information is insufficient on the nature and extent of potential contamination to evaluate and recommend corrective action alternatives. Additional information will be obtained before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS by conducting a corrective action investigation (CAI). The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on August 24, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture, and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 190. The scope of the CAU 190 CAI includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling; (2) Conduct radiological and geophysical surveys; (3) Perform field screening; (4) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present; (5) If COCs are present, collect additional step-out samples to define the lateral and vertical extent of the contamination; (6) Collect samples of source material, if present

  1. Numerical modeling and experimental investigation of the local hydrology of a porous concrete site.

    Science.gov (United States)

    2011-10-01

    Although porous pavement use has been accepted as a successful stormwater management practice in warm climates, application in regions with colder climates, like New England, is still under investigation. The Randolph Park and Ride Site, which is the...

  2. Phase 2 environmental site investigation procedures and technologies for property transfer and PS and E development

    Science.gov (United States)

    1999-05-01

    The purpose of this project is to provide TxDOT with an improved procedure for conducting environmental site investigations at various stages during transportation infrastructure development. The project seeks to identify modern assessment technologi...

  3. Case studies in geographic information systems for environmental streamlining

    Science.gov (United States)

    2012-05-31

    This 2012 summary report addresses the current use of geographic information systems (GIS) and related technologies by State Departments of Transportation (DOTs) for environmental streamlining and stewardship, particularly in relation to the National...

  4. Installation restoration program site investigation. Gulfport Field Training Site, Mississippi Air National Guard Gulfport-Biloxi Regional Airport Gulfport, Mississippi. Volume 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-01

    Site Investigation Report, Volume: 2. A Site Investigation was performed at 3 sites at the Combat Readiness Training Center, Gulfport-Bolixi. The 3 sites investigated are the: Former Fire Training Area (Site 1), the Former JP-4 Bulk Storage Area, Mill Road (Site 2), and the Motor Pool Above-Ground Diesel Fuel Storage Tank Area (Site 3). The findings of this investigation recommended further investigation at the Fire Training Area and the JP-4 Bulk Storage Tank. At Site 3 the levels of contamination did not represent a risk to human health or the environment; therefore, no further action was recommended. Volume two of this report consisted of the following Appendixes: Site Photographs (A), Well Inventory (B), Boring Logs (C), CSL Technical Memorandum (D), Data Review and Validation (E), GPS Memorandum (F), Level C Analytical Data Summary Tables (G), Slug Test (H), Special-Status Species (I), and Representative Species of Less Mobile Fish and Wildlife (J).

  5. Investigation of nonlinear dynamic soil property at the Savannah River Site

    International Nuclear Information System (INIS)

    Lee, R.C.

    2000-01-01

    This document summarizes laboratory dynamic soil testing investigations conducted by the University of Texas at Austin (UTA) for the Savannah River Site (SRS) (Stokoe et al., 1995a, Stokoe et al., 1995b, Sponseller and Stokoe, 1995). The purpose of the investigation is to provide an evaluation of past testing results in the context of new test data and the development of consistent site wide models of material strain dependencies based upon geologic formation, depth, and relevant index properties

  6. 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

  7. 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

  8. 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

  9. Streamline segment statistics of premixed flames with nonunity Lewis numbers

    Science.gov (United States)

    Chakraborty, Nilanjan; Wang, Lipo; Klein, Markus

    2014-03-01

    The interaction of flame and surrounding fluid motion is of central importance in the fundamental understanding of turbulent combustion. It is demonstrated here that this interaction can be represented using streamline segment analysis, which was previously applied in nonreactive turbulence. The present work focuses on the effects of the global Lewis number (Le) on streamline segment statistics in premixed flames in the thin-reaction-zones regime. A direct numerical simulation database of freely propagating thin-reaction-zones regime flames with Le ranging from 0.34 to 1.2 is used to demonstrate that Le has significant influences on the characteristic features of the streamline segment, such as the curve length, the difference in the velocity magnitude at two extremal points, and their correlations with the local flame curvature. The strengthenings of the dilatation rate, flame normal acceleration, and flame-generated turbulence with decreasing Le are principally responsible for these observed effects. An expression for the probability density function (pdf) of the streamline segment length, originally developed for nonreacting turbulent flows, captures the qualitative behavior for turbulent premixed flames in the thin-reaction-zones regime for a wide range of Le values. The joint pdfs between the streamline length and the difference in the velocity magnitude at two extremal points for both unweighted and density-weighted velocity vectors are analyzed and compared. Detailed explanations are provided for the observed differences in the topological behaviors of the streamline segment in response to the global Le.

  10. Remedial investigation for the chemical plant area of the Weldon Spring Site

    International Nuclear Information System (INIS)

    1992-11-01

    The US Department of Energy (DOE) is responsible for management of the Weldon Spring Site Remedial Action Project (WSSRAP) under its Environmental Restoration and Waste Management Program. Major goals include eliminating potential public and environmental hazards due to site contamination and releasing the property for alternate uses to the maximum extent practicable. The purpose of the remedial investigation described in this report was to determine the extent of contamination associated with the portion of the Weldon Spring site known as the chemical plant and raffinate pit area. The DOE has assumed responsibility for investigating and remediating all on-site soil contamination and off-site soil which is radiologically contaminated as a result of uranium and thorium processing operations. The DOE has also assumed the responsibility for radiologically contaminated groundwater on and off site. The Weldon Spring site remedial investigation also involved the evaluation of the sources, nature and extent, and environmental fate and transport of contaminants to provide a basis for defining the risks that the contaminants may pose to human health and the environment. Data are included in this report to support the screening of remedial technologies and to permit the development and detailed analysis of alternatives for remedial action at the site during the feasibility study process

  11. Main phases of siting for nuclear power plants with review of required investigations

    International Nuclear Information System (INIS)

    Malbasa, N.

    1984-01-01

    The purpose of the article is a short description of the main phases in the process of siting for nuclear power plants as interpreted and applied by the Institut za elektroprivredu, Zagreb in the screening, comparison and evaluation of the sites for NPPs in the SR of Croatia. The scope and purpose, as well as review of required data and investigations for each particular phase are given. Common used methods for the comparison of sites are described and example of rejection criteria applicable for early phases of the siting is proposed. It is given a list of the most important activities which detailed analysis id indispensable for ending of the evaluation and getting a site permit from the regulatory body. A legal and regulatory basis for carrying out the siting process is also described. (author)

  12. Novel diffusion tensor imaging technique reveals developmental streamline volume changes in the corticospinal tract associated with leg motor control.

    Science.gov (United States)

    Kamson, David O; Juhász, Csaba; Chugani, Harry T; Jeong, Jeong-Won

    2015-04-01

    Diffusion tensor imaging (DTI) has expanded our knowledge of corticospinal tract (CST) anatomy and development. However, previous developmental DTI studies assessed the CST as a whole, overlooking potential differences in development of its components related to control of the upper and lower extremities. The present cross-sectional study investigated age-related changes, side and gender differences in streamline volume of the leg- and hand-related segments of the CST in children. DTI data of 31 children (1-14 years; mean age: 6±4 years; 17 girls) with normal conventional MRI were analyzed. Leg- and hand-related CST streamline volumes were quantified separately, using a recently validated novel tractography approach. CST streamline volumes on both sides were compared between genders and correlated with age. Higher absolute streamline volumes were found in the left leg-related CST compared to the right (p=0.001) without a gender effect (p=0.4), whereas no differences were found in the absolute hand-related CST volumes (p>0.4). CST leg-related streamline volumes, normalized to hemispheric white matter volumes, declined with age in the right hemisphere only (R=-.51; p=0.004). Absolute leg-related CST streamline volumes showed similar, but slightly weaker correlations. Hand-related absolute or normalized CST streamline volumes showed no age-related variations on either side. These results suggest differential development of CST segments controlling hand vs. leg movements. Asymmetric volume changes in the lower limb motor pathway may be secondary to gradually strengthening left hemispheric dominance and is consistent with previous data suggesting that footedness is a better predictor of hemispheric lateralization than handedness. Copyright © 2014 The Japanese Society of Child Neurology. Published by Elsevier B.V. All rights reserved.

  13. Streamlined Modeling for Characterizing Spacecraft Anomalous Behavior

    Science.gov (United States)

    Klem, B.; Swann, D.

    2011-09-01

    Anomalous behavior of on-orbit spacecraft can often be detected using passive, remote sensors which measure electro-optical signatures that vary in time and spectral content. Analysts responsible for assessing spacecraft operational status and detecting detrimental anomalies using non-resolved imaging sensors are often presented with various sensing and identification issues. Modeling and measuring spacecraft self emission and reflected radiant intensity when the radiation patterns exhibit a time varying reflective glint superimposed on an underlying diffuse signal contribute to assessment of spacecraft behavior in two ways: (1) providing information on body component orientation and attitude; and, (2) detecting changes in surface material properties due to the space environment. Simple convex and cube-shaped spacecraft, designed to operate without protruding solar panel appendages, may require an enhanced level of preflight characterization to support interpretation of the various physical effects observed during on-orbit monitoring. This paper describes selected portions of the signature database generated using streamlined signature modeling and simulations of basic geometry shapes apparent to non-imaging sensors. With this database, summarization of key observable features for such shapes as spheres, cylinders, flat plates, cones, and cubes in specific spectral bands that include the visible, mid wave, and long wave infrared provide the analyst with input to the decision process algorithms contained in the overall sensing and identification architectures. The models typically utilize baseline materials such as Kapton, paints, aluminum surface end plates, and radiators, along with solar cell representations covering the cylindrical and side portions of the spacecraft. Multiple space and ground-based sensors are assumed to be located at key locations to describe the comprehensive multi-viewing aspect scenarios that can result in significant specular reflection

  14. Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

    International Nuclear Information System (INIS)

    Malbasa, N.

    2008-01-01

    A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

  15. Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

    Energy Technology Data Exchange (ETDEWEB)

    Malbasa, N [Ekonerg, Zagreb (Croatia)

    2008-07-01

    A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

  16. 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

  17. 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

  18. Transport processes investigation: A necessary first step in site scale characterization plans

    International Nuclear Information System (INIS)

    Roepke, C.; Glass, R.J.; Brainard, J.; Mann, M.; Kriel, K.; Holt, R.; Schwing, J.

    1995-01-01

    We propose an approach, which we call the Transport Processes Investigation or TPI, to identify and verify site-scale transport processes and their controls. The TPI aids in the formulation of an accurate conceptual model of flow and transport, an essential first step in the development of a cost effective site characterization strategy. The TPI is demonstrated in the highly complex vadose zone of glacial tills that underlie the Fernald Environmental Remediation Project (FEMP) in Fernald, Ohio. As a result of the TPI, we identify and verify the pertinent flow processes and their controls, such as extensive macropore and fracture flow through layered clays, which must be included in an accurate conceptual model of site-scale contaminant transport. We are able to conclude that the classical modeling and sampling methods employed in some site characterization programs will be insufficient to characterize contaminant concentrations or distributions at contaminated or hazardous waste facilities sited in such media

  19. Remedial investigation/feasibility study for the David Witherspoon, Inc., 901 Site, Knoxville, Tennessee: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This remedial investigation (RI)/feasibility study (FS) supports the selection of remedial actions for the David Witherspoon, Inc. 901 Maryville Pike Site in Knoxville, Tennessee. Operations at the site, used as a recycling center, have resulted in past, present, and potential future releases of hazardous substances in to the environment. This Site is a Tennessee Superfund site. A phased approach was planned to (1) gather existing data from previous investigations managed by the Tenn. Dept. of Environment and Conservation; (2) perform a preliminary RI, including risk assessments, and an FS with existing data to identify areas where remedial action may be necessary; (3) gather additional field data to adequately define the nature and extent of risk-based contaminants that present identifiable threats to human and/or ecological receptors; and (4) develop remedial action alternatives to reduce risks to acceptable levels.

  20. Remedial investigation for the 200-BP-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    Buckmaster, M.A.

    1991-01-01

    The Hanford Site, Richland, Washington, contains over 1500 identified waste sites that will be characterized and remediated over the next 30 years. In support of the ''Hanford Federal Facility Agreement and Consent Order,'' the US Department of Energy has initiated a remedial investigation/feasibility study (RI/FS) at the 200-BP-1 operable unit. The 200-BP-1 RI is the first Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) investigation on the Hanford Site that involves drilling into highly radioactive and chemically contaminated soils. The initial phase of the site characterization is oriented toward determining the nature and extent of any contamination present in the vicinity of the 200-BP-1 operable unit. The major focus of the Phase I RI is the drilling and sampling of 10 inactive waste disposal units which received low level radioactive liquid waste

  1. Remedial investigation/feasibility study for the David Witherspoon, Inc., 901 Site, Knoxville, Tennessee: Volume 1

    International Nuclear Information System (INIS)

    1996-10-01

    This remedial investigation (RI)/feasibility study (FS) supports the selection of remedial actions for the David Witherspoon, Inc. 901 Maryville Pike Site in Knoxville, Tennessee. Operations at the site, used as a recycling center, have resulted in past, present, and potential future releases of hazardous substances in to the environment. This Site is a Tennessee Superfund site. A phased approach was planned to (1) gather existing data from previous investigations managed by the Tenn. Dept. of Environment and Conservation; (2) perform a preliminary RI, including risk assessments, and an FS with existing data to identify areas where remedial action may be necessary; (3) gather additional field data to adequately define the nature and extent of risk-based contaminants that present identifiable threats to human and/or ecological receptors; and (4) develop remedial action alternatives to reduce risks to acceptable levels

  2. An investigation of site diversity and comparison with ITU-R recommendations

    Science.gov (United States)

    Callaghan, S. A.; Boyes, B.; Couchman, A.; Waight, J.; Walden, C. J.; Ventouras, S.

    2008-08-01

    Earth-space radio systems operating at frequencies of 10 GHz and above are badly attenuated by rain, cloud, and atmospheric gases. As the frequencies of operational systems increase, it becomes increasingly uneconomic to compensate for the effects of fading through the use of a fixed fade margin, hence the implementation of fade mitigation techniques (FMT). The spatial and temporal variation of rain provides the justification for the use of site diversity as an FMT. Site diversity employs two or more ground stations receiving the same satellite signal with a separation distance such that the sites encounter intense rainfall at different times, and switching to the site experiencing the least fading improves system performance considerably. Measurements of the 20.7 GHz beacon carried as part of the Global Broadcast Service (GBS) payload on the U.S. Department of Defense satellite UFO-9 have been made at three sites: two are located in the South of England (˜8 km apart), and the third receiver was located in Scotland. These beacon measurements have produced long term attenuation exceedance and site diversity gain and improvement statistics. This attenuation time series data can simulate the performance of an Earth-space system using site diversity, indicating the optimum method of implementing this FMT. In this paper, unbalanced site diversity is investigated, as this is a more likely scenario than the balanced site diversity modeled by the ITU-R recommendations. This paper also investigates the implementation of site diversity from a commercial context, including cost-benefit analysis and technical feasibility.

  3. Investigation of the metal binding site in methionine aminopeptidase by density functional theory

    DEFF Research Database (Denmark)

    Jørgensen, Anne Techau; Norrby, Per-Ola; Liljefors, Tommy

    2002-01-01

    All methionine aminopeptidases exhibit the same conserved metal binding site. The structure of this site with either Co2+ ions or Zn2+ ions was investigated using density functional theory. The calculations showed that the structure of the site was not influenced by the identity of the metal ions....... This was the case for both of the systems studied; one based on the X-ray structure of the human methionine aminopeptidase type 2 (hMetAP-2) and the other based on the X-ray structure of the E. coli methionine aminopeptidase type 1 (eMetAP-1). Another important structural issue is the identity of the bridging...

  4. 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

  5. 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

  6. Single-Site Palladium(II) Catalyst for Oxidative Heck Reaction: Catalytic Performance and Kinetic Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Duan, Hui; Li, Mengyang; Zhang, Guanghui; Gallagher, James R.; Huang, Zhiliang; Sun, Yu; Luo, Zhong; Chen, Hongzhong; Miller, Jeffrey T.; Zou, Ruqiang; Lei, Aiwen; Zhao, Yanli

    2015-01-01

    ABSTRACT: The development of organometallic single-site catalysts (SSCs) has inspired the designs of new heterogeneous catalysts with high efficiency. Nevertheless, the application of SSCs in certain modern organic reactions, such as C-C bond formation reactions, has still been less investigated. In this study, a single-site Pd(II) catalyst was developed, where 2,2'-bipyridine-grafted periodic mesoporous organosilica (PMO) was employed as the support of a Pd(II) complex. The overall performance of the single-site Pd(II) catalyst in the oxidative Heck reaction was then investigated. The investigation results show that the catalyst displays over 99% selectivity for the product formation with high reaction yield. Kinetic profiles further confirm its high catalytic efficiency, showing that the rate constant is nearly 40 times higher than that for the free Pd(II) salt. X-ray absorption spectroscopy reveals that the catalyst has remarkable lifetime and recyclability.

  7. AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

    International Nuclear Information System (INIS)

    Whitaker, S.H.; Brown, A.; Davison, C.C.; Gascoyne, M.; Lodha, G.S.; Stevenson, D.R.; Thorne, G.A.; Tomsons, D.

    1994-05-01

    The objective of this report is to summarize AECL's strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB's R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL's investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL's Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL's strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL's R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs

  8. AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

    Energy Technology Data Exchange (ETDEWEB)

    Whitaker, S H; Brown, A; Davison, C C; Gascoyne, M; Lodha, G S; Stevenson, D R; Thorne, G A; Tomsons, D [AECL Research, Whiteshell Labs., Pinawa, MB (Canada)

    1994-05-01

    The objective of this report is to summarize AECL`s strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB`s R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL`s investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL`s Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL`s strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL`s R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs.

  9. Site investigations for repositories for solid radioactive wastes in deep continental geological formations

    International Nuclear Information System (INIS)

    1982-01-01

    This report reviews the earth-science investigations and associated scientific studies that may be needed to select a repository site and confirm that its characteristics are such that it will provide a safe confinement for solidified high-level and alpha-bearing and certain other solid radioactive wastes. Site investigations, as used in this report, cover earth sciences and associated safety analyses. Other site-investigation activities are identified but not otherwise considered here. The repositories under consideration are those consisting of mined cavities in deep continental rocks for accepting wastes in the solid and packaged form. The term deep as used in this report is used solely to emphasize the distinction between the repositories discussed in this report and those for shallow-ground disposal. In general, depths under consideration here are greater than 200 metres. The term continental refers to those geological formations that occur either beneath present-day land masses and adjoining islands or beneath the shallow seas. One of the objectives of site investigations is to collect the site-specific data necessary for the different evaluations, such as modelling required to assess the long-term safety of an underground repository

  10. Site investigations for repositories for solid radioactive wastes in deep continental geological formations

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    This report reviews the earth-science investigations and associated scientific studies that may be needed to select a repository site and confirm that its characteristics are such that it will provide a safe confinement for solidified high-level and alpha-bearing and certain other solid radioactive wastes. Site investigations, as used in this report, cover earth sciences and associated safety analyses. Other site-investigation activities are identified but not otherwise considered here. The repositories under consideration are those consisting of mined cavities in deep continental rocks for accepting wastes in the solid and packaged form. The term deep as used in this report is used solely to emphasize the distinction between the repositories discussed in this report and those for shallow-ground disposal. In general, depths under consideration here are greater than 200 metres. The term continental refers to those geological formations that occur either beneath present-day land masses and adjoining islands or beneath the shallow seas. One of the objectives of site investigations is to collect the site-specific data necessary for the different evaluations, such as modelling required to assess the long-term safety of an underground repository.

  11. The use of desk studies, remote sensing and surface geological and geophysical techniques in site investigations

    International Nuclear Information System (INIS)

    Mather, J.D.

    1984-02-01

    The geoscientific investigations required to characterise a site for the underground disposal of radioactive wastes involve a wide range of techniques and expertise. Individual national investigations need to be planned with the specific geological environment and waste form in mind. However, in any investigation there should be a planned sequence of operations leading through desk studies and surface investigations to the more expensive and sophisticated sub-surface investigations involving borehole drilling and the construction of in situ test facilities. Desk studies are an important and largely underestimated component of site investigations. Most developed countries have archives of topographical, geological and environmental data within government agencies, universities, research institutes and learned societies. Industry is another valuable source but here confidentiality can be a problem. However, in developing countries and in some regions of developed countries the amount of basic data, which needs to be collected over many decades, will not be as extensive. In such regions remote sensing offers a rapid method of examining large areas regardless of land access, vegetation or geological setting, rapidly and at relatively low cost. It can also be used to examine features, such as discontinuity patterns, over relatively small areas in support of intensive ground investigations. Examples will be given of how remote sensing has materially contributed to site characterisation in a number of countries, particularly those such as Sweden, Canada and the United Kingdom where the major effort has concentrated on crystalline rocks. The main role of desk studies and surface investigations is to provide basic data for the planning and execution of more detailed subsurface investigations. However, such studies act as a valuable screening mechanism and if they are carried out correctly can enable adverse characteristics of a site to be identified at an early stage before

  12. Site-specific investigations of aquifer thermal energy storage for space and process cooling

    International Nuclear Information System (INIS)

    Brown, D.R.

    1991-01-01

    This paper reports on the Pacific Northwest Laboratory (PNL) that has completed three preliminary site-specific feasibility studies that investigated aquifer thermal energy storage (ATES) for reducing space and process cooling costs. Chilled water stored in an ATES system could be used to meet all or part of the process and/or space cooling loads at the three facilities investigated. Seasonal or diurnal chill ATES systems could be significantly less expensive than a conventional electrically-driven, load-following chiller system at one of the three sites, depending on the cooling water loop return temperature and presumed future electricity escalation rate. For the other two sites investigated, a chill ATES system would be economically competitive with conventional chillers if onsite aquifer characteristics were improved. Well flow rates at one of the sites were adequate, but the expected thermal recovery efficiency was too low. The reverse of this situation was found at the other site, where the thermal recovery efficiency was expected to be adequate, but well flow rates were too low

  13. Argonne's Expedited Site Characterization: An integrated approach to cost- and time-effective remedial investigation

    International Nuclear Information System (INIS)

    Burton, J.C.; Walker, J.L.; Aggarwal, P.K.; Meyer, W.T.

    1995-01-01

    Argonne National Laboratory has developed a methodology for remedial site investigation that has proven to be both technically superior to and more cost- and time-effective than traditional methods. This methodology is referred to as the Argonne Expedited Site Characterization (ESC). Quality is the driving force within the process. The Argonne ESC process is abbreviated only in time and cost and never in terms of quality. More usable data are produced with the Argonne ESC process than with traditional site characterization methods that are based on statistical-grid sampling and multiple monitoring wells. This paper given an overview of the Argonne ESC process and compares it with traditional methods for site characterization. Two examples of implementation of the Argonne ESC process are discussed to illustrate the effectiveness of the process in CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act) and RCRA (Resource Conservation and Recovery Act) programs

  14. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    International Nuclear Information System (INIS)

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations

  15. Corrective Action Investigation Plan for Corrective Action Unit 551: Area 12 Muckpiles, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Boehlecke, Robert F.

    2004-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 551, Area 12 muckpiles, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the 'Federal Facility Agreement and Consent Order' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 551 is located in Area 12 of the NTS, which is approximately 110 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Area 12 is approximately 40 miles beyond the main gate to the NTS. Corrective Action Unit 551 is comprised of the four Corrective Action Sites (CASs) shown on Figure 1-1 and listed below: (1) 12-01-09, Aboveground Storage Tank and Stain; (2) 12-06-05, Muckpile; (3) 12-06-07, Muckpile; and (4) 12-06-08, Muckpile. Corrective Action Site 12-01-09 is located in Area 12 and consists of an above ground storage tank (AST) and associated stain. Corrective Action Site 12-06-05 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. Corrective Action Site 12-06-07 is located in Area 12 and consists of a muckpile associated with the U12 C-, D-, and F-Tunnels. Corrective Action Site 12-06-08 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. In keeping with common convention, the U12B-, C-, D-, and F-Tunnels will be referred to as the B-, C-, D-, and F-Tunnels. The corrective action investigation (CAI) will include field inspections, radiological surveys, and sampling of media, where appropriate. Data will also be obtained to support waste management decisions

  16. Animal investigation program 1974 annual report: Nevada Test Site and vicinity

    International Nuclear Information System (INIS)

    Smith, D.D.; Giles, K.R.; Bernhardt, D.E.; Brown, K.R.

    1977-06-01

    Data are presented from the radioanalysis of tissues collected from cattle, deer, desert bighorn sheep, and other wildlife that resided on or near the Nevada Test Site during 1974. Routine activities and special investigations of the Animal Investigation Program are also discussed. Other than the naturally occurring potassium-40, gamma-emitting radionuclides were detected infrequently. For example, cesium-137 was found only in the muscle tissues from 3 of the 12 Nevada Test Site cattle sampled during 1974. Tritium concentrations in the tissues from most of the animals sampled are at background levels. Animals from the experimental farm tended to have slightly higher concentrations than those sampled at other locations on the Nevada Test Site. Strontium-90 levels in bones from deer, desert bighorn sheep, and cattle were slightly lower than those reported for the preceding year. A graph depicts the average levels found in the bones of the three species from 1956 through 1974

  17. Geochemical investigation of UMTRAP designated site at Salt Lake City, Utah

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.

    1983-09-01

    This report is the result of a geochemical investigation of the former uranium mill and tailings site at Salt Lake City, Utah. This is one in a series of site specific geochemical investigations performed on the inactive uranium mill tailings included in the Uranium Mill Tailings Remedial Action Project. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results will be used to model contaminant migration and to develop criteria for long-term containment media such as a cover system which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. The solid samples were water extracted to remove easily soluble salts and acid extracted to remove carbonates and hydroxides. The water extracts and solid samples were anlyzed for the major and trace elements. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Four major conclusions are: (1) sediments in the ditches and creeks adjacent to the site contain tailings, however, the waters were generally not contaminated; (2) tailings are mixed with the soils within a meter below the tailings in some locations, however, water-soluble contaminants decrease to below background levels within 30 cm below the tailings; (3) there has not been significant acid seepage into the soils below the tailings; and (4) salt crusts on the tailings contain trace elements, with the elements that form chloride complexes having the greatest accumulation

  18. Geo-scientific basis for the investigation site Oberbauenstock. Volume 1

    International Nuclear Information System (INIS)

    Schneider, T.R.; Kappeler, S.W.

    1984-12-01

    The geological and hydrogeological conditions prevailing in the region of the investigation site Oberbauen Stock have been chosen as model data-set, in the frame of project Gewaehr 1985, for a type B (low and intermediate level) waste repository. The report, in its capacity as a reference report for project Gewaehr presents all available, relevant site data applicable to modeling of the site. The sources of the data are presented. Geological studies and investigations, boreholes and geophysical investigations prior to the construction of the Seelisberg tunnel (as well as all underground facilities pertaining to the said tunnel) are described. In the section devoted to geology, the stratigraphy and the tectonics of the helvetic nappes in the area of the site are described. Further, the host rock, the neighbouring formations and the local tectonics are presented. In conclusion the geological boundary conditions of the area are summarized. The section devoted to hydrogeology deals with the observations and measurements carried out at the surface and in the underground facilities. As well, the present state of knowledge concerning the water chemistry is described. The section also includes a description of the regional hydrogeology. Concerning rock mechanics a summary and discussion of all available parameters and excavation classes is presented. A description of all the experiences acquired during construction follows as a second part. The section ends with a presentation of the observations and measurements of the gas content of the host rock and other formations. A section concerning long-term behaviour concludes the report. Possible future changes of the geology and the climate are investigated. The consequences for the model site are discussed. It is concluded that a negative impact to a repository on the site is improbable on a timescale of 10 5 years. (author)

  19. ERDA test facilities, East Mesa Test Site. Geothermal resource investigations, Imperial Valley, California

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    Detailed specifications which must be complied with in the construction of the ERDA Test Facilities at the East Mesa Site for geothermal resource investigations in Imperial Valley, California are presented for use by prospective bidders for the construction contract. The principle construction work includes a 700 gpm cooling tower with its associated supports and equipment, pipelines from wells, electrical equipment, and all earthwork. (LCL)

  20. Remedial investigation and feasibility study for the Lawrence Livermore National Laboratory Site 300 Pit 7 Complex

    Energy Technology Data Exchange (ETDEWEB)

    Taffet, M.J. (Lawrence Livermore National Lab., CA (USA)); Oberdorfer, J.A. (San Jose State Univ., CA (USA)); McIlvride, W.A. (Weiss Associates, Oakland, CA (USA))

    1989-10-01

    This report summarizes the results and conclusions of the investigation of tritium and other compounds in ground water in the vicinity of landfills at the Lawrence Livermore National Laboratory (LLNL) Site 300 Pit 7 Complex. 91 refs., 110 figs., 43 tabs.

  1. Aespoe Hard Rock Laboratory - feasibility and usefulness of site investigation methods. Experiences from the pre-investigation phase

    Energy Technology Data Exchange (ETDEWEB)

    Almen, K E [ed.; KEA GEO-Konsult (Sweden); Olsson, Paer [SKANSKA, (Sweden); Rhen, I [VBB VIAK AB, Malmoe (Sweden); Stanfors, R [RS Consulting, (Sweden); Wikberg, P [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    1994-08-01

    One of the main goals set up by SKB for the Aespoe HRL project is to `test the quality and appropriateness of different methods for characterizing the bedrock with respect to conditions of importance for a final repository`. An extensive investigation programme was carried out during the projects pre-investigation phase that in part was based in experience from SKBs previous site investigations and in part entailed the testing of new or other unestablished methods. Previous technical reports have described the methods that have been used and the results, models and predictions that have been produced. All the methods used are discussed in the present report in terms of how they have contributed in different analysis stages to the total geoscientific characterization of the rock at Aespoe. The usefulness of each method for modelling and prediction in different scales is evaluated, and aspects of the practical execution of the methods under different conditions are discussed. The report sheds light on the importance of dividing large investigation programmes such as this one into suitable stages to get an opportunity to evaluate the results obtained and plan in detail the investigations in the next stage. Furthermore, the way in which the characterization/modelling work in different geometric scales has been done for the different investigation stages is discussed, along with whether this has been found to be a suitable approach. The importance of pursuing an interdisciplinary strategy throughout the pre-investigation process cannot be overemphasized. For the planning, execution, analysis and reporting of the results of the pre-investigations, this has been guaranteed by an organization in which an interdisciplinary group has been in charge of the investigations, together with the project manager. 52 refs, numerous tabs and figs.

  2. Remedial Investigation of Hanford Site Releases to the Columbia River - 13603

    Energy Technology Data Exchange (ETDEWEB)

    Lerch, J.A.; Hulstrom, L.C. [Washington Closure Hanford, LLC, Richland, Washington 99354 (United States); Sands, J.P. [U.S Department of Energy, Richland Operations Office, Richland, Washington 99352 (United States)

    2013-07-01

    In south-central Washington State, the Columbia River flows through the U.S. Department of Energy Hanford Site. A primary objective of the Hanford Site cleanup mission is protection of the Columbia River, through remediation of contaminated soil and groundwater that resulted from its weapons production mission. Within the Columbia River system, surface water, sediment, and biota samples related to potential Hanford Site hazardous substance releases have been collected since the start of Hanford operations. The impacts from release of Hanford Site radioactive substances to the Columbia River in areas upstream, within, and downstream of the Hanford Site boundary have been previously investigated as mandated by the U.S. Department of Energy requirements under the Atomic Energy Act. The Remedial Investigation Work Plan for Hanford Site Releases to the Columbia River [1] was issued in 2008 to initiate assessment of the impacts under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 [2]. The work plan established a phased approach to characterize contaminants, assess current risks, and determine whether or not there is a need for any cleanup actions. Field investigation activities over a 120-mile stretch of the Columbia River began in October 2008 and were completed in 2010. Sampled media included surface water, pore water, surface and core sediment, island soil, and fish (carp, walleye, whitefish, sucker, small-mouth bass, and sturgeon). Information and sample results from the field investigation were used to characterize current conditions within the Columbia River and assess whether current conditions posed a risk to ecological or human receptors that would merit additional study or response actions under CERCLA. The human health and ecological risk assessments are documented in reports that were published in 2012 [3, 4]. Conclusions from the risk assessment reports are being summarized and integrated with remedial investigation

  3. Geophysical and geological borehole investigations for the characterization of a site for radioactive waste disposal

    International Nuclear Information System (INIS)

    Olsson, O.; Ahlbom, K.

    1984-02-01

    In the Swedish program for site investigations detailed geological and geophysical investigations are performed at areas of 4-6 km 2 at the surface. Normally around 10 deep core bore holes are drilled. The length of the holes is normally from 600 to 1000 m. The holes are drilled to verify the location of fracture zones and to investigate the physical and hydraulic properties of the fracture zones at large depths. Investigations have been performed in a number of sites with mainly granitic and gneissic rocks. The core from these boreholes is logged with the aid of a microcomputer system. The cores are mapped with respect to rock type, structure, fractures and fracture minerals. Indications of water flow, shearing and core-discing are also studied. The boreholes are logged with a suite of geophysical logs. Several different electrical logs are used and have been found to be good indicators of fracture zones. Normally the electrical logs in combination with the fracture frequency are used to define the limits of fracture zones crossing the borehole. The temperature log and the salinity log have proved to be good indicators of permeable zones. The data from each hole is correlated with data obtained from the other holes and the surface investigations to build a fracture zone model which is used for the hydraulic modelling of the site. In order to verify the extension of the fracture zones at a distance from the borehole cross-hole techniques have been applied. At the Swedish test site Finnsjoe and in the Stripa mine the suitability of the mise a la masse technique for mapping of fracture zones was tested. At the Finnsjoe site it was possible to map a fairly complex fracture system over distances up to 150 m. In the Stripa mine the object was to follow the extent of a major fracture zone for distances up to 600 m. It was possible to obtain an indication of the orientation of the fracture zone

  4. Supplemental site inspection for Air Force Plant 59, Johnson City, New York, Volume 1: Investigation report

    Energy Technology Data Exchange (ETDEWEB)

    Nashold, B.; Rosenblatt, D.; Hau, J. [and others

    1995-08-01

    This summary describes a Supplemental Site Inspection (SSI) conducted by Argonne National Laboratory (ANL) at Air Force Plant 59 (AFP 59) in Johnson City, New York. All required data pertaining to this project were entered by ANL into the Air Force-wide Installation Restoration Program Information System (IRPIMS) computer format and submitted to an appropriate authority. The work was sponsored by the United States Air Force as part of its Installation Restoration Program (IRP). Previous studies had revealed the presence of contaminants at the site and identified several potential contaminant sources. Argonne`s study was conducted to answer questions raised by earlier investigations.

  5. Intermediary report on the 1994/95 investigations at the Wellenberg site (Community of Wolfenschiessen, NW)

    International Nuclear Information System (INIS)

    1996-01-01

    Following submission of the application for a general licence by GNW in June 1994, Nagra continued as planned with the field work at the Wellenberg site and with analysis of available data. In view of the delay in procedure brought about by the cantonal vote of 25th June 1995, the Federal Office of Energy requested GNW to review the geological content of the general license application in the light of more recent investigation results in order to give HSK (the Swiss Federal Nuclear Safety Inspectorate) access to the most up-to-date information when preparing its opinion. This is the purpose of the present report, which discusses the current status of ongoing analyses. The report concentrates on the main results only and is correspondingly concise; it is in no way intended to anticipate the final report on the Wellenberg investigations. The report begins by ountlining the aims of the site investigations of 1994/95 and goes on to discuss the field work performed at the site. The raw data available from the field investigations are also presented. The main section of the report discusses the first analyses of the data; these are then summarised into a set of geological conclusions which are complemented by a preliminary safety analysis. The resulting conceptualisations and parameter values clearly lie within the confines of the geological dataset used for the general licence application. It can therefore be concluded that the field investigations and complementary studies performed since the submission of the general licence application confirm the validity of the basic findings of the reference reports which formed the background to the application: the selected site is suitable for continuing investigations with a view to construction of a L/ILW repository. (author) figs., tabs., refs

  6. 48 CFR 12.602 - Streamlined evaluation of offers.

    Science.gov (United States)

    2010-10-01

    ... offers. 12.602 Section 12.602 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION... for Commercial Items 12.602 Streamlined evaluation of offers. (a) When evaluation factors are used... evaluation factors. (b) Offers shall be evaluated in accordance with the criteria contained in the...

  7. Application-Tailored I/O with Streamline

    NARCIS (Netherlands)

    de Bruijn, W.J.; Bos, H.J.; Bal, H.E.

    2011-01-01

    Streamline is a stream-based OS communication subsystem that spans from peripheral hardware to userspace processes. It improves performance of I/O-bound applications (such as webservers and streaming media applications) by constructing tailor-made I/O paths through the operating system for each

  8. A review of geophysical investigations at the site of Chalk River Nuclear Laboratories, Ontario

    International Nuclear Information System (INIS)

    Thomas, M.D.; Hayles, J.G.

    1988-01-01

    The site of the Chalk River Nuclear Laboratories was one of the first research areas located on crystalline rocks to be extensively investigated under the Canadian Nuclear Fuel Waste Management Program. A large contribution to meeting the geoscientific objectives of the program has been made using a suite of geophysical techniques. Many of them are standard, though sometimes modified in terms of instrumentation and/or experimental and/or analytical procedures, to meet the particular needs of the waste management program. Relatively new techniques have also been employed. Much of the early evaluation and development of the various techniques took place at the Chalk River site. Standard methods such as gravity, magnetics and seismic sounding have been used to investigate bedrock structure, and the seismic method has also been used to estimate overburden thickness. Standard geophysical borehole logging has been used to obtain in situ estimates of physical properties, to locate fracture zones and to make hole to hole correlations that have helped define local structure. Several standard electrical (e.g. resitivity) and electromagnetic (e.g. VLF-EM) techniques have proven successful in identifying water-filled fractures and faults. Relatively new techniques introduced into the geophysics at Chalk River were: ground probing radar; to investigate overburden; borehole TV and acoustic televiewer and VLF-EM, to locate fractures; studies of seismic tube-waves, well tides and temperature logs, to investigate fracture location and permeability. Most of these methods have been successful and are now routinely employed at other research sites

  9. Investigations at the former sites of raw phosphate processing in Germany

    International Nuclear Information System (INIS)

    Reichelt, Andreas; Weiss, Dietmar; Feige, Sebastian; Wiegand, Jens; Gerler, Juergen

    2008-01-01

    Raw phosphates have been processed in an industrial scale in Germany approximately since the middle of the 19th century. During the centuries, huge amounts of residues with high mass specific activities have been accumulated. Within the framework of a historical study, we have determined the accumulated radionuclide inventory from 1865 to 2005. The consumption amounts to approx. 150 million tons raw phosphates (corresponds to approx. 2.22*10 14 Bq U-238) with a fraction of national production of approx. 1 million tons. A production of approx. 3 million tons of elemental phosphorus (calcium silicate slag: 3.6*10 13 Bq Ra-226) and approx. 12 million tons of phosphoric acid (phosphogypsum: 2.7*10 13 Bq Ra-226) had been achieved. In the next step, we have looked for the former sites with legacies of the raw phosphate processing industry. 92 sites of former production of phosphate fertilizers, 3 sites of former production of elemental phosphorus and 10 sites of former production of phosphoric acid had been identified. Some of them were selected for more detailed researches regarding the accumulated radionuclide inventory and on-site/laboratory radiological investigations. (author)

  10. Supplemental Investigation Plan for FFACO Use Restrictions, Nevada Test Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Lynn Kidman

    2008-02-01

    This document is part of an effort to re-evaluate all FFACO URs against the current RBCA criteria (referred to in this document as the Industrial Sites [IS] RBCA process) as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006a). After reviewing all of the existing FFACO URs, the 12 URs addressed in this Supplemental Investigation Plan (SIP) could not be evaluated against the current RBCA criteria as sufficient information about the contamination at each site was not available. This document presents the plan for conducting field investigations to obtain the needed information. This SIP includes URs from Corrective Action Units (CAUs) 326, 339, 358, 452, 454, 464, and 1010, located in Areas 2, 6, 12, 19, 25, and 29 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada; and CAU 403, located in Area 3 of the Tonopah Test Range, which is approximately 165 miles north of Las Vegas, Nevada.

  11. Status of site investigation for L/ILW facilities in the Philippines - 59262

    International Nuclear Information System (INIS)

    Palattao, Maria V.; Nohay, Carl; Reyes, Rolando; Singayan, Alfonso; Mallants, Dirk

    2012-01-01

    Document available in abstract form only. Full text of publication follows: Radioactive waste in the Philippines is generated from the various applications of radioactive materials in medicine, industries and research. The Philippine Nuclear Research Institute (PNRI) currently manages these wastes through its centralized treatment and storage facilities on site. Radioactive wastes that are received at the Institute are of different types ranging from contaminated solid and liquid materials to spent sealed sources, including radium. Treated and conditioned wastes are temporarily stored in simple roofed above ground concrete bunkers. The Philippine government through the Inter-agency Subcommittee on Radioactive Waste Management is committed to the development of a national repository for the country's radioactive waste. This policy has been recognized in spite of the relatively small volume of radioactive waste compared with countries that have a nuclear power program. To date, a potential site has been identified for detailed investigation with the assistance of the International Atomic Energy Agency (IAEA). The site is located in the northern part of the Philippine archipelago and has about 34 hectares for potential development. A drilling program that aimed to investigate the geologic, hydrogeologic and hydrologic properties of the site has been implemented

  12. The role of streamline curvature in sand dune dynamics: evidence from field and wind tunnel measurements

    Science.gov (United States)

    Wiggs, Giles F. S.; Livingstone, Ian; Warren, Andrew

    1996-09-01

    Field measurements on an unvegetated, 10 m high barchan dune in Oman are compared with measurements over a 1:200 scale fixed model in a wind tunnel. Both the field and wind tunnel data demonstrate similar patterns of wind and shear velocity over the dune, confirming significant flow deceleration upwind of and at the toe of the dune, acceleration of flow up the windward slope, and deceleration between the crest and brink. This pattern, including the widely reported upwind reduction in shear velocity, reflects observations of previous studies. Such a reduction in shear velocity upwind of the dune should result in a reduction in sand transport and subsequent sand deposition. This is not observed in the field. Wind tunnel modelling using a near-surface pulse-wire probe suggests that the field method of shear velocity derivation is inadequate. The wind tunnel results exhibit no reduction in shear velocity upwind of or at the toe of the dune. Evidence provided by Reynolds stress profiles and turbulence intensities measured in the wind tunnel suggest that this maintenance of upwind shear stress may be a result of concave (unstable) streamline curvature. These additional surface stresses are not recorded by the techniques used in the field measurements. Using the occurrence of streamline curvature as a starting point, a new 2-D model of dune dynamics is deduced. This model relies on the establishment of an equilibrium between windward slope morphology, surface stresses induced by streamline curvature, and streamwise acceleration. Adopting the criteria that concave streamline curvature and streamwise acceleration both increase surface shear stress, whereas convex streamline curvature and deceleration have the opposite effect, the relationships between form and process are investigated in each of three morphologically distinct zones: the upwind interdune and concave toe region of the dune, the convex portion of the windward slope, and the crest-brink region. The

  13. Ground-penetrating radar investigations conducted in the 100 areas, Hanford Site: Fiscal Year 1992

    International Nuclear Information System (INIS)

    Bergstrom, K.A.

    1994-01-01

    During Fiscal Year 1992, the Geophysics Group conducted forty- five Ground-Penetrating Radar (GPR) surveys in the 100 Areas (Figure 1) - Objectives for the investigations varied, from locating cribs, trenches and septic systems to helping site boreholes. The results of each investigation were delivered to clients in the form of a map that summarized the interpretation of a given site. No formal reports were prepared. The purpose of this document is to show where and why each of the surveys was conducted. The data and interpretation of each survey are available by contacting the Westinghouse Hanford Company, Geophysics Group. A map showing the location and basic parameters of each survey can be found in the Appendices of this report

  14. Investigating motives for preservation of Jewish heritage sites: the case of Macedonia

    OpenAIRE

    Petrevska, Biljana; Collins-Kreiner, Noga; Krakover, Shaul

    2017-01-01

    The study investigates the main motives for preservation of sites of Jewish heritage tourism (JHT) by studying three locations in Macedonia: Skopje (the capital), Štip (the largest city in the east part of Macedonia) and Bitola (the largest city in the southwest part of Macedonia). The article assesses the presence of several motivations, like: (i) Guilt; (ii) Interest in national history; (iii) Revival of a glorious Past; (iv) Economic benefits; (v) Display of sympathy; and (vi) Dark tourism...

  15. Savannah River Site RCRA/CERCLA/NEPA integrated investigation case study

    International Nuclear Information System (INIS)

    Clark, D.R.; Thomas, R.; Wilson, M.P.

    1992-01-01

    The Savannah River Site (SRS) is a US Department of Energy facility placed on the Superfund National Priority List in 1989. Numerous past disposal facilities and contaminated areas are undergoing the integrated regulatory remediation process detailed in the draft SRS Federal Facility Agreement. This paper will discuss the integration of these requirements by highlighting the investigation of the D-Area Burning/Rubble Pits, a typical waste unit at SRS

  16. Cavola experiment site: geophysical investigations and deployment of a dense seismic array on a landslide

    OpenAIRE

    L. Martelli; M. Cercato; P. Augliera; G. Di Giulio; G. Milana; J. Haines; P. Bordoni; F. Cara; undefined Cavola Experiment Team

    2007-01-01

    Geophysical site investigations have been performed in association with deployment of a dense array of 95 3-component seismometers on the Cavola landslide in the Northern Apennines. The aim of the array is to study propagation of seismic waves in the heterogeneous medium through comparison of observation and modelling. The small-aperture array (130 m×56 m) operated continuously for three months in 2004. Cavola landslide consists of a clay body sliding over mudstone-shale b...

  17. Learning of the subject: Methodology of investigation by means of a Site Web.

    Directory of Open Access Journals (Sweden)

    Yolanda Margarita Carbonell Cabarga

    2010-10-01

    Full Text Available Results of an investigation are presented having as an objective: the design of a Web Site for the learning of Methodology of Investigation subject in Psychology Bachelor of the Municipal University of Sancti Spíritus. This study was carried out in students of psychology career who were facing first year. Methods of the theoretical and empiric level were applied as well as the Mathematical Statistic. In the diagnosis was possible to appreciate the ignorance regarding the use of the methodology in the therorical methodological design of an investigation, also the difficulties in the study of the subject and violations in the application of orientations from the professors at the time of doing the research papers, so an interactive Web Site was obtained and applied which allow the teaching of the subject. The site was validated by means of a quasi-experiment, the obtained information was processed with the use of the statistical inferentia, results were in general highly significant for the feasibility of the proposal.

  18. 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

  19. A descriptive ecosystem model - a strategy for model development during site investigations

    International Nuclear Information System (INIS)

    Loefgren, Anders

    2003-09-01

    This report describes a strategy for the development of a site descriptive model for the surface ecosystem on the potential deep repository sites. The surface ecosystem embraces many disciplines, and these have to be identified, described and integrated in order to construct a descriptive ecosystem model that describes and quantifies biotic and abiotic patterns and processes of importance for the ecosystem on the site. The descriptive model includes both present day conditions and historical information. The descriptive ecosystem model will be used to supply input data for the safety assessment and to serve as the baseline model for devising a monitoring program to detect short-term disturbances caused first by the site investigations and later by the construction of the deep repository. Furthermore, it will serve as a reference for future comparisons to determine more long-term effects or changes caused by the deep repository. The report adopts a non-site-specific approach focusing on the following aims: 1. To present and define the properties that will constitute the descriptive ecosystem model. 2. To present a methodology for determining those properties. 3. To describe and develop the framework for the descriptive ecosystem model by integrating the different properties. 4. To present vital data from other site descriptive models such as those for geology or hydrogeology that interacts with and affects the descriptive ecosystem model. The properties are described under four different sections: general physical properties of the landscape, the terrestrial system, the limnic system and the marine system. These headings are further subdivided into entities that integrate properties in relation to processes

  20. A descriptive ecosystem model - a strategy for model development during site investigations

    Energy Technology Data Exchange (ETDEWEB)

    Loefgren, Anders [Stockholm Univ. (Sweden). Dept. of Botany; Lindborg, Tobias [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2003-09-01

    This report describes a strategy for the development of a site descriptive model for the surface ecosystem on the potential deep repository sites. The surface ecosystem embraces many disciplines, and these have to be identified, described and integrated in order to construct a descriptive ecosystem model that describes and quantifies biotic and abiotic patterns and processes of importance for the ecosystem on the site. The descriptive model includes both present day conditions and historical information. The descriptive ecosystem model will be used to supply input data for the safety assessment and to serve as the baseline model for devising a monitoring program to detect short-term disturbances caused first by the site investigations and later by the construction of the deep repository. Furthermore, it will serve as a reference for future comparisons to determine more long-term effects or changes caused by the deep repository. The report adopts a non-site-specific approach focusing on the following aims: 1. To present and define the properties that will constitute the descriptive ecosystem model. 2. To present a methodology for determining those properties. 3. To describe and develop the framework for the descriptive ecosystem model by integrating the different properties. 4. To present vital data from other site descriptive models such as those for geology or hydrogeology that interacts with and affects the descriptive ecosystem model. The properties are described under four different sections: general physical properties of the landscape, the terrestrial system, the limnic system and the marine system. These headings are further subdivided into entities that integrate properties in relation to processes.

  1. Final Report: Results of Environmental Site Investigation at Sylvan Grove, Kansas

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M [Argonne National Lab. (ANL), Argonne, IL (United States)

    2014-09-01

    Sylvan Grove is located in western Lincoln County, approximately 60 mi west of Salina, Kansas (Figure 1.1). From 1954 to 1966, the Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of Sylvan Grove. During this time, commercial grain fumigants containing carbon tetrachloride were in common use to preserve grain in storage. In 1998, the Kansas Department of Health and Environment (KDHE) found carbon tetrachloride above the maximum contaminant level (MCL) of 5 μg/L in groundwater from one private well used for livestock and lawn and garden watering. The 1998 KDHE sampling at Sylvan Grove was conducted under the USDA private well sampling program. To determine whether the former CCC/USDA facility at Sylvan Grove is a potential contaminant source and its possible relationship to the contamination in groundwater, the CCC/USDA proposed to conduct an environmental site investigation, in accordance with the Intergovernmental Agreement between the KDHE and the Farm Service Agency (FSA) of the USDA. Argonne National Laboratory, on behalf of the CCC/USDA, developed a work plan (Argonne 2012) for the site investigation and a supplemental work plan for indoor and ambient air sampling (Appendix A). The proposed work was approved by the KDHE (2012a, 2013). The investigations were performed by the Environmental Science Division of Argonne National Laboratory, on behalf of the CCC/USDA. The main activities for the site investigation were conducted in June 2012, and indoor and ambient air sampling was performed in February 2013. This report presents the findings of the investigations at Sylvan Grove.

  2. Joint statistics and conditional mean strain rates of streamline segments

    International Nuclear Information System (INIS)

    Schaefer, P; Gampert, M; Peters, N

    2013-01-01

    Based on four different direct numerical simulations of turbulent flows with Taylor-based Reynolds numbers ranging from Re λ = 50 to 300 among which are two homogeneous isotropic decaying, one forced and one homogeneous shear flow, streamlines are identified and the obtained space curves are parameterized with the pseudo-time as well as the arclength. Based on local extrema of the absolute value of the velocity along the streamlines, the latter are partitioned into segments following Wang (2010 J. Fluid Mech. 648 183–203). Streamline segments are then statistically analyzed based on both parameterizations using the joint probability density function of the pseudo-time lag τ (arclength l, respectively) between and the velocity difference Δu at the extrema: P(τ,Δu), (P(l,Δu)). We distinguish positive and negative streamline segments depending on the sign of the velocity difference Δu. Differences as well as similarities in the statistical description for both parameterizations are discussed. In particular, it turns out that the normalized probability distribution functions (pdfs) (of both parameterizations) of the length of positive, negative and all segments assume a universal shape for all Reynolds numbers and flow types and are well described by a model derived in Schaefer P et al (2012 Phys. Fluids 24 045104). Particular attention is given to the conditional mean velocity difference at the ending points of the segments, which can be understood as a first-order structure function in the context of streamline segment analysis. It determines to a large extent the stretching (compression) of positive (negative) streamline segments and corresponds to the convective velocity in phase space in the transport model equation for the pdf. While based on the random sweeping hypothesis a scaling ∝ (u rms ετ) 1/3 is found for the parameterization based on the pseudo-time, the parameterization with the arclength l yields a much larger than expected l 1/3 scaling. A

  3. Geological and hydrological investigations at Sidi Kreir Site, west of Alexandria, Egypt

    International Nuclear Information System (INIS)

    El-Shazly, E.M.; Shehata, W.M.; Somaida, M.A.

    1978-01-01

    Sidi-Kreir site lies along the Mediterranean Sea coast at km 30 to km 33 westwards from the center of the city of Alexandria. The studied site covers approximately 10 km 2 from the Mediterranean Sea northward to Mallehet (Lake) Maryut southward. This study includes the results of geological investigation of the site both structurally and stratigraphically, and the groundwater conditions, in relation to the erection of a nuclear power station in the site. The surface geology has been mapped using aerial photographs on scale of 1:20,000. Twenty-five drillholes were core-drilled in order to outline the subsurface geology and to observe the groundwater fluctuations. Selected core samples and soil samples were tested geologically in thin sections, physically and mechanically. Water samples were also collected and tested for total dissolved solids and specific weight. Groundwater level fluctuations were observed for a period of one year in 75 wells and drillholes. Furthermore three pumping tests were conducted to estimate the hydraulic properties of the freshwater aquifer. These properties were also calculated using the core samples data

  4. The use of small diameter probing equipment for contaminated site investigation

    International Nuclear Information System (INIS)

    Christy, T.M.; Spradlin, S.C.

    1992-01-01

    The past decade has witnessed a dramatic increase in the number of contaminated sites being investigated in the United States. This increase in subsurface investigation has spurred a corresponding increase in the development of subsurface sampling tools and methods. The past five years, in particular, have seen the development of small diameter (1 double-prime to 1.4 double-prime O.D.) percussion driven probing tools which can be used for the recovery of soil vapor, soil core and groundwater samples. This development has placed heretofore unavailable tools at the disposal of site investigators. Mechanized, vehicle mounted soil probe systems apply both static force and hydraulically powered percussion hammers for tool placement. Static down forces up to 3,000 lbs combined with percussion hammers of eight (8) horsepower continuous output are typical on equipment available to the field investigator. Using these energies, probing tools have been used for sampling a variety of media at depths exceeding 70 feet. Advantages of probing equipment which have contributed to its increasing usage in recent years include: ease of mobilization, absence of borehole cuttings, minimization of surface disturbance, and speed of sample collection. This paper focuses on the field application of hydraulic probing equipment including: the suitability of probing operations with respect to various Boil types and lithologies to probing operations; sampler types and recovery quantities for various media, and innovative probing applications presently being tested

  5. River and river-related drainage area parameters for site investigation program

    International Nuclear Information System (INIS)

    Blomqvist, P.; Brunberg, A.K.; Brydsten, L.

    2001-05-01

    In this paper, a number of parameters of importance to a determination of the function of running waters as transport channels for material from the continents to the sea are presented. We have assumed that retention mechanisms of material in the river and in the riparian zone will be covered by special investigations but tried to create a platform for such investigations by quantification of the extension of different main habitats. The choice of parameters has been made so that also the nature conservation value of the river can be preliminary established, and includes a general description of the river type and the inherent ecosystem. The material links directly to that presented in a previous report concerning site investigation programmes for lakes. The parameters have been divided into five groups: 1) The location of the object relative important gradients in the surrounding nature; 2) The river catchment area and its major constituents; 3) The river morphometry; 4) The river ecosystem; 5) Human-induced damages to the river ecosystem. The first two groups, principally based on the climate, hydrology, geology and vegetation of the catchment area, represent parameters that can be used to establish the rarity and representativity of the system, and will in the context of site investigation program be used as a basis for generalisation of the results. The third group, the river morphometry parameters, are standard parameters for the outline of sampling programmes and for calculations of the physical extension of key habitats in the system. The fourth group, the ecosystem of the river, includes physical, chemical and biological parameters required for determination of the influence from the terrestrial ecosystem of the catchment area, nutrient status, distribution of different habitats, and presence of fish in the system. In the context of site investigation program, the parameters in these two groups will be used for budget calculations of the flow of energy and

  6. River and river-related drainage area parameters for site investigation program

    Energy Technology Data Exchange (ETDEWEB)

    Blomqvist, P.; Brunberg, A.K. [Uppsala Univ. (Sweden). Dept. of Limnology; Brydsten, L. [Umeaa Univ. (Sweden). Dept. of Ecology and Environmental Science

    2001-05-01

    In this paper, a number of parameters of importance to a determination of the function of running waters as transport channels for material from the continents to the sea are presented. We have assumed that retention mechanisms of material in the river and in the riparian zone will be covered by special investigations but tried to create a platform for such investigations by quantification of the extension of different main habitats. The choice of parameters has been made so that also the nature conservation value of the river can be preliminary established, and includes a general description of the river type and the inherent ecosystem. The material links directly to that presented in a previous report concerning site investigation programmes for lakes. The parameters have been divided into five groups: 1) The location of the object relative important gradients in the surrounding nature; 2) The river catchment area and its major constituents; 3) The river morphometry; 4) The river ecosystem; 5) Human-induced damages to the river ecosystem. The first two groups, principally based on the climate, hydrology, geology and vegetation of the catchment area, represent parameters that can be used to establish the rarity and representativity of the system, and will in the context of site investigation program be used as a basis for generalisation of the results. The third group, the river morphometry parameters, are standard parameters for the outline of sampling programmes and for calculations of the physical extension of key habitats in the system. The fourth group, the ecosystem of the river, includes physical, chemical and biological parameters required for determination of the influence from the terrestrial ecosystem of the catchment area, nutrient status, distribution of different habitats, and presence of fish in the system. In the context of site investigation program, the parameters in these two groups will be used for budget calculations of the flow of energy and

  7. Vadose zone investigations at the Lawrence Livermore National Laboratory Superfund Site: An overview

    International Nuclear Information System (INIS)

    Iovenitti, J.L.; Nitao, J.J.; Bishop, D.J.

    1992-09-01

    Lawrence Livermore National Laboratory (LLNL)is investigating the fate and transport of vadose zone contaminants at their Livermore site in Livermore, California. The principal objectives of this work are to identify potential source areas at the Livermore site which require remediation, to prioritize those areas, and finally, to optimize the remediation process. Primary contaminants of interest for this investigation are volatile organic compounds (VOCs) and tritium. A fully integrated, three-part program, consisting of quantitative modeling, field studies, and laboratory measurements, is in progress. To evaluate and predict vadose zone contaminant migration, quantitative modeling is used. Our modeling capabilities are being enhanced through the development of a multicomponent,three-dimensional,nonaqueous phase liquid-liquid-vapor,nonisothermal flow and transport computer code. This code will be also used to evaluate vadose zone remediation requirements. Field studies to acquire LLNL site-specific soil (sediment) characteristics for computer code calibration and validation include subsurf ace lithologic and contaminant profiling, in situ soil moisture content, ground surface emission flux of VOCs and tritium, transpiration of tritium, and ground surface evapotranspiration of water. Multilevel vadose zone monitoring devices are used to monitor the gaseous and aqueous transport of contaminants

  8. Theoretical Calculations on Sediment Transport on Titan, and the Possible Production of Streamlined Forms

    Science.gov (United States)

    Burr, D. M.; Emery, J. P.; Lorenz, R. D.

    2005-01-01

    The Cassini Imaging Science System (ISS) has been returning images of Titan, along with other Saturnian satellites. Images taken through the 938 nm methane window see down to Titan's surface. One of the purposes of the Cassini mission is to investigate possible fluid cycling on Titan. Lemniscate features shown recently and radar evidence of surface flow prompted us to consider theoretically the creation by methane fluid flow of streamlined forms on Titan. This follows work by other groups in theoretical consideration of fluid motion on Titan's surface.

  9. An Evaluation of the Acquisition Streamlining Methods at the Fleet and Industrial Supply Center Pearl Harbor Hawaii

    National Research Council Canada - National Science Library

    Henry, Mark

    1999-01-01

    ...) Pearl Harbor's implementation of acquisition streamlining initiatives and recommends viable methods of streamlining the acquisition process at FISC Pearl Harbor and other Naval Supply Systems Command...

  10. Coordination Environment of Copper Sites in Cu-CHA Zeolite Investigated by Electron Paramagnetic Resonance

    DEFF Research Database (Denmark)

    Godiksen, Anita; Stappen, Frederick N.; Vennestrøm, Peter N. R.

    2014-01-01

    Cu-CHA combines high activity for the selective catalytic reduction (SCR) reaction with better hydrothermal stability and selectivity compared to other copper-substituted zeolites. At the same time Cu-CHA offers an opportunity for unraveling the coordination environment of the copper centers since...... the zeolite framework is very simple with only one crystallographically independent tetrahedral site (T-site). In this study the results of an X-band electron paramagnetic resonance (EPR) investigation of ion-exchanged Cu-CHA zeolite with a Si/Al ratio of 14 ± 1 is presented. Different dehydration treatments...... of the EPR silent monomeric Cu2+ in copper-substituted zeolites is suggested to be copper species with an approximate trigonal coordination sphere appearing during the dehydration. After complete dehydration at 250 °C the majority of the EPR silent Cu2+ is suggested to exist as Cu2+–OH– coordinated to two...

  11. Distribution and mobility of metals in contaminated sites. chemometric investigation of pollutant profiles.

    Science.gov (United States)

    Abollino, Ornella; Aceto, Maurizio; Malandrino, Mery; Mentasti, Edoardo; Sarzanini, Corrado; Barberis, Renzo

    2002-01-01

    The distribution and mobility of heavy metals in the soils of two contaminated sites in Piedmont (Italy) was investigated, evaluating the horizontal and vertical profiles of 15 metals, namely Al, Cd, Cu, Cr, Fe. La, Mn, Ni, Pb, Sc, Ti, V, Y, Zn and Zr. The concentrations in the most polluted areas of the sites were higher than the acceptable limits reported in Italian and Dutch legislations for soil reclamation. Chemometric elaboration of the results by pattern recognition techniques allowed us to identify groups of samples with similar characteristics and to find correlations among the variables. The pollutant mobility was studied by extraction with water, dilute acetic acid and EDTA and by applying Tessier's procedure. The fraction of mobile species, which potentially is the most harmful for the environment, was found to be higher than the one normally present in unpolluted soils, where heavy metals are, to a higher extent, strongly bound to the matrix.

  12. Streamlining: Reducing costs and increasing STS operations effectiveness

    Science.gov (United States)

    Petersburg, R. K.

    1985-01-01

    The development of streamlining as a concept, its inclusion in the space transportation system engineering and operations support (STSEOS) contract, and how it serves as an incentive to management and technical support personnel is discussed. The mechanics of encouraging and processing streamlining suggestions, reviews, feedback to submitters, recognition, and how individual employee performance evaluations are used to motivation are discussed. Several items that were implemented are mentioned. Information reported and the methodology of determining estimated dollar savings are outlined. The overall effect of this activity on the ability of the McDonnell Douglas flight preparation and mission operations team to support a rapidly increasing flight rate without a proportional increase in cost is illustrated.

  13. FInal Report: Site Investigation Results, 2009-2011, at Inman, Kansas

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Sciences Div.

    2015-05-01

    The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) operated a grain storage facility at the southern edge of the city of Inman, Kansas, from 1954 to 1965. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In 1997, trace to low levels of carbon tetrachloride (below the maximum contamination level [MCL] of 5.0 μg/L) were detected in three private wells near the former grain storage facility at Inman, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. No public water supply wells were identified in 1998 by the KDHE within 1 mi of the town. Carbon tetrachloride is the contaminant of primary concern at sites associated with grain storage operations. To determine whether the former CCC/USDA facility at Inman is a potential contaminant source and its possible relationship to the contamination in groundwater, the CCC/USDA agreed to conduct investigations at Inman. The investigations were performed by the Environmental Science Division of Argonne National Laboratory in accordance with the Intergovernmental Agreement between the KDHE and the Farm Service Agency of the USDA. Argonne, on behalf of the CCC/USDA, developed a Work Plan (Argonne 2007) and subsequently a Summary of Investigation Results and Proposed Work Plan (Appendix A) for a phased site investigation. The proposed work was approved by the KDHE (2007, 2011). The investigations were conducted from November 2009 to September 2011, as proposed in the two work plans. This report presents the findings of the 2009-2011 investigations at Inman.

  14. Review of the ANSTO submission on the site geological investigations for the RRR at Lucas Heights

    International Nuclear Information System (INIS)

    2002-01-01

    Preliminary Safety Analysis Report (PSAR) and ANSTO's Consolidated Seismic Report were reviewed by ARPANSA's Regulatory Branch, and by an IAEA consultant to ARPANSA. It included a recommendation by the IAEA Peer Review Team (June 2001) that an additional study be undertaken for the Lucas Heights site in accordance with IAEA Safety Guide 50-SG-S1. In particular this related to regional and local investigations to determine whether there exists a potential for surface faulting at the site area, to formulate the investigations that should be used to determine whether or not any faults in the area should be considered capable. The CEO of ARPANSA requested ANSTO to undertake such a task. The reviews that have been undertaken by experts from Geoscience Australia and the IAEA expert contracted by ARPANSA give confidence that the seismic design of the reactor structures, systems, and components important for safety should not be affected by the fault through the excavations for the foundations of the reactor building. The basis is the conclusions reached by these experts that the fault discovered is very old and not capable under either the USNRC Criteria or the IAEA Criteria. It is not now active, has not been active in the geologically recent past and is unlikely to re-activate within the foreseeable lifespan of the proposed facility. Consequently, this pre-existing fault presents no greater risk than the surrounding unfaulted material. Thus, the replacement reactor need not be designed for such displacement. The existence of this 'incapable' fault does not impact on the probabilistic seismic hazard assessment from which the seismic design basis for the reactor was derived. Therefore, the existing design response spectrum accepted in the Regulatory Assessment Report as the basis for seismic design of structures, systems and components, and approved in the Construction Licence, has not changed and remains adequately conservative with regard to vibratory motion at the site

  15. Streamline topology: Patterns in fluid flows and their bifurcations

    DEFF Research Database (Denmark)

    Brøns, Morten

    2007-01-01

    Using dynamical systems theory, we consider structures such as vortices and separation in the streamline patterns of fluid flows. Bifurcation of patterns under variation of external parameters is studied using simplifying normal form transformations. Flows away from boundaries, flows close to fix...... walls, and axisymmetric flows are analyzed in detail. We show how to apply the ideas from the theory to analyze numerical simulations of the vortex breakdown in a closed cylindrical container....

  16. Damage Detection with Streamlined Structural Health Monitoring Data

    OpenAIRE

    Li, Jian; Deng, Jun; Xie, Weizhi

    2015-01-01

    The huge amounts of sensor data generated by large scale sensor networks in on-line structural health monitoring (SHM) systems often overwhelms the systems’ capacity for data transmission and analysis. This paper presents a new concept for an integrated SHM system in which a streamlined data flow is used as a unifying thread to integrate the individual components of on-line SHM systems. Such an integrated SHM system has a few desirable functionalities including embedded sensor data compressio...

  17. Zephyr: A secure Internet process to streamline engineering

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, C.W.; Niven, W.A.; Cavitt, R.E. [and others

    1998-05-12

    Lawrence Livermore National Laboratory (LLNL) is implementing an Internet-based process pilot called `Zephyr` to streamline engineering and commerce using the Internet. Major benefits have accrued by using Zephyr in facilitating industrial collaboration, speeding the engineering development cycle, reducing procurement time, and lowering overall costs. Programs at LLNL are potentializing the efficiencies introduced since implementing Zephyr. Zephyr`s pilot functionality is undergoing full integration with Business Systems, Finance, and Vendors to support major programs at the Laboratory.

  18. A Streamlined Artificial Variable Free Version of Simplex Method

    OpenAIRE

    Inayatullah, Syed; Touheed, Nasir; Imtiaz, Muhammad

    2015-01-01

    This paper proposes a streamlined form of simplex method which provides some great benefits over traditional simplex method. For instance, it does not need any kind of artificial variables or artificial constraints; it could start with any feasible or infeasible basis of an LP. This method follows the same pivoting sequence as of simplex phase 1 without showing any explicit description of artificial variables which also makes it space efficient. Later in this paper, a dual version of the new ...

  19. Final Phase II report : QuickSite(R) investigation, Everest, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Research)

    2003-11-01

    this reason, the CCC/USDA is conducting an environmental site investigation to determine the source(s) and extent of the carbon tetrachloride contamination at Everest and to assess whether the contamination requires remedial action. The investigation at Everest is being performed by the Environmental Research Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by the University of Chicago for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an interagency agreement with DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. At these facilities, Argonne is applying its QuickSite{reg_sign} environmental site characterization methodology. This methodology has been applied successfully at a number of former CCC/USDA facilities in Kansas and Nebraska and has been adopted by the American Society for Testing and Materials (ASTM 1998) as standard practice for environmental site characterization. Phase I of the QuickSite{reg_sign} investigation examined the key geologic, hydrogeologic, and hydrogeochemical relationships that define potential contaminant migration pathways at Everest (Argonne 2001). Phase II of the QuickSite{reg_sign} investigation at Everest was undertaken with the primary goal of delineating and improving understanding of the distribution of carbon tetrachloride contamination in groundwater at this site and the potential source area(s) that might have contributed to this contamination. To address this goal, four specific technical objectives were developed to guide the Phase II field studies. Sampling of near-surface soils at the former Everest CCC/USDA facility that was originally planned for Phase I had to be postponed until October 2000 because of access restrictions. Viable vegetation was not available for sampling then. This period is termed the first session of Phase II

  20. Dividing Streamline Formation Channel Confluences by Physical Modeling

    Directory of Open Access Journals (Sweden)

    Minarni Nur Trilita

    2010-02-01

    Full Text Available Confluence channels are often found in open channel network system and is the most important element. The incoming flow from the branch channel to the main cause various forms and cause vortex flow. Phenomenon can cause erosion of the side wall of the channel, the bed channel scour and sedimentation in the downstream confluence channel. To control these problems needed research into the current width of the branch channel. The incoming flow from the branch channel to the main channel flow bounded by a line distributors (dividing streamline. In this paper, the wide dividing streamline observed in the laboratory using a physical model of two open channels, a square that formed an angle of 30º. Observations were made with a variety of flow coming from each channel. The results obtained in the laboratory observation that the width of dividing streamline flow is influenced by the discharge ratio between the channel branch with the main channel. While the results of a comparison with previous studies showing that the observation in the laboratory is smaller than the results of previous research.

  1. Corrective Action Investigation Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Patrick Matthews

    2011-08-01

    CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric Test Site T-7C; (2) 07-23-04, Atmospheric Test Site T7-1; (3) 07-23-05, Atmospheric Test Site; (4) 07-23-06, Atmospheric Test Site T7-5a; (5) 07-23-07, Atmospheric Test Site - Dog (T-S); (6) 07-23-08, Atmospheric Test Site - Baker (T-S); (7) 07-23-09, Atmospheric Test Site - Charlie (T-S); (8) 07-23-10, Atmospheric Test Site - Dixie; (9) 07-23-11, Atmospheric Test Site - Dixie; (10) 07-23-12, Atmospheric Test Site - Charlie (Bus); (11) 07-23-13, Atmospheric Test Site - Baker (Buster); (12) 07-23-14, Atmospheric Test Site - Ruth; (13) 07-23-15, Atmospheric Test Site T7-4; (14) 07-23-16, Atmospheric Test Site B7-b; (15) 07-23-17, Atmospheric Test Site - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison

  2. Geotechnical investigation for seismic issues for K-reactor area at Savannah River Site

    International Nuclear Information System (INIS)

    Castro, G.; Reeves, C.Q.

    1991-01-01

    A geotechnical investigation has been completed at Savannah River Site to characterize the foundation conditions in K-Reactor Area and confirm soil design properties for use in seismic qualification of structures. The scope of field work included ten soil borings to a 200-foot depth with split-spoon and undisturbed sampling. Additionally, 42 cone penetrometer tests were performed with seismic down-hole measurements. Three cross-hole shear wave velocity tests were also completed to confirm the assumed dynamic properties which had been used in preliminary seismic analysis

  3. Improvement of worker safety through the investigation of the site response to rockbursts.

    CSIR Research Space (South Africa)

    Durrheim, RJ

    1997-12-01

    Full Text Available Committee DRAFT FINAL REPORT Improvement of worker safety through the investigation of the site response to rockbursts R J Durrheim, A M Milev, S M Spottiswoode, and B Vakalisa Research agency CSIR: Division of Mining Technology Project number GAP2OI... in the application of current technology, such as numerical modelling for mine design, were also identified. It was also found that published guidelines, e.g. for pillar design, have limitations which are not explicitly stated. The performance of new technologies...

  4. Status of remedial investigation activities in the Hanford Site 300 Area groundwater operable unit

    International Nuclear Information System (INIS)

    Hulstrom, L.C.; Innis, B.E.; Frank, M.A.

    1993-09-01

    The Phase 1 remedial investigation (RI) and Phase 1 and 2 feasibility studies (FS) for the 300-FF-5 groundwater operable unit underlying the 300 Area on the Hanford Site have been completed. Analysis and evaluation of soil, sediment, and surface water, and biotic sampling data, groundwater chemistry, and radiological data gathered over the past 3 years has been completed. Risk assessment calculations have been performed. Use of the data gathered, coupled with information from an automated water level data collection system, has enabled engineers to track three plumes that represent the most significant contamination of the groundwater

  5. Corrective Action Investigation Plan for Corrective Action Unit 542: Disposal Holes, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Laura Pastor

    2006-01-01

    Corrective Action Unit (CAU) 542 is located in Areas 3, 8, 9, and 20 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 542 is comprised of eight corrective action sites (CASs): (1) 03-20-07, ''UD-3a Disposal Hole''; (2) 03-20-09, ''UD-3b Disposal Hole''; (3) 03-20-10, ''UD-3c Disposal Hole''; (4) 03-20-11, ''UD-3d Disposal Hole''; (5) 06-20-03, ''UD-6 and UD-6s Disposal Holes''; (6) 08-20-01, ''U-8d PS No.1A Injection Well Surface Release''; (7) 09-20-03, ''U-9itsy30 PS No.1A Injection Well Surface Release''; and (8) 20-20-02, ''U-20av PS No.1A Injection Well Surface Release''. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 30, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 542. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 542 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Conduct geophysical surveys to

  6. Corrective Action Investigation Plan for Corrective Action Unit 568: Area 3 Plutonium Dispersion Sites Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick

    2014-01-01

    CAU 568 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 568, which comprises the following corrective action sites (CASs): • 03-23-17, S-3I Contamination Area • 03-23-19, T-3U Contamination Area • 03-23-20, Otero Contamination Area • 03-23-22, Platypus Contamination Area • 03-23-23, San Juan Contamination Area • 03-23-26, Shrew/Wolverine Contamination Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report.

  7. Further investigations on the inorganic phosphate binding site of beef heart mitochondrial F1-ATPase

    International Nuclear Information System (INIS)

    Pougeois, R.; Lauquin, G.J.

    1985-01-01

    The possibility that 4-azido-2-nitrophenyl phosphate (ANPP), a photoreactive derivative of inorganic phosphate (P /sub i/ ), could mimic ATP was investigated. ANPP was hydrolyzed in the dark by sarcoplasmic reticulum Ca 2+ -ATPase in the presence of Ca 2+ but not in the presence of ethylene glycol bis(beta-aminoethyl ether)-N,N,N',N'-tetraacetic acid. ANPP was not hydrolyzed by purified mitochondrial F1-ATPase; however, ADP and ATP protected F1-ATPase against ANPP photoinactivation. On the other hand, the trinitrophenyl nucleotide analogues (TNP-ADP, TNP-ATP, and TNP-AMP-PNP), which bind specifically at the two catalytic sites of F1-ATPase, abolished P /sub i/ binding on F1-ATPase; they do not protect F1-ATPase against ANPP photoinactivation. Furthermore, ANPP-photoinactivated F1-ATPase binds the TNP analogues in the same way as the native enzyme. The Pi binding site of F1-ATPase, which is shown to be photolabeled by ANPP, does not appear to be at the gamma-phosphate position of the catalytic sites

  8. Geoarchaeological investigation at Al-Khiday (central Sudan): late Quaternary palaeoenvironment and site formation

    Science.gov (United States)

    Zerboni, Andrea; Usai, Donatella; Salvatori, Sandro

    2010-05-01

    The micromorphological investigation on several pluristratified archaeological sites in central Sudan (Al-Khiday, left bank of the White Nile, Khartoum region, Sudan) permitted to elucidate depositional and post-depositional processes playing a role in the formation and preservation of the archaeological record. At Al-Khiday sites are located at the top of small mounds, representing the remains of Pleistocene sandy fluvial bars, and were attended since the beginning of the Holocene. The first occupation of the area corresponds to a pre-Mesolithic cemetery; than Mesolithic groups lived upon the mounds and their occupation is testified by several archaeological features: pits filled by ash and bones and living floors. Preserved Neolithic features are scarce and limited to few graves (V millennium BC). After this phase, a long gap in human attendance is registered, during which wind continued to dismantling the mounds and the sites; at ca. 2000 years BP Meroitic/Post-Meroitic groups built their tombs at the top of the archaeological sequences and altered most of the stratigraphic record. Thanks to micromorphology, it was possible to distinguish between archaeological strata still in situ and those disturbed by natural and anthropic processes; furthermore, this approach allowed to interpret the significance of several archaeological features (living floors, fireplaces, and garbage pits). In this case micromorphology of archaeological deposits was a key tool to reconstruct the depositional and post-depositional processes that contributed to the formation and preservation of the archaeological record.

  9. Animal Investigation Program 1973 annual report: Nevada Test Site and vicinity

    International Nuclear Information System (INIS)

    Smith, D.D.; Giles, K.R.; Bernhardt, D.E.

    1977-05-01

    Data are presented from the radioanalysis of tissues collected from cattle, deer, desert bighorn sheep, and other wildlife that resided on or near the Nevada Test Site during 1973. Routine activities and special investigations are discussed. Iodine-131 was detected in the thyroid of a Nevada Test Site mule deer. The postulated source was worldwide fallout from a nuclear detonation conducted by the People's Republic of China. Other than the naturally occurring potassium-40, cesium-137 was the only gamma-emitting radionuclide detected with any consistency in soft tissues. Nine muscle samples from the Nevada Test Site beef herd contained levels of cesium-137 ranging from 14 to 50 pCi/kilogram. Muscle from two deer contained 20 and 30 pCi/kilogram. Rabbit muscle contained 200 pCi/kilogram and muscle from a feral horse contained 40 pCi/kilogram. Tritium levels in all animal tissues sampled were at background except for animals residing at the Area 15 farm and for a feral horse. Postulated sources of these exposures are discussed. The strontium content in bones continued the downward trend observed during recent years

  10. Improving archaeological site analysis: a rampart in the middle Orkhon Valley investigated with combined geoscience techniques

    International Nuclear Information System (INIS)

    Grützner, C; Bemmann, J; Reichert, S; Berking, J; Klinger, R; Frechen, M; Schütt, B; Klitzsch, N; Linzen, S; Schneider, M; Mackens, S; Oczipka, M; Piezonka, H

    2012-01-01

    The Orkhon Valley in the Central Mongolia was included in the World Heritage list in 2004. It hosts multiple archaeological sites from Palaeolithic to recent times, which can contribute to the reconstruction of settlement history in this part of the Eurasian Steppe landscape. Almost 100 archaeological sites from prehistoric and historic times including ramparts and khirigsuurs were investigated in five field campaigns from 2008 to 2010 in the middle and upper Orkhon Valley. One site, MOR-2 (Dörvölzhin), proved especially difficult to date due to the lack of sufficient archaeological surface finds, and its role within a manifold of walled enclosures from different times in the study area remained unclear. Therefore, different techniques of archaeology, geophysics and geoarchaeology were combined at MOR-2 in order to determine a comprehensive picture about its timing, archaeological meaning, and environmental history. Information on topographical setting and morphometry of the rampart was gathered by an octocopter equipped with a high-resolution range finder camera. We achieved a high-resolution DEM that allowed us to map the rampart in detail and this served as a base map for all other investigations. SQUID magnetometry, ground-penetrating radar, and electric resistivity measurements (capacitive coupled geoelectrics) were subsequently used to detect archaeological remains and to characterize the sediment distribution of the inner part of the enclosure and the ramparts themselves. The data show that the construction of the walls is similar to well-known Uighur neighbouring sites. Man-made sub-surface structures or bigger finds could not be detected. Sediment cores were drilled in a nearby meander, covering 3000 years BP. The analysis of the strata in terms of elemental composition (P, N, Mn, Fe, etc) revealed an increase of organic content in Medieval times, whereas the allochthonous filling of the back water must have started around the beginning of the 6th

  11. Radiological investigations at the 'Taiga' nuclear explosion site: Site description and in situ measurements

    Energy Technology Data Exchange (ETDEWEB)

    Ramzaev, V., E-mail: V.Ramzaev@mail.ru [Institute of Radiation Hygiene, Mira str. 8, 197101 St.-Petersburg (Russian Federation); Repin, V.; Medvedev, A.; Khramtsov, E.; Timofeeva, M.; Yakovlev, V. [Institute of Radiation Hygiene, Mira str. 8, 197101 St.-Petersburg (Russian Federation)

    2011-07-15

    In the summer of 2009, we performed a field survey of the 'Taiga' peaceful underground nuclear explosion site, the Perm region, Russia (61.30{sup o} N, 56.60{sup o} E). The explosion was carried out by the USSR in 1971. This paper provides an extended summary of the available published data on the 'Taiga' experiment. A detailed description of the site is illustrated by original aerial and ground-level photos. A large artificial lake (700 m long and 350 m wide) currently occupies the central area of the experimental site. The ground lip surrounding the lake is covered by a newly grown mixed forest. In situ measurements, performed in August 2009, revealed elevated levels of the {gamma}-ray dose rate in air on the banks of the lake 'Taiga'. Two hot spots were detected on the eastern bank of the lake. The excess of the {gamma}-ray radiation is attributable to the man-made radionuclides {sup 60}Co and {sup 137}Cs. The current external {gamma}-ray dose rate to a human from the contaminations associated with the 'Taiga' experiment was between 9 and 70 {mu}Sv per week. Periodic monitoring the site is recommended. - Highlights: > We studied a radiation anomaly at the 'Taiga' underground nuclear explosion site. > The anomaly currently has an area of approximately 1 km{sup 2}. > The excess of {gamma}-ray radiation at the site is mainly attributable to {sup 60}Co and {sup 137}Cs. > The external effective dose may currently exceed the negligible value of 10 {mu}Sv y{sup -1}.

  12. Design of quality assurance surveillance of geotechnical investigation in evaluation of nuclear power plants siting

    International Nuclear Information System (INIS)

    Made Pramayuni; Haendra Subekti

    2011-01-01

    System of building Nuclear Power Plants (NPP) is built above ground surface and rocks. Therefore, the geotechnical aspects evaluation of NPP siting in particular must be implemented properly and accurately. The successful of the design and construction of the building system is influenced by geotechnical conditions in the vicinity of NPP will be built. To be able to perform geotechnical analysis is good and true; it's required data of surface/underground completely. These data can be obtained directly not only from the geotechnical field investigations, but also can be obtained from the laboratory tests results. To ensure that geotechnical investigations are conducted effectively and efficiently, produce accurate data, as well as meeting the requirements of safety, health, safety, environmental, quality and economic, then the Quality Assurance Program (QAP) should be established and implemented. Supervision of the QAP implementation is required to ensure the work is done according to QAP that have been established and applicable requirement. (author)

  13. Radionuclide migration in fractured rock: hydrological investigations at an experimental site in the Carnmennellis granite, Cornwall

    International Nuclear Information System (INIS)

    Heath, M.J.; Durrance, E.M.

    1985-01-01

    The objectives, methods and results of hydrological investigation of the granite at an experimental site in Cornwall are described and discussed. Constant head injection tests and radioactive tracer experiments have revealed a fracture permeability in which water movement is confined to discrete fractures separated by rock of very low permeability. Data on flow path frequency, orientation and effective hydraulic aperture, required for network modelling, are presented for a 700 m borehole, with additional hydraulic data from three other boreholes. In addition to fractures of average hydraulic conductivity a small number of major hydraulic features (''main drains'') with major implications for radionuclide migration have been identified. A mean hydraulic conductivity for the granite investigated of 1.57x10 -7 ms -1 has been obtained, 2.11x10 -8 ms -1 if the major hydraulic features are excluded

  14. A summary of ecological investigations at the burial ground complex, Savannah River Site - 1994

    Energy Technology Data Exchange (ETDEWEB)

    Friday, G.P.; Hartman, G.D.; Mackey, H.E. Jr.; Riley, R.S.; Roach, J.L.; Specht, W.L.; Westbury, H.M.; Wike, L.D.

    1994-11-01

    This report summarizes the results of three ecological investigations that were conducted in 1994 at the Burial Ground Complex (BGC) at the Savannah River Site (SRS). The three topics of study included remote sensing, aquatic toxicity testing, and qualitative surveys of herpetofauna and small mammals. Interim reports from each investigation are included in the appendices (A, B, and C). The objectives of the remote sensing effort were to compile historical aerial photography of the BGC and to develop a land use/cover map of the complex using recent aerial imagery. The goal of the aquatic toxicity testing was to determine if surface waters were toxic to aquatic biota whereas the objectives of the vertebrate surveys were to identify the species diversity and relative abundances of amphibians, reptiles, and small mammals inhabiting the study area.

  15. A summary of ecological investigations at the burial ground complex, Savannah River Site - 1994

    International Nuclear Information System (INIS)

    Friday, G.P.; Hartman, G.D.; Mackey, H.E. Jr.; Riley, R.S.; Roach, J.L.; Specht, W.L.; Westbury, H.M.; Wike, L.D.

    1994-11-01

    This report summarizes the results of three ecological investigations that were conducted in 1994 at the Burial Ground Complex (BGC) at the Savannah River Site (SRS). The three topics of study included remote sensing, aquatic toxicity testing, and qualitative surveys of herpetofauna and small mammals. Interim reports from each investigation are included in the appendices (A, B, and C). The objectives of the remote sensing effort were to compile historical aerial photography of the BGC and to develop a land use/cover map of the complex using recent aerial imagery. The goal of the aquatic toxicity testing was to determine if surface waters were toxic to aquatic biota whereas the objectives of the vertebrate surveys were to identify the species diversity and relative abundances of amphibians, reptiles, and small mammals inhabiting the study area

  16. Biologic overview for the Nevada Nuclear Waste Storage Investigations, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Collins, E.; O'Farrell, T.P.; Rhoads, W.A.

    1982-01-01

    The Nevada Nuclear Waste Storage Investigations project study area includes five major vegetation associations characteristic of the transition between the northern extent of the Mojave Desert and the southern extent of the Great Basin Desert. A total of 32 species of reptiles, 66 species of birds, and 46 species of mammals are known to occur within these associations elsewhere on the Nevada Test Site. Ten species of plants, and the mule deer, wild horse, feral burro, and desert tortoise were defined as possible sensitive species because they are protected by federal and state regulations, or are being considered for such protection. The major agricultural resources of southern Nye County included 737,000 acres of public grazing land managed by the Bureau of Land Management, and 9500 acres of irrigated crop land located in the Beatty/Oasis valleys, the Amargosa Valley, and Ash Meadows. Range lands are of poor quality. Alfalfa and cotton are the major crops along with small amounts of grains, Sudan grass, turf, fruits, and melons. The largest impacts to known ecosystems are expected to result from: extensive disturbances associated with construction of roads, seismic lines, drilling pads, and surface facilities; storage and leaching of mined spoils; disposal of water; off-road vehicle travel; and, over several hundred years, elevated soil temperatures. Significant impacts to off-site areas such as Ash Meadows are anticipated if new residential developments are built there to accommodate an increased work force. Several species of concern and their essential habitats are located at Ash Meadows. Available literature contained sufficient baseline information to assess potential impacts of the proposed project on an area-wide basis. It was inadequate to support analysis of potential impacts on specific locations selected for site characterization studies, mining an exploratory shaft, or the siting and operation of a repository

  17. Corrective Action Investigation Plan for the CNTA Subsurface Sites (CAU Number 443), Revision 1; FINAL

    International Nuclear Information System (INIS)

    1999-01-01

    This Corrective Action Investigation Plan (CAIP) describes the U.S. Department of Energy's (DOE's) planned environmental investigation of the subsurface Central Nevada Test Area (CNTA) Corrective Action Unit (CAU) No. 443. The CNTA is located in Hot Creek Valley in Nye County, Nevada, adjacent to U.S. Highway 6, about 48 kilometers (km) (30 miles[mi]) north of Warm Springs, Nevada. The CNTA was the site of Project Faultless, a nuclear device detonated in the subsurface by the U.S. Atomic Energy Commission (AEC) in January 1968. The purposes of this test were to gauge the seismic effects of a relatively large, high-yield detonation completed in Hot Creek Valley (outside the Nevada Test Site) and to determine the suitability of the site for future large detonations. The yield of the Faultless test was between 200 kilotons and 1 megaton. Two similar tests were planned for the CNTA, but neither of them was completed. Based on the general definition of a corrective action investigation (CAI) from Section IV.14 of the Federal Facility Agreement and Consent Order (FFACO), the purpose of the CAI is ''to gather data sufficient to characterize the nature, extent, and rate of migration or potential rate of migration from releases or discharges of pollutants or contaminants and/or potential releases or discharges from corrective action units identified at the facilities''. For CNTA CAU 443 the concepts developed for the Underground Test Area (UGTA) CAUs will be applied on a limited scale. For the UGTA CAUs, ''the objective of the CAI process is to define boundaries around each UGTA CAU that establish areas that contain water that may be unsafe for domestic and municipal use,'' as stated in Appendix VI of the FFACO (1996). Based on this strategy the CAI for CAU 443 will start with modeling using existing data. New data collection activities are generally contingent upon the results of the modeling and may or may not be part of the CAI. Specific objectives of the CAI ar e as

  18. Analysis of ASR Clogging Investigations at Three Australian ASR Sites in a Bayesian Context

    Directory of Open Access Journals (Sweden)

    Peter Dillon

    2016-10-01

    Full Text Available When evaluating uncertainties in developing an aquifer storage and recovery (ASR system, under normal budgetary constraints, a systematic approach is needed to prioritise investigations. Three case studies where field trials have been undertaken, and clogging evaluated, reveal the changing perceptions of viability of ASR from a clogging perspective as a result of the progress of investigations. Two stormwater and one recycled water ASR investigations in siliceous aquifers are described that involved different strategies to evaluate the potential for clogging. This paper reviews these sites, as well as earlier case studies and information relating water quality, to clogging in column studies. Two novel theoretical concepts are introduced in the paper. Bayesian analysis is applied to demonstrate the increase in expected net benefit in developing a new ASR operation by undertaking clogging experiments (that have an assumed known reliability for predicting viability for the injectant treatment options and aquifer material from the site. Results for an example situation demonstrate benefit cost ratios of experiments ranging from 1.5 to 6 and apply if decisions are based on experimental results whether success or failure are predicted. Additionally, a theoretical assessment of clogging rates characterised as acute and chronic is given, to explore their combined impact, for two operating parameters that define the onset of purging for recovery of reversible clogging and the onset of occasional advanced bore rehabilitation to address recovery of chronic clogging. These allow the assessment of net recharge and the proportion of water purged or redeveloped. Both analyses could inform economic decisions and help motivate an improved investigation methodology. It is expected that aquifer heterogeneity will result in differing injection rates among wells, so operational experience will ultimately be valuable in differentiating clogging behaviour under

  19. Investigation of off-site airborne transport of lead from a superfund removal action site using lead isotope ratios and concentrations

    Science.gov (United States)

    Pribil, Michael J.; Maddaloni, Mark A.; Staiger, Kimberly; Wilson, Eric; Magriples, Nick; Ali, Mustafa; Santella, Dennis

    2014-01-01

    Lead (Pb) concentration and Pb isotopic composition of surface and subsurface soil samples were used to investigate the potential for off-site air transport of Pb from a former white Pb processing facility to neighboring residential homes in a six block area on Staten Island, NY. Surface and subsurface soil samples collected on the Jewett White Pb site were found to range from 1.122 to 1.138 for 206Pb/207Pb and 2.393 to 2.411 for 208Pb/207Pb. The off-site surface soil samples collected from residential backyards, train trestle, near site grass patches and background areas varied from 1.144 to 1.196 for 206Pb/207Pb and 2.427 to 2.464 for 208Pb/207Pb. Two soil samples collected along Richmond Terrace, where Jewett site soils accumulated after major rain events, varied from 1.136 to 1.147 for 206Pb/207Pb and 2.407 to 2.419 for 208Pb/207Pb. Lead concentration for on-site surface soil samples ranged from 450 to 8000 ug/g, on-site subsurface soil samples ranged from 90,000 to 240,000 ug/g and off-site samples varied from 380 to 3500 ug/g. Lead concentration and isotopic composition for the Staten Island off-site samples were similar to previously published data for other northeastern US cities and reflect re-suspension and re-mobilization of local accumulated Pb. The considerable differences in both the Pb isotopic composition and Pb concentration of on-site and off-site samples resulted in the ability to geochemically trace the transport of particulate Pb. Data in this study indicate minimal off-site surface transport of Pb from the Jewett site into the neighboring residential area.

  20. Different integrated geophysical approaches to investigate archaeological sites in urban and suburban area.

    Science.gov (United States)

    Piro, Salvatore; Papale, Enrico; Zamuner, Daniela

    2016-04-01

    Geophysical methods are frequently used in archaeological prospection in order to provide detailed information about the presence of structures in the subsurface as well as their position and their geometrical reconstruction, by measuring variations of some physical properties. Often, due to the limited size and depth of an archaeological structure, it may be rather difficult to single out its position and extent because of the generally low signal-to-noise ratio. This problem can be overcome by improving data acquisition, processing techniques and by integrating different geophysical methods. In this work, two sites of archaeological interest, were investigated employing several methods (Ground Penetrating Radar (GPR), Electrical Resistivity Tomography (ERT), Fluxgate Differential Magnetic) to obtain precise and detailed maps of subsurface bodies. The first site, situated in a suburban area between Itri and Fondi, in the Aurunci Natural Regional Park (Central Italy), is characterized by the presence of remains of past human activity dating from the third century B.C. The second site, is instead situated in an urban area in the city of Rome (Basilica di Santa Balbina), where historical evidence is also present. The methods employed, allowed to determine the position and the geometry of some structures in the subsurface related to this past human activity. To have a better understanding of the subsurface, we then performed a qualitative and quantitative integration of this data, which consists in fusing the data from all the methods used, to have a complete visualization of the investigated area. Qualitative integration consists in graphically overlaying the maps obtained by the single methods; this method yields only images, not new data that may be subsequently analyzed. Quantitative integration is instead performed by mathematical and statistical solutions, which allows to have a more accurate reconstruction of the subsurface and generates new data with high

  1. Non-invasive shallow seismic source comparison for hazardous waste site investigations

    International Nuclear Information System (INIS)

    Doll, W.E.

    1994-01-01

    Many commonly used shallow seismic sources are unacceptable for hazardous waste site investigations because they risk exhumation of contaminants in the soil, they add contaminants (e.g. lead) which are not allowed by regulations, or they add new migration paths for contaminants. Furthermore, recently developed high frequency vibrators for shallow investigations could be more effective at some sites than non-invasive impulsive sources because of their ability to tailor the source spectrum and reduce interference. The authors show preliminary results of a comparison test of eight non-invasive impulsive and swept sources in preparation for seismic reflection profiling on the Oak Ridge Reservation, Tennessee. Well log data are used to determine geologic contacts and to generate synthetic seismograms for the site. Common midpoint (CMP) seismic data for each source were collected at 95 geophone groups from 125 shot points along a 400m test line. Hydrophone data were obtained at 1.5m spacing between 61m and 133m depth in a hole near the center of the CMP line. As of March, 1994, brute stacks have been completed for three of the eight sources. Depth penetration is demonstrated in brute stacks and shot gathers, which show a 200ms reflector for all of the sources tested along portions of the line. Source effectiveness will also be evaluated by comparing images of several shallower reflectors (40--150ms) which are apparent in many of the records. Imaging of these reflectors appears to depend upon the ability of the source to generate sufficient high frequency energy (>100 Hz)

  2. Archival Investigation of Outburst Sites and Progenitors of Extragalactic Intermediate-Luminosity Mid-IR Transients

    Science.gov (United States)

    Bond, Howard

    2017-08-01

    Our team is using Spitzer in a long-term search for extragalactic mid-infrared (MIR) variable stars and transients-the SPIRITS project (SPitzer InfraRed Intensive Transients Survey). In this first exploration of luminous astrophysical transients in the infrared, we have discovered a puzzling new class. We call them SPRITEs: eSPecially Red Intermediate-luminosity Transient Events. They have maximum MIR luminosities between supernovae and classical novae, but are not detected in the optical to deep limits. To date, we have discovered more than 50 SPRITEs in galaxies out to 17 Mpc. In this Archival Research proposal, we request support in order to investigate the pre-eruption sites in HST images of some 3 dozen SPRITEs discovered to date, and an additional 2 dozen that we are likely to find until the end of Spitzer observing in late 2018. Our aims are (1) characterize the pre-outburst environments at HST resolution in the visible and near-IR, to understand the stellar populations, stellar ages and masses, and interstellar medium at the outburst sites; (2) search for progenitors; (3) help prepare the way for a better understanding of the nature of extragalactic IR transients that will be investigated by JWST.

  3. Cavola experiment site: geophysical investigations and deployment of a dense seismic array on a landslide

    Directory of Open Access Journals (Sweden)

    L. Martelli

    2007-06-01

    Full Text Available Geophysical site investigations have been performed in association with deployment of a dense array of 95 3-component seismometers on the Cavola landslide in the Northern Apennines. The aim of the array is to study propagation of seismic waves in the heterogeneous medium through comparison of observation and modelling. The small-aperture array (130 m×56 m operated continuously for three months in 2004. Cavola landslide consists of a clay body sliding over mudstone-shale basement, and has a record of historical activity, including destruction of a small village in 1960. The site investigations include down-hole logging of P- and S-wave travel times at a new borehole drilled within the array, two seismic refraction lines with both P-wave profiling and surface-wave analyses, geo-electrical profiles and seismic noise measurements. From the different approaches a consistent picture of the depths and seismic velocities for the landslide has emerged. Their estimates agree with resonance frequencies of seismic noise, and also with the logged depths to basement of 25 m at a new borehole and of 44 m at a pre-existing borehole. Velocities for S waves increase with depth, from 230 m/s at the surface to 625 m/s in basement immediately below the landslide.

  4. 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

  5. Corrective Action Investigation Plan for Corrective Action Unit 571: Area 9 Yucca Flat Plutonium Dispersion Sites, Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, Bernadine; Matthews, Patrick

    2013-07-01

    CAU 571 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 571, which comprises the following corrective action sites (CASs): • 09-23-03, Atmospheric Test Site S-9F • 09-23-04, Atmospheric Test Site T9-C • 09-23-12, Atmospheric Test Site S-9E • 09-23-13, Atmospheric Test Site T-9D • 09-45-01, Windrows Crater These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on March 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (now the Nevada Field Office). The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 571. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 571 CASs are from nuclear testing activities. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary exceeds the final action level (FAL) and requires corrective action. The presence and nature of contamination outside the default

  6. 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

  7. 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

  8. Integrated account of method, site selection and programme prior to the site investigation phase[Planning for a Swedish repository for spent nuclear fuels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    In order to dispose of the spent nuclear fuel in a safe manner, SKB plans to site a deep repository and an encapsulation plant with associated canister fabrication and transportation system. After an integrated evaluation of feasibility studies and other material, SKB will proceed with investigations of the rock and studies regarding establishment of the deep disposal system in the municipality of Oskarshamn or in Northern Uppland. The plans also include further study of the prospects for a deep repository in the municipality of Nykoeping. In the municipality of Oskarshamn, SKB plans further studies of a siting of the deep repository at Simpevarp. There SKB wants to initiate site investigations with test drilling. For the encapsulation plant, SKB wants to continue studying a siting at CLAB. In Northern Uppland, SKB plans to study two siting alternatives for the deep repository. One is Forsmark in the municipality of Oesthammar, where SKB wants to initiate a site investigation with test drilling. The other is Tierp north of Skutskaer, where SKB intends to start test drilling in an area north of Tierp. First, however, a suitable drilling area with possible transport solutions needs to be defined. This alternative requires the participation of the municipalities of both Tierp and Aelvkarleby. A siting of the encapsulation plant in Northern Uppland will also be studied. For the municipality of Nykoeping, SKB plans to conduct a new safety assessment for the Fjaellveden area, based on data from previous investigations as well as additional studies of how a deep repository could be arranged. SKB will thereby gather data from yet another geographic and geological region beyond those that are prioritized. No test drilling is planned in Nykoeping. The goal of the site investigation phase is to obtain all permits needed to build the planned facilities. It will take an estimated 7 - 8 years to assemble the requisite supporting material, carry out consultations, compile siting

  9. Detailed imaging of flowing structures at depth using microseismicity: a tool for site investigation?

    Science.gov (United States)

    Pytharouli, S.; Lunn, R. J.; Shipton, Z. K.

    2011-12-01

    Field evidence shows that faults and fractures can act as focused pathways or barriers for fluid migration. This is an important property for modern engineering problems, e.g., CO2 sequestration, geological radioactive waste disposal, geothermal energy exploitation, land reclamation and remediation. For such applications the detailed characterization of the location, orientation and hydraulic properties of existing fractures is necessary. These investigations are expensive, requiring the hire of expensive equipment (excavator or drill rigs), which incur standing charges when not in use. In addition, they only provide information for discrete sample 'windows'. Non-intrusive methods have the ability to gather information across an entire area. Methods including electrical resistivity/conductivity and ground penetrating radar (GRP), have been used as tools for site investigations. Their imaging ability is often restricted due to unfavourable on-site conditions e.g. GRP is not useful in cases where a layer of clay or reinforced concrete is present. Our research has shown that high quality seismic data can be successfully used in the detailed imaging of sub-surface structures at depth; using induced microseismicity data recorded beneath the Açu reservoir in Brazil we identified orientations and values of average permeability of open shear fractures at depths up to 2.5km. Could microseismicity also provide information on the fracture width in terms of stress drops? First results from numerical simulations showed that higher stress drop values correspond to narrower fractures. These results were consistent with geological field observations. This study highlights the great potential of using microseismicity data as a supplementary tool for site investigation. Individual large-scale shear fractures in large rock volumes cannot currently be identified by any other geophysical dataset. The resolution of the method is restricted by the detection threshold of the local

  10. Lake and lake-related drainage area parameters for site investigation program

    International Nuclear Information System (INIS)

    Blomqvist, P.; Brunberg, A.K.; Brydsten, L

    2000-09-01

    In this paper, a number of parameters of importance to a preliminary determination of the ecological function of lakes are presented. The choice of parameters have been made with respect to a model for the determination of the nature conservation values of lakes which is currently being developed by the authors of this report, but is also well suited for a general description of the lake type and the functioning of the inherent ecosystem. The parameters have been divided into five groups: 1) The location of the object relative important gradients in the surrounding nature; 2) The lake catchment area and its major constituents; 3) The lake morphometry; 4) The lake ecosystem; 5) Human-induced damages to the lake ecosystem. The first two groups, principally based on the climate, hydrology, geology and vegetation of the catchment area represent parameters that can be used to establish the rarity and representativity of the lake, and will in the context of site investigation program be used as a basis for generalisation of the results. The third group, the lake morphometry parameters, are standard parameters for the outline of sampling programmes and for calculations of the physical extension of different key habitats in the system. The fourth group, the ecosystem of the lake, includes physical, chemical and biological parameters required for determination of the stratification pattern, light climate, influence from the terrestrial ecosystem of the catchment area, trophic status, distribution of key habitats, and presence of fish and rare fauna and flora in the lake. In the context of site investigation program, the parameters in these two groups will be used for budget calculations of the flow of energy and material in the system. The fifth group, finally, describes the degree on anthropogenic influence on the ecosystem and will in the context of site investigation programmes be used to judge eventual malfunctioning within the entire, or parts of, the lake ecosystem

  11. Lake and lake-related drainage area parameters for site investigation program

    Energy Technology Data Exchange (ETDEWEB)

    Blomqvist, P.; Brunberg, A.K. [Uppsala Univ. (Sweden). Dept. of Limnology; Brydsten, L [Umeaa Univ. (Sweden). Dept. of Ecology and Environmental Science

    2000-09-01

    In this paper, a number of parameters of importance to a preliminary determination of the ecological function of lakes are presented. The choice of parameters have been made with respect to a model for the determination of the nature conservation values of lakes which is currently being developed by the authors of this report, but is also well suited for a general description of the lake type and the functioning of the inherent ecosystem. The parameters have been divided into five groups: (1) The location of the object relative important gradients in the surrounding nature; (2) The lake catchment area and its major constituents; (3) The lake morphometry; (4) The lake ecosystem; (5) Human-induced damages to the lake ecosystem. The first two groups, principally based on the climate, hydrology, geology and vegetation of the catchment area represent parameters that can be used to establish the rarity and representativity of the lake, and will in the context of site investigation program be used as a basis for generalisation of the results. The third group, the lake morphometry parameters, are standard parameters for the outline of sampling programmes and for calculations of the physical extension of different key habitats in the system. The fourth group, the ecosystem of the lake, includes physical, chemical and biological parameters required for determination of the stratification pattern, light climate, influence from the terrestrial ecosystem of the catchment area, trophic status, distribution of key habitats, and presence of fish and rare fauna and flora in the lake. In the context of site investigation program, the parameters in these two groups will be used for budget calculations of the flow of energy and material in the system. The fifth group, finally, describes the degree on anthropogenic influence on the ecosystem and will in the context of site investigation programmes be used to judge eventual malfunctioning within the entire, or parts of, the lake

  12. A summary of INSITE activities in tracking SKB's spent fuel repository site investigations from 2002-2009 and of advice provided to the regulatory authorities on the status of site understanding at the end of the surface-based investigations

    International Nuclear Information System (INIS)

    Chapman, Neil; Bath, Adrian; Geier, Joel; Ove Stephansson; Tiren, Sven; Tsang, Chin-Fu

    2010-11-01

    SSM and its predecessor SKI employed a team of earth scientists who followed and reviewed SKB's investigations of the potential spent nuclear fuel repository sites at Forsmark and Laxemar. This group was named INSITE (INdependent Site Investigation Tracking and Evaluation) and began its work in 2002 and completed its task with the review of the final versions SKB's site descriptive models, SDM-Site, in 2009. This report is a summary of INSITE's work over the eight-and-a-half year period of the site investigations and the lead-in and the wind-down to the work. It is intended to provide an outline and a record of how INSITE has worked and how its advice was generated and provided to SKI and, latterly, to SSM. Together with all the other documentation generated by INSITE, this report is intended to support the regulatory review of SKB's licence application for a spent nuclear fuel repository

  13. Analysis of Critical Issues in Biosphere Assessment Modelling and Site Investigation

    Energy Technology Data Exchange (ETDEWEB)

    Egan, M.J.; Thorne, M.C.; Little, R.H.; Pasco, R.F. [Quintessa Limited, Henley-on-Thames (United Kingdom)

    2003-07-01

    The aim of this document is to present a critical review of issues concerned with the treatment of the biosphere and geosphere-biosphere interface in long-term performance assessment studies for nuclear waste disposal in Sweden. The review covers three main areas of investigation: a review of SKB's plans for undertaking site investigations at candidate locations for the development of a deep geological repository for spent fuel; identification of critical uncertainties associated with SKB's treatment of the geosphere-biosphere interface in recent performance assessments; and a preliminary modelling investigation of the significance of features, events and processes in the near-surface environment in terms of their effect on the accumulation and redistribution of radionuclides at the geosphere-biosphere interface. Overall, SKB's proposals for site investigations are considered to be comprehensive and, if they can be carried out to the specification presented, will constitute a benchmark that other waste management organisations will have to work hard to emulate. The main concern is that expertise for undertaking the investigations and reporting the results could be stretched very thin. The authors have also identified weaknesses in the documentation concerning the collection of evidence for environmental change and on developing scenarios for future environmental change. A fundamental assumption adopted in the renewed assessment of the SFR 1 repository, which is not discussed or justified in any of the documentation that has been reviewed, is that radionuclides enter the water column of the coastal and lake models directly, without passing first through the bed sediments. The modelling study reported herein suggests that SKB's models are robust to range of alternative conceptual descriptions relating to the geosphere-biosphere interface. There are however situations, in which contaminated groundwater is released via sediment rather than directly

  14. Analysis of Critical Issues in Biosphere Assessment Modelling and Site Investigation

    International Nuclear Information System (INIS)

    Egan, M.J.; Thorne, M.C.; Little, R.H.; Pasco, R.F.

    2003-07-01

    The aim of this document is to present a critical review of issues concerned with the treatment of the biosphere and geosphere-biosphere interface in long-term performance assessment studies for nuclear waste disposal in Sweden. The review covers three main areas of investigation: a review of SKB's plans for undertaking site investigations at candidate locations for the development of a deep geological repository for spent fuel; identification of critical uncertainties associated with SKB's treatment of the geosphere-biosphere interface in recent performance assessments; and a preliminary modelling investigation of the significance of features, events and processes in the near-surface environment in terms of their effect on the accumulation and redistribution of radionuclides at the geosphere-biosphere interface. Overall, SKB's proposals for site investigations are considered to be comprehensive and, if they can be carried out to the specification presented, will constitute a benchmark that other waste management organisations will have to work hard to emulate. The main concern is that expertise for undertaking the investigations and reporting the results could be stretched very thin. The authors have also identified weaknesses in the documentation concerning the collection of evidence for environmental change and on developing scenarios for future environmental change. A fundamental assumption adopted in the renewed assessment of the SFR 1 repository, which is not discussed or justified in any of the documentation that has been reviewed, is that radionuclides enter the water column of the coastal and lake models directly, without passing first through the bed sediments. The modelling study reported herein suggests that SKB's models are robust to range of alternative conceptual descriptions relating to the geosphere-biosphere interface. There are however situations, in which contaminated groundwater is released via sediment rather than directly to the water column

  15. Investigation of well redevelopment techniques for the MWD Well Field, Savannah River Site, South Carolina

    International Nuclear Information System (INIS)

    Kroening, D.E.; Snipes, D.S.; Falta, R.W.; Benson, S.M.

    1994-01-01

    Clemson University, in cooperation with the Savannah River Site (SRS) is investigating well treatment techniques at the Mixed Waste Disposal (MWD) Well Field at SRS. This well field consists of fifteen wells screened in three aquifers with a downward trending head gradient. Based on aquifer performance tests of the MWD wells, it has been determined that many of the wells exhibit low well efficiencies and high skin factors, indicative of damaged wells. Bacterial investigations show that the biological activity in these wells is low, probably due to a high pH environment. Evaluation of the Calcite Saturation Index for each well indicates that nearly all of the MWD wells have the potential for precipitating calcite and calcite deposits have been observed on downhole equipment. The calcite deposits may occur due to the dissolution of the grout mixtures by waters infiltrating down the well annulus driven by the downward head gradient with subsequent precipitation of calcite in the higher pH sand pack. Well rehabilitation techniques currently under investigation include acidification, hydraulic fracturing and traditional physical methods. In addition to treating the wells at MWD, the authors plan to perform aquifer performance tests and evaluate post-treatment skin factors. Further research into the long term effects of well treatment will be conducted, focusing on long term chemical changes brought about by the treatments

  16. Corrective Action Investigation Plan for Corrective Action Unit 570: Area 9 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Patrick Matthews

    2012-08-01

    CAU 570 comprises the following six corrective action sites (CASs): • 02-23-07, Atmospheric Test Site - Tesla • 09-23-10, Atmospheric Test Site T-9 • 09-23-11, Atmospheric Test Site S-9G • 09-23-14, Atmospheric Test Site - Rushmore • 09-23-15, Eagle Contamination Area • 09-99-01, Atmospheric Test Site B-9A These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 570. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The presence and nature of contamination at CAU 570 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological

  17. Recent drilling program to investigate radionuclide migration at the Nevada Test Site

    International Nuclear Information System (INIS)

    Smith, D.K.

    1997-01-01

    Recent drilling affords new opportunities to investigate the occurrence, distribution and transport of radionuclides in the unsaturated and saturated zone at the Nevada Test Site (NTS), Nye County, Nevada. This program is unique becmise of the elevated activities of radionuclides encountered during drilling (> 3.7E+6 Bq/L 3H), extreme completion depths (> 950 m), the expense of constructing new wells (> $IE+6/borehole), and collaboration of government, academic, and industrial partners in the planning and execution of the program. The recent chilling is significant because it substantively augments earlier field of radionuclide migration at NTS, most notably the 1974 CAMBRIC RNM experiment Sites of five nuclear tests fired below or adjacent to the saturated zone have been drilled. Three of the events were fired in Yucca Flat which is a hydrologically closed basin and two were fired in fractured volcanics of Pahute Mesa. Results from Yucca Flat indicate that volatile and refractory radionuclides, fractionated at zero time, we not highly mobile under sawmted conditions. In contrast, borcholes completed on Pahute Mesa indicate Wgh concentrations of tritium (> 3.7E+6 Bq/L 3H) and other radionuclides may be rted more than 300 m from event cavities as dissolved species or as colloids

  18. Correlated compositional and mineralogical investigations at the Chang′e-3 landing site

    Science.gov (United States)

    Ling, Zongcheng; Jolliff, Bradley L.; Wang, Alian; Li, Chunlai; Liu, Jianzhong; Zhang, Jiang; Li, Bo; Sun, Lingzhi; Chen, Jian; Xiao, Long; Liu, Jianjun; Ren, Xin; Peng, Wenxi; Wang, Huanyu; Cui, Xingzhu; He, Zhiping; Wang, Jianyu

    2015-01-01

    The chemical compositions of relatively young mare lava flows have implications for the late volcanism on the Moon. Here we report the composition of soil along the rim of a 450-m diameter fresh crater at the Chang′e-3 (CE-3) landing site, investigated by the Yutu rover with in situ APXS (Active Particle-induced X-ray Spectrometer) and VNIS (Visible and Near-infrared Imaging Spectrometer) measurements. Results indicate that this region's composition differs from other mare sample-return sites and is a new type of mare basalt not previously sampled, but consistent with remote sensing. The CE-3 regolith derived from olivine-normative basaltic rocks with high FeO/(FeO+MgO). Deconvolution of the VNIS data indicates abundant high-Ca ferropyroxene (augite and pigeonite) plus Fe-rich olivine. We infer from the regolith composition that the basaltic source rocks formed during late-stage magma-ocean differentiation when dense ferropyroxene-ilmenite cumulates sank and mixed with deeper, relatively ferroan olivine and orthopyroxene in a hybridized mantle source. PMID:26694712

  19. Correlated compositional and mineralogical investigations at the Chang'e-3 landing site.

    Science.gov (United States)

    Ling, Zongcheng; Jolliff, Bradley L; Wang, Alian; Li, Chunlai; Liu, Jianzhong; Zhang, Jiang; Li, Bo; Sun, Lingzhi; Chen, Jian; Xiao, Long; Liu, Jianjun; Ren, Xin; Peng, Wenxi; Wang, Huanyu; Cui, Xingzhu; He, Zhiping; Wang, Jianyu

    2015-12-22

    The chemical compositions of relatively young mare lava flows have implications for the late volcanism on the Moon. Here we report the composition of soil along the rim of a 450-m diameter fresh crater at the Chang'e-3 (CE-3) landing site, investigated by the Yutu rover with in situ APXS (Active Particle-induced X-ray Spectrometer) and VNIS (Visible and Near-infrared Imaging Spectrometer) measurements. Results indicate that this region's composition differs from other mare sample-return sites and is a new type of mare basalt not previously sampled, but consistent with remote sensing. The CE-3 regolith derived from olivine-normative basaltic rocks with high FeO/(FeO+MgO). Deconvolution of the VNIS data indicates abundant high-Ca ferropyroxene (augite and pigeonite) plus Fe-rich olivine. We infer from the regolith composition that the basaltic source rocks formed during late-stage magma-ocean differentiation when dense ferropyroxene-ilmenite cumulates sank and mixed with deeper, relatively ferroan olivine and orthopyroxene in a hybridized mantle source.

  20. Investigative studies on water contamination in Bangladesh. Primary treatment of water samples at the sampling site

    International Nuclear Information System (INIS)

    Sera, K.; Islam, Md. Shafiqul; Takatsuji, T.; Nakamura, T.; Goto, S.; Takahashi, C.; Saitoh, Y.

    2010-01-01

    Arsenic concentration in 13 well waters, 9 pond waters, 10 agricultural waters and a coconut juice taken in Comilla district, Bangladesh, where the problem of arsenic pollution is the most severe, was investigated. High-level arsenic is detected even in the well water which has been kept drinking by the people. Relatively high arsenic concentration was detected for some pond and farm waters even though the sampling was performed just after the rainy season and the waters were expected to be highly diluted. Clear relationship was observed in elemental compositions between the pond water and the coconut juice collected at the edge of the water. These results are expected to become the basic information for evaluating the risk of individual food such as cultured fishes, shrimps and farm products, and for controlling total intakes of arsenic. In order to solve the problem of transportation of water samples internationally, a simple method of target preparation performed at the sampling site was established and its validity was confirmed. All targets were prepared at the sampling sites in this study on the basis of this method. (author)

  1. Animal Investigation Program: Nevada Test Site and Vicinity. Annual report, 1979

    International Nuclear Information System (INIS)

    Smith, D.D.; Giles, Jr.; Bernhardt, D.E.

    1981-05-01

    Data are presented from the radioanalyses of tissues collected from cattle, mule deer, desert bighorn sheep, rabbits, chukar, golden eagles, and other wildlife that resided on or near the Nevada Test Site during 1979. Routine and special activities of the Animal Investigation Program are also discussed. Other than the naturally occurring potassium-40, gamma-emitting radionuclides were detected infrequently. Strontium-90 concentrations in bones from deer, cattle, and desert bighorn sheep were lower than those of recent years. Tritium concentrations were generally within expected environmental limits with the exception of animals exposed to known sources of contamination; e.g., drainage ponds from Area 12 tunnels or the Sedan Crater. Plutonium levels in all tissues from all species showed little variation to those levels in samples collected in recent years. Radionuclide tissue concentrations were generally higher in the tissues of animals residing in Area 15 than in similar animals collected from other Nevada Test Site areas. Hypothetical annual dose estimates to man were calculated on the basis of the daily consumption of 0.5 kilogra of liver or muscle from animals that contained peak radionuclide levels. The movements of 25 mule deer outfitted with collars containing a radio transmitter unit were monitored on a weekly basis. No gross or microscopic lesions were found in necropsied animals that could be directly attributed to the effects of ionizing radiation

  2. Recent drilling program to investigate radionuclide migration at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.K.

    1997-04-01

    Recent drilling affords new opportunities to investigate the occurrence, distribution and transport of radionuclides in the unsaturated and saturated zone at the Nevada Test Site (NTS), Nye County, Nevada. This program is unique becmise of the elevated activities of radionuclides encountered during drilling (> 3.7E+6 Bq/L 3H), extreme completion depths (> 950 m), the expense of constructing new wells (> $IE+6/borehole), and collaboration of government, academic, and industrial partners in the planning and execution of the program. The recent chilling is significant because it substantively augments earlier field of radionuclide migration at NTS, most notably the 1974 CAMBRIC RNM experiment Sites of five nuclear tests fired below or adjacent to the saturated zone have been drilled. Three of the events were fired in Yucca Flat which is a hydrologically closed basin and two were fired in fractured volcanics of Pahute Mesa. Results from Yucca Flat indicate that volatile and refractory radionuclides, fractionated at zero time, we not highly mobile under sawmted conditions. In contrast, borcholes completed on Pahute Mesa indicate Wgh concentrations of tritium (> 3.7E+6 Bq/L 3H) and other radionuclides may be rted more than 300 m from event cavities as dissolved species or as colloids.

  3. Utilization of multimode Love wave dispersion curve inversion for geotechnical site investigation

    International Nuclear Information System (INIS)

    Hamimu, La; Nawawi, Mohd; Safani, Jamhir

    2011-01-01

    Inversion codes based on a modified genetic algorithm (GA) have been developed to invert multimode Love wave dispersion curves. The multimode Love wave dispersion curves were synthesized from the profile representing shear-wave velocity reversal using a full SH (shear horizontal) waveform. In this study, we used a frequency–slowness transform to extract the dispersion curve from the full SH waveform. Dispersion curves overlain in dispersion images were picked manually. These curves were then inverted using the modified GA. To assess the accuracy of the inversion results, differences between the true and inverted shear-wave velocity profile were quantified in terms of shear-wave velocity and thickness errors, E S and E H . Our numerical modeling showed that the inversion of multimode dispersion curves can significantly provide the better assessment of a shear-wave velocity structure, especially with a velocity reversal profile at typical geotechnical site investigations. This approach has been applied on field data acquired at a site in Niigata prefecture, Japan. In these field data, our inversion results show good agreement between the calculated and experimental dispersion curves and accurately detect low velocity layer targets

  4. Site study plan for Playa investigations, Deaf Smith County, Texas: Salt Repository Project

    International Nuclear Information System (INIS)

    1987-01-01

    This plan defines the purpose and objectives of the Playa Investigation Study, presents a plan of work to provide the information necessary to resolve issues, and discusses the rationale for test method selection. The required information will be obtained from existing well drilling records, describing and testing of soil and rock samples recovered from project test holes, geophysical well logs, seismic surveys, and shallow test pits excavated at ground surface. There have been numerous, often conflicting, theories presented to explain the origin(s) of the playas of the Texas High Plains. The primary purpose of this study is to establish if existing playas and playa alignments are related to deeper subsurface structure, such as faulting or salt dissolution, the potential for future playa development, and the significance of existing and/or future playas on siting a repository in Deaf Smith County, Texas. 11 refs

  5. Animal investigation program 1980 annual report: Nevada Test Site and vicinity

    International Nuclear Information System (INIS)

    Smith, D.D.; Bernhardt, D.E.; Giles, K.R.

    1982-07-01

    This report summarizes the data collected through the Animal Investigation Program during 1980. A major goal of the Program is to assess the radionuclide burden in the tissues of wild and domesticated animals around the Nevada Test Site and to detect pathological effects resulting from the burdens. Other than naturally occurring potassium-40, gamma emitting radionuclides were detected infrequently. Strontium-90 and plutonium concentrations in tissues from deer, cattle, and desert bighorn sheep were similar to those found in samples collected during recent years. Lesions found in necropsied animals were similar to those found in animals from other areas of the U.S. and would not be attributable to ionizing radiation exposure. The report also describes other activities of the program, including the deer migration study and census

  6. Investigation of surface and underground waters about the Blayais nuclear site - 2010

    International Nuclear Information System (INIS)

    Migeon, A.; Bernollin, A.; Dunand, E.; Barbey, P.; Boilley, D.; Josset, M.

    2011-01-01

    This investigation aims at proposing a first assessment of the impact of releases on surface and underground waters around the Blayais nuclear power station, i.e. the assessment of the (mainly radiological) quality of waters. The report identifies the various pollution sources: old sources (like atmospheric nuclear tests, nuclear accidents), incidents in the Blayais station, and potential sources for the present contamination. Different radionuclides are searched like tritium, carbon 14, gamma radioactivity (from different elements), some beta emitters, radon as well as some chemicals related to the station activity (hydrazine, boric acid, EDTA, lithium, morpholine). Sampling sites are presented (estuary, canals, reservoirs). Radiological and chemical analysis are reported and commented. Significant presence of Tritium and Nickel-63 are noticed

  7. The Plan for Investigating the Radiation Environment around the KAERI Site

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geun Sik; Lee, Chang Woo

    2007-11-15

    The investigation of the radiation environment is carried out broadly for the environmental radiation measurement, analyses of the environmental radioactivity and radiological assessment for the public. Environmental radiation dose is measured by a continuous and a portable environmental radiation monitor (ERM) in the range of the radius of 30 km from the sites. And the accumulated radiation dose is measured by thermoluminescent dosimeter (TLD). The environmental radioactivity on gross alpha and gross beta, Uranium, Tritium, Strontium, and gamma-radionuclides are analyzed routinely in the various samples such as air particulate, air iodine, air moisture, soil, sediment, pine needle, rainwater, surface water, underground water, fallout, farm products, and stock farm products. Effective dose assessment by monitoring results is performed to obtain the public confidence.

  8. Remedial investigation of the High-Explosives (HE) Process Area, Lawrence Livermore National Laboratory Site 300

    Energy Technology Data Exchange (ETDEWEB)

    Crow, N.B.; Lamarre, A.L.

    1990-08-01

    This report presents the results of a Remedial Investigation (RI) to define the extent of high explosives (HE) compounds and volatile organic compounds (VOCs) found in the soil, rocks, and ground water of the HE Process Area of Lawrence Livermore National Laboratory's (LLNL) Site 300 Facility. The report evaluates potential public health environmental risks associated with these compounds. Hydrogeologic information available before February 15, 1990, is included; however, chemical analyses and water-level data are reported through March 1990. This report is intended to assist the California Regional Water Quality Control Board (RWQCB)--Central Valley Region and the US Environmental Protection Agency (EPA) in evaluating the extent of environmental contamination of the LLNL HE Process Area and ultimately in designing remedial actions. 90 refs., 20 figs., 7 tabs.

  9. Streamlining digital signal processing a tricks of the trade guidebook

    CERN Document Server

    2012-01-01

    Streamlining Digital Signal Processing, Second Edition, presents recent advances in DSP that simplify or increase the computational speed of common signal processing operations and provides practical, real-world tips and tricks not covered in conventional DSP textbooks. It offers new implementations of digital filter design, spectrum analysis, signal generation, high-speed function approximation, and various other DSP functions. It provides:Great tips, tricks of the trade, secrets, practical shortcuts, and clever engineering solutions from seasoned signal processing professionalsAn assortment.

  10. A streamlined ribosome profiling protocol for the characterization of microorganisms

    DEFF Research Database (Denmark)

    Latif, Haythem; Szubin, Richard; Tan, Justin

    2015-01-01

    Ribosome profiling is a powerful tool for characterizing in vivo protein translation at the genome scale, with multiple applications ranging from detailed molecular mechanisms to systems-level predictive modeling. Though highly effective, this intricate technique has yet to become widely used...... in the microbial research community. Here we present a streamlined ribosome profiling protocol with reduced barriers to entry for microbial characterization studies. Our approach provides simplified alternatives during harvest, lysis, and recovery of monosomes and also eliminates several time-consuming steps...

  11. Streamlined library programming how to improve services and cut costs

    CERN Document Server

    Porter-Reynolds, Daisy

    2014-01-01

    In their roles as community centers, public libraries offer many innovative and appealing programs; but under current budget cuts, library resources are stretched thin. With slashed budgets and limited staff hours, what can libraries do to best serve their publics? This how-to guide provides strategies for streamlining library programming in public libraries while simultaneously maintaining-or even improving-quality delivery. The wide variety of principles and techniques described can be applied on a selective basis to libraries of all sizes. Based upon the author's own extensive experience as

  12. Topology of streamlines and vorticity contours for two - dimensional flows

    DEFF Research Database (Denmark)

    Andersen, Morten

    on the vortex filament by the localised induction approximation the stream function is slightly modified and an extra parameter is introduced. In this setting two new flow topologies arise, but not more than two critical points occur for any combination of the parameters. The analysis of the closed form show...... by a point vortex above a wall in inviscid fluid. There is no reason to a priori expect equivalent results of the three vortex definitions. However, the study is mainly motivated by the findings of Kudela & Malecha (Fluid Dyn. Res. 41, 2009) who find good agreement between the vorticity and streamlines...

  13. Preliminary site description Laxemar stage 2.1. Feedback for completion of the site investigation including input from safety assessment and repository engineering

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-09-15

    The Laxemar subarea is the focus for the complete site investigations in the Simpevarp area. The south and southwestern parts of the subarea (the so-called 'focused area') have been designated for focused studies during the remainder of the site investigations. This area, some 5.3 square kilometres in size, is characterised on the surface by an arc shaped body of quartz monzodiorite gently dipping to the north, flanked in the north and south by Aevroe granite. The current report documents work conducted during stage 2.1 of the site-descriptive modelling of the Laxemar subarea. The primary objective of the work performed is to provide feedback to the site investigations at Laxemar to ensure that adequate and timely data and information are obtained during the remaining investigation stage. The work has been conducted in cooperation with the site investigation team at Laxemar and representatives from safety assessment and repository engineering. The principal aim of this joint effort has been to safeguard that adequate data are collected that resolve the remaining issues/uncertainties which are of importance for repository layout and long-term safety. The proposed additional works presented in this report should be regarded as recommended additions and/or modifications in relation to the CSI programme published early 2006. The overall conclusion of the discipline-wise review of critical issues is that the CSI programme overall satisfies the demands to resolve the remaining uncertainties. This is interpreted to be partly a result of the close interaction between the site modelling team, site investigation team and the repository engineering teams, which has been in operation since early 2005. In summary, the performed interpretations and modelling have overall confirmed the version 1.2 results. The exception being Hydrogeology where the new Laxemar 2.1 borehole data suggest more favourable conditions in the south and west parts of the focused area compared

  14. Preliminary site description Laxemar stage 2.1. Feedback for completion of the site investigation including input from safety assessment and repository engineering

    International Nuclear Information System (INIS)

    2006-09-01

    The Laxemar subarea is the focus for the complete site investigations in the Simpevarp area. The south and southwestern parts of the subarea (the so-called 'focused area') have been designated for focused studies during the remainder of the site investigations. This area, some 5.3 square kilometres in size, is characterised on the surface by an arc shaped body of quartz monzodiorite gently dipping to the north, flanked in the north and south by Aevroe granite. The current report documents work conducted during stage 2.1 of the site-descriptive modelling of the Laxemar subarea. The primary objective of the work performed is to provide feedback to the site investigations at Laxemar to ensure that adequate and timely data and information are obtained during the remaining investigation stage. The work has been conducted in cooperation with the site investigation team at Laxemar and representatives from safety assessment and repository engineering. The principal aim of this joint effort has been to safeguard that adequate data are collected that resolve the remaining issues/uncertainties which are of importance for repository layout and long-term safety. The proposed additional works presented in this report should be regarded as recommended additions and/or modifications in relation to the CSI programme published early 2006. The overall conclusion of the discipline-wise review of critical issues is that the CSI programme overall satisfies the demands to resolve the remaining uncertainties. This is interpreted to be partly a result of the close interaction between the site modelling team, site investigation team and the repository engineering teams, which has been in operation since early 2005. In summary, the performed interpretations and modelling have overall confirmed the version 1.2 results. The exception being Hydrogeology where the new Laxemar 2.1 borehole data suggest more favourable conditions in the south and west parts of the focused area compared with the

  15. Site investigation SFR. Hydrogeological modelling of SFR. Model version 0.2

    Energy Technology Data Exchange (ETDEWEB)

    Oehman, Johan (Golder Associates AB (Sweden)); Follin, Sven (SF GeoLogic (Sweden))

    2010-01-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has conducted site investigations for a planned extension of the existing final repository for short-lived radioactive waste (SFR). A hydrogeological model is developed in three model versions, which will be used for safety assessment and design analyses. This report presents a data analysis of the currently available hydrogeological data from the ongoing Site Investigation SFR (KFR27, KFR101, KFR102A, KFR102B, KFR103, KFR104, and KFR105). The purpose of this work is to develop a preliminary hydrogeological Discrete Fracture Network model (hydro-DFN) parameterisation that can be applied in regional-scale modelling. During this work, the Geologic model had not yet been updated for the new data set. Therefore, all analyses were made to the rock mass outside Possible Deformation Zones, according to Single Hole Interpretation. Owing to this circumstance, it was decided not to perform a complete hydro-DFN calibration at this stage. Instead focus was re-directed to preparatory test cases and conceptual questions with the aim to provide a sound strategy for developing the hydrogeological model SFR v. 1.0. The presented preliminary hydro-DFN consists of five fracture sets and three depth domains. A statistical/geometrical approach (connectivity analysis /Follin et al. 2005/) was performed to estimate the size (i.e. fracture radius) distribution of fractures that are interpreted as Open in geologic mapping of core data. Transmissivity relations were established based on an assumption of a correlation between the size and evaluated specific capacity of geologic features coupled to inflows measured by the Posiva Flow Log device (PFL-f data). The preliminary hydro-DFN was applied in flow simulations in order to test its performance and to explore the role of PFL-f data. Several insights were gained and a few model technical issues were raised. These are summarised in Table 5-1

  16. Animal investigation program: Nevada test site and vicinity. Annual report, 1977

    International Nuclear Information System (INIS)

    Smith, D.D.; Crockett, A.B.; Bernhardt, D.E.; Giles, K.R.; Kinnison, R.R.

    1979-07-01

    Data are presented from the radioanalysis of tissues collected from cattle, mule deer, desert bighorn sheep, rabbits, feral horses, and other wildlife that resided on or near the Nevada Test Site. Routine activities and special investigations of the Animal Investigation Program are also discussed. Other than potassium-40, gamma-emitting radionuclides were detected infrequently. Strontium-90 concentrations in bones from deer, cattle, and desert bighorn sheep continued the downward trend of recent years. Tritium concentrations were generally within expected environmental limits with the exception of animals exposed to sources of contamination. Radionuclide tissue concentrations were generally higher in the tissues of animals residing in Area 15 than in other areas. Statistical analyses made of plutonium-239 levels reported in cattle tissue collected from 1971 through 1977 reveal that activity levels in lungs, liver, and bone are significantly related to age. Activity levels did not change significantly in the ingesta and lungs during this time but did tend to increase for bone and liver. Activity levels in the ingesta are significantly higher in the fall than in the spring. Hypothetical dose estimates to man were calculated on the basis of liver or muscle from animals that contained peak radionuclide levels. The highest postulated dose was 8.6 millirems for tritium in tissues from a mule deer. The movements of 17 mule deer were monitored on a weekly basis.During the winter months, all deer left their summer range on the mesas of the Nevada Test Site and migrated 40 to 60 kilometers south and west. A statistical estimate was made of the deer population in selected areas utilizing the marked deer as a basis for this estimate. No gross or microscopic lesions were found in necropsied animals that could be directly attributed to the effects of ionizing radiation

  17. Studies on the geological environment of the Nanjido waste disposal site: Gravity and magnetic investigations

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Byung Doo; Kim, Cha Seop; Chung, Ho Joon; Oh, Seok Hoon [Seoul National Univ., Seoul (Korea, Republic of)

    1995-10-01

    Gravity and magnetic surveys were carried out to investigate the three dimensional configuration and characteristics of the landfills at Nanjido waste disposal site. For terrain correction and three dimensional density inversion of gravity data an algorithm, which calculates the gravity effect of a three dimensional body by using the solid angle method, is developed. This algorithm has been proved to give more accurate terrain correction values for the small survey area having varied topography like Nanjido site as compared with widely used methods such as Hammer`s method and multiquadric equation method. Density inversion of gravity anomaly data gives very useful information about the lateral and vertical variation of the landfills, which can be used to discriminate the kinds of wastes. The average density of filled materials appears to be 1.7 g/cm{sup 3} which is much higher than the value (0.8 g/cm{sup 3}) estimated by Seoul City. The lateral variation of density shows high correlation with the pattern of ongoing depression of the landfills. The northern region of the landfill no. 1, which shows low density and high depression, is closely associated with the industrial waste and sludge filled area. The magnetic anomaly data provide information about relative concentration of magnetic materials, which is also very useful to investigate characteristics of the fills. Several high positive anomaly regions on the reduced-to-pole magnetic anomaly map are appeared to be associated with the industrial waste fills, but certain industrial waste fills show low negative anomalies. This kind of magnetic information can be used in selecting drilling locations over landfills away from buried metal products during the stabilization process. (author). 15 refs., 2 tabs., 15 figs.

  18. Site investigation SFR. Hydrogeological modelling of SFR. Model version 0.2

    International Nuclear Information System (INIS)

    Oehman, Johan; Follin, Sven

    2010-01-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has conducted site investigations for a planned extension of the existing final repository for short-lived radioactive waste (SFR). A hydrogeological model is developed in three model versions, which will be used for safety assessment and design analyses. This report presents a data analysis of the currently available hydrogeological data from the ongoing Site Investigation SFR (KFR27, KFR101, KFR102A, KFR102B, KFR103, KFR104, and KFR105). The purpose of this work is to develop a preliminary hydrogeological Discrete Fracture Network model (hydro-DFN) parameterisation that can be applied in regional-scale modelling. During this work, the Geologic model had not yet been updated for the new data set. Therefore, all analyses were made to the rock mass outside Possible Deformation Zones, according to Single Hole Interpretation. Owing to this circumstance, it was decided not to perform a complete hydro-DFN calibration at this stage. Instead focus was re-directed to preparatory test cases and conceptual questions with the aim to provide a sound strategy for developing the hydrogeological model SFR v. 1.0. The presented preliminary hydro-DFN consists of five fracture sets and three depth domains. A statistical/geometrical approach (connectivity analysis /Follin et al. 2005/) was performed to estimate the size (i.e. fracture radius) distribution of fractures that are interpreted as Open in geologic mapping of core data. Transmissivity relations were established based on an assumption of a correlation between the size and evaluated specific capacity of geologic features coupled to inflows measured by the Posiva Flow Log device (PFL-f data). The preliminary hydro-DFN was applied in flow simulations in order to test its performance and to explore the role of PFL-f data. Several insights were gained and a few model technical issues were raised. These are summarised in Table 5-1

  19. Corrective Action Investigation Plan for Corrective Action Unit 536: Area 3 Release Site, Nevada Test Site, Nevada (Rev. 0 / June 2003), Including Record of Technical Change No. 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    2003-06-27

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 536: Area 3 Release Site, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 536 consists of a single Corrective Action Site (CAS): 03-44-02, Steam Jenny Discharge. The CAU 536 site is being investigated because existing information on the nature and extent of possible contamination is insufficient to evaluate and recommend corrective action alternatives for CAS 03-44-02. The additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating CAAs and selecting the appropriate corrective action for this CAS. The results of this field investigation are to be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document. Record of Technical Change No. 1 is dated 3-2004.

  20. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 408: Bomblet Target Area, Tonopah Test Range, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Management

    2006-01-01

    This Streamlined Approach for Environmental Restoration Plan provides the details for the closure of Corrective Action Unit (CAU) 408, Bomblet Target Area. CAU 408 is located at the Tonopah Test Range and is currently listed in Appendix III of the Federal Facility Agreement and Consent Order of 1996. One Corrective Action Site (CAS) is included in CAU 408: (lg b ullet) CAS TA-55-002-TAB2, Bomblet Target Areas Based on historical documentation, personnel interviews, process knowledge, site visits, aerial photography, multispectral data, preliminary geophysical surveys, and the results of data quality objectives process (Section 3.0), clean closure will be implemented for CAU 408. CAU 408 closure activities will consist of identification and clearance of bomblet target areas, identification and removal of depleted uranium (DU) fragments on South Antelope Lake, and collection of verification samples. Any soil containing contaminants at concentrations above the action levels will be excavated and transported to an appropriate disposal facility. Based on existing information, contaminants of potential concern at CAU 408 include explosives. In addition, at South Antelope Lake, bomblets containing DU were tested. None of these contaminants is expected to be present in the soil at concentrations above the action levels; however, this will be determined by radiological surveys and verification sample results. The corrective action investigation and closure activities have been planned to include data collection and hold points throughout the process. Hold points are designed to allow decision makers to review the existing data and decide which of the available options are most suitable. Hold points include the review of radiological, geophysical, and analytical data and field observations

  1. Investigation of Nonlinear Site Response and Seismic Compression from Case History Analysis and Laboratory Testing

    Science.gov (United States)

    Yee, Eric

    ). Aside from the expected strong influence of RC, increasing fines content is found to generally decrease volume change for fines fractions consisting of silts and clayey silts with moderate to low plasticity. With truly non-plastic fines (rock flour), cyclic volume change increases with FC. Some materials also exhibit an effect of as-compacted saturation in which moderate saturation levels associated with high matric suction cause volume change to decrease. A preliminary empirical model to capture these effects is presented. The balance of the dissertation is related to a case history of strongly nonlinear site response and seismic compression associated with a free-field downhole array installed near the Service Hall at the Kashiwazaki-Kariwa nuclear power plant, which recorded strong ground motions from the Mw 6.6 2007 Niigata-ken Chuetsu-oki earthquake. Site conditions at the array consist of about 70 m of medium-dense sands overlying clayey bedrock, with ground water located at 45 m. Ground shaking at the bedrock level had geometric mean peak accelerations of 0.55 g which is reduced to 0.4 g at the ground surface, indicating nonlinear site response. Ground settlements of approximately 15+/-5 cm occurred at the site. A site investigation was performed to develop relevant soil properties for ground response and seismic compression analysis, including shear wave velocities, shear strength, relative density, and modulus reduction and damping curves. (Abstract shortened by UMI.)

  2. Remedial investigation/feasibility study for the David Witherspoon, Inc., 901 Site, Knoxville, Tennessee: Volume 2, Appendixes

    International Nuclear Information System (INIS)

    1996-10-01

    This document contains the appendixes for the remedial investigation and feasibility study for the David Witherspoon, Inc., 901 site in Knoxville, Tennessee. The following topics are covered in the appendixes: (A) David Witherspoon, Inc., 901 Site Historical Data, (B) Fieldwork Plans for the David Witherspoon, Inc., 901 Site, (C) Risk Assessment, (D) Remediation Technology Discussion, (E) Engineering Support Documentation, (F) Applicable or Relevant and Appropriate Requirements, and (G) Cost Estimate Documentation

  3. Remedial investigation/feasibility study for the David Witherspoon, Inc., 901 Site, Knoxville, Tennessee: Volume 2, Appendixes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This document contains the appendixes for the remedial investigation and feasibility study for the David Witherspoon, Inc., 901 site in Knoxville, Tennessee. The following topics are covered in the appendixes: (A) David Witherspoon, Inc., 901 Site Historical Data, (B) Fieldwork Plans for the David Witherspoon, Inc., 901 Site, (C) Risk Assessment, (D) Remediation Technology Discussion, (E) Engineering Support Documentation, (F) Applicable or Relevant and Appropriate Requirements, and (G) Cost Estimate Documentation.

  4. Results of the 1987 Archeological Investigations at the Travis 2 Site, 39WW15, Walworth County, South Dakota

    Science.gov (United States)

    1988-09-01

    only approximately 25 percent of the ground surface was visible during field work. The beach areas of the site are essentially barren of vegetation so...7.6. Pollen types observed in samples from the Travis 2 site, 39WW15. Common Name ARBOREAL POLLEN: Betulaceae Birch family Pinus Pine Populus...David W. (editor) 1981 Archaeoloical Investigations at the Rainbow Site Plymouth Countyifowa. Luther Coll ige-rchaeologica’Research Center, Decorah

  5. An interdisciplinary geoscientific investigation of a proposed site for radioactive waste disposal in Austria

    International Nuclear Information System (INIS)

    Holzer, H.; Stumpfl, E.; Weber, F.; Oszuszky, F.; Rudan, P.

    1980-01-01

    A geological reconnaissance of potentially suitable formations for long-term storage of highly active radioactive waste in Austria showed that such formations could be expected within the Bohemian Massif. Careful interpretation of LANDSAT imagery and available air-photo coverage led to the selection of an unfaulted area, approximately in the centre of a large body of granodiorite. Field geology confirmed the homogeneity of granodiorite; hydrologic investigations revealed the absence of a groundwater table except for small amounts of surface water in the soil cover and weathering zone. A morphological analysis showed that erosional processes are minimal at present and will remain so in the foreseeable geological future. Geophysical investigations included, amongst others, magnetic measurements (vertical intensity). The area chosen for further investigation is situated in a region of positive measurements of vertical intensity. Some minor flat anomalies are due to higher magnetite content of the granodiorite, which has magnetic susceptibilities of (4.0-5.8)x10 -4 (SI) or (32-46)x10 -6 (CGS). Well-logging demonstrated high electric resistivities (some 1000 ohm.m) in fresh rock; these values are reduced to about 100 ohm.m in weathered and fractured rock. Temperature logs reveal undisturbed increase with depth; the average temperature gradient (to 90 m depth) is 0.018 0 C/m. There is no microscopic evidence of tectonism or fracturing. In conclusion, the large-scale regional features which indicate stability and lack of tectonism, and geophysical data, are supported by a detailed petrological investigation of the granodiorite. The chosen area and site seem to be well suited to meet the containment and isolation requirements for disposal of all sorts of radioactive waste to be expected. (author)

  6. Geological data acquisition for site characterisation at Olkiluoto: a framework for the phase of underground investigations

    International Nuclear Information System (INIS)

    Milnes, A.G.; Aaltonen, I.; Kemppainen, K.; Mattila, J.; Wikstroem, L.; Front, K.; Kaerki, A.; Gehoer, S.; Paulamaeki, S.; Paananen, M.; Ahokas, T.

    2007-05-01

    'Geological data acquisition' is a general term for the collection of observations and measurements by direct observation of exposed bedrock in the field (i.e. in natural outcrops and trenches, in drillholes, and in tunnels and other underground excavations). Only field-based data acquisition is included in this report: laboratory-based investigations will be continued, based on the field data and sampling, and all the data will be subject to discipline-specific processing, as the project proceeds. The ultimate aim of geological data acquisition is to provide the necessary data base for geological models of the bedrock of the Olkiluoto site, in connection with the construction of an underground rock characterisation facility, ONKALO, and a repository for spent nuclear fuel, at about 500m depth. Geological data acquisition plays a central role in site characterisation and modelling, and is intended to provide a solid platform on which the other disciplines (rock mechanics, hydrogeology, seismic risk assessment, etc.) can base their investigations. Based on consideration of a series of guidelines (e.g. modelling scale, source of data, level of investigation, national and international experience, special conditions at Olkiluoto, need for process understanding), a project-oriented 'framework' has been developed as a background to the different projects within the geological data acquisition programme. Each project will require its own system of data acquisition (methodology, spreadsheets, protocols, etc.), as described in the corresponding reports; the present report concentrates on the general principles which lie behind the different methodologies and data sheets. These principles are treated under three main headings: characterization of intact rock, characterization of deformation zone intersections, and characterization of individual fractures. Geological mapping of natural outcrops and trenches at Olkiluoto, and lithological logging of more than 40 rock cores

  7. Remedial investigation/feasibility study work plan for the 100-BC-2 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1993-05-01

    This work plan and attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) remedial investigation/feasibility study (RI/FS) for the 100-BC-2 operable unit in the 100 Area of the Hanford Site. The 100 Area is one of four areas at the Hanford Site that are on the US Environmental Protection Agency's (EPA) National Priorities List under CERCLA. The 100-BC-2 operable unit is one of two source operable units in the 100-B/C Area (Figure ES-1). Source operable units are those that contain facilities and unplanned release sites that are potential sources of hazardous substance contamination. The 100-BC-2 source operable unit contains waste sites that were formerly in the 100-BC-2, 100-BC-3, and 100-BC-4 operable units. Because of their size and geographic location, the waste sites from these two operable units were added to 100-BC-2. This allows for a more efficient and effective investigation of the remaining 100-B/C Reactor area waste sites. The investigative approach to waste sites associated with the 100-BC-2 operable unit are listed in Table ES-1. The waste sites fall into three general categories: high priority liquid waste disposal sites, low priority liquid waste disposal sites, and solid waste burial grounds. Several sites have been identified as candidates for conducting an IRM. Two sites have been identified as warranting additional limited field sampling. The two sites are the 116-C-2A pluto crib, and the 116-C-2C sand filter

  8. Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Alfred Wickline

    2007-01-01

    Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval

  9. Laboratory measurements of the solute transport properties of samples from the Bradwell, Elstow, Fulbeck and Killingholme site investigations

    International Nuclear Information System (INIS)

    Gilling, D.; Jefferies, N.L.; Lineham, T.R.

    1987-12-01

    The diffusivity and hydraulic conductivity of geological samples collected during the site investigations at Bradwell, Elstow, Fulbeck and Killingholme have been determined. Comparison between laboratory permeability measurements and in-situ permeability measurements for the mudstone units may give some indication of the importance of fissure flow at the sites. (author)

  10. Animal investigation program 1975 annual report: Nevada Test Site and vicinity

    International Nuclear Information System (INIS)

    Smith, D.D.; Giles, K.R.; Bernhardt, D.E.; Brown, K.W.

    1978-02-01

    Data are presented from the radioanalysis of tissues collected from cattle, deer, desert bighorn sheep, and other wildlife that resided on or near the Nevada Test Site during 1975. Routine activities and special investigations of the Animal Investigation Program are also discussed. Other than the naturally occurring potassium-40, gamma-emitting radionuclides are detected infrequently. Tritium concentrations in the tissues from most of the animals sampled were at background levels. Strontium-90 levels in bones from deer and cattle were slightly lower than those reported for the preceding year while levels in desert bighorn sheep bones were elevated. A graph depicts the average levels found in the bones of the three species from 1956 through 1975. The gross and microscopic lesions found in necropsied animals are discussed. In general, these lesions are consistent with the physical condition of the animal and type of population sampled. No gross or microscopic lesions were detected that could be directly attributed to the effects of ionizing radiation

  11. Investigation of the groundwater composition at potential radioactive waste disposal sites in Sweden

    International Nuclear Information System (INIS)

    Wikberg, P.T.

    1984-02-01

    Within an investigation program of sites suitable for an underground repository for spent nuclear fuel the groundwater has been characterized. Until now seven areas have been investigated. The groundwater has been pumped up from several isolated sections at depth of 100 m to 600 m in boreholes in each area. Each test section has been pumped continuously for at least two weeks. During the pumping period the water was characterized in the field and sampled for later analysis. Most of the characterized waters are non saline and the concentration of the different constituents varies within a rather narrow interval. Saline waters with much higher concentrations of chloride, sulphate, sodium and calcium have been encountered. The groundwater characterization includes field monitoring of the physico-chemical parameters pH, redox potential, free sulphide concentration, dissolved oxygen concentration and conductivity. These parameters are measured in a flow through cell where the water passes before coming in contact with the air. The redox potential measurements have been successful. A new equipment for measurements in the sampling section has been constructed. Preliminary tests have given very promising results

  12. Corrective Action Investigation Plan for Corrective Action Unit 105: Area 2 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Patrick Matthews

    2012-09-01

    Corrective Action Unit (CAU) 105 is located in Area 2 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 105 is a geographical grouping of sites where there has been a suspected release of contamination associated with atmospheric nuclear testing. This document describes the planned investigation of CAU 105, which comprises the following corrective action sites (CASs): • 02-23-04, Atmospheric Test Site - Whitney • 02-23-05, Atmospheric Test Site T-2A • 02-23-06, Atmospheric Test Site T-2B • 02-23-08, Atmospheric Test Site T-2 • 02-23-09, Atmospheric Test Site - Turk These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 105. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with all CAU 105 CASs are from atmospheric nuclear testing activities. The presence and nature of contamination at CAU

  13. Evaluation of two streamlined life cycle assessment methods

    International Nuclear Information System (INIS)

    Hochschomer, Elisabeth; Finnveden, Goeran; Johansson, Jessica

    2002-02-01

    Two different methods for streamlined life cycle assessment (LCA) are described: the MECO-method and SLCA. Both methods are tested on an already made case-study on cars fuelled with petrol or ethanol, and electric cars with electricity produced from hydro power or coal. The report also contains some background information on LCA and streamlined LCA, and a deschption of the case study used. The evaluation of the MECO and SLCA-methods are based on a comparison of the results from the case study as well as practical aspects. One conclusion is that the SLCA-method has some limitations. Among the limitations are that the whole life-cycle is not covered, it requires quite a lot of information and there is room for arbitrariness. It is not very flexible instead it difficult to develop further. We are therefore not recommending the SLCA-method. The MECO-method does in comparison show several attractive features. It is also interesting to note that the MECO-method produces information that is complementary compared to a more traditional quantitative LCA. We suggest that the MECO method needs some further development and adjustment to Swedish conditions

  14. Study of streamline flow in the portal system

    International Nuclear Information System (INIS)

    Atkins, H.L.; Deitch, J.S.; Oster, Z.H.; Perkes, E.A.

    1985-01-01

    The study was undertaken to determine if streamline flow occurs in the portal vein, thus separating inflow from the superior mesenteric artery (SMA) and the inferior mesenteric artery. Previously published data on this subject is inconsistent. Patients undergoing abdominal angiography received two administrations of Tc-99m sulfur colloid, first via the SMA during angiography and, after completion of the angiographic procedure, via a peripheral vein (IV). Anterior images of the liver were recorded over a three minute acquisition before and after the IV injection without moving the patient. The image from the SMA injection was subtracted from the SMA and IV image to provide a pure IV image. Analysis of R to L ratios for selected regions of interest as well as whole lobes was carried out and the shift of R to L (SMA to IV) determined. Six patients had liver metastases from the colon, four had cirrhosis and four had no known liver disease. The shift in the ratio was highly variable without a consistent pattern. Large changes in some patients could be attributed to hepatic artery flow directed to metastases. No consistent evidence for streamlining of portal flow was discerned

  15. Petroleum hydrocarbon contaminated sites: a review of investigation and remediation regulations and processes

    Energy Technology Data Exchange (ETDEWEB)

    Epelbaum, Michel; Claudio, Jair R. [Bureau Veritas do Brasil Sociedade Classificadora e Certificadora Ltda., Sao Paulo, SP (Brazil)

    1993-12-31

    This paper discusses alternatives on remediation of petroleum hydrocarbon contaminated sites which include groundwater remediation techniques and soil remediation techniques. Finally, the work points out some trends of sites remediation in Brazil and abroad. 6 refs., 1 fig., 7 tabs.

  16. Investigation and demonstration of turbidity reduction in stormwater runoff for Oklahoma highway construction sites : final report.

    Science.gov (United States)

    2013-12-01

    The Environmental protection Agency (USEPA) has issued new requirements on the construction industry to control the discharge of pollutants from the sites. The construction effluent guidelines or ELGs require construction sites to reduce the pollu...

  17. Petroleum hydrocarbon contaminated sites: a review of investigation and remediation regulations and processes

    Energy Technology Data Exchange (ETDEWEB)

    Epelbaum, Michel; Claudio, Jair R [Bureau Veritas do Brasil Sociedade Classificadora e Certificadora Ltda., Sao Paulo, SP (Brazil)

    1994-12-31

    This paper discusses alternatives on remediation of petroleum hydrocarbon contaminated sites which include groundwater remediation techniques and soil remediation techniques. Finally, the work points out some trends of sites remediation in Brazil and abroad. 6 refs., 1 fig., 7 tabs.

  18. Data Quality Assessment Report for the Remedial Investigation of Hanford Site Releases to the Columbia River, Hanford Site, Washington

    Energy Technology Data Exchange (ETDEWEB)

    L.C. Hulstrom

    2010-09-21

    This report summarizes the results of the data quality assessment that was performed on the analytical data generated in connection with the 2008/2009 surface water, sediment, and soil data collection; groundwater upwelling investigation sample collection; and fish tissue sample collection.

  19. Data Quality Assessment Report for the Remedial Investigation of Hanford Site Releases to the Columbia River, Hanford Site, Washington

    Energy Technology Data Exchange (ETDEWEB)

    L.C. Hulstrom

    2010-08-10

    This report summarizes the results of the data quality assessment that was performed on the analytical data generated in connection with the 2008/2009 surface water, sediment, and soil data collection; groundwater upwelling investigation sample collection; and fish tissue sample collection.

  20. Strategy for the use of laboratory methods in the site investigations programme for the transport properties of the rock

    International Nuclear Information System (INIS)

    Widestrand, Henrik; Byegaard, Johan; Ohlsson, Yvonne; Tullborg, Eva-Lena

    2003-06-01

    This report comprises a strategy for the handling of laboratory investigations of diffusivity and sorption characteristics within the discipline-specific programme 'Transport Properties of the Rock' in the SKB site investigations. The aim of the transport programme is to investigate the solute transport properties at a site in order to acquire data that are required for an assessment of the long-term performance and radiological safety of the deep repository. The result of the transport programme is the Transport Properties Site Descriptive Model, i.e. a description of the site-specific properties for the transport of solutes in the groundwater at a site. A strategy for the methodology, control of sampling and characterisation programme and interpretation of the results, is proposed. The basis for the laboratory investigations is a conceptual geological model based on the geological model produced in the geology programme. Major and minor types of rock and fractures are defined and characterised according to the quality of the general database and site-specific needs. The selection of samples and analyses is determined in close co-operation with the geology, hydrogeology, hydrogeochemistry and rock mechanics programmes. The result of the laboratory investigations is a retardation model, which is used as an input in the Transport Properties Site Descriptive Model. The interpretation and production of a retardation model is described and exemplified. Lastly, method-specific strategies and recommendations are given, including strategies for the selection of tracers in the experiments and for the treatment of the sampled geologic materials

  1. Archaeomagnetic investigation and dating of Neolithic archaeological site (Kovatchevo) from Bulgaria

    Science.gov (United States)

    Kovacheva, M.; Jordanova, N.; Kostadinova, M.

    2003-04-01

    Archaeomagnetic investigation of direction and palaeointensity was carried out on a collection of samples from Neolithic kiln, excavated at Kovatchevo site. Suitability of the materials for obtaining reliable archaeomagnetic results was checked by applying different rock-magnetic experiments. The obtained values of viscosity index and Koeningsberger ratio show favorable stability characteristics of the burnt clay. The main magnetic minerals, identified by Curie temperature analysis through high-temperature behavior of magnetic susceptibility, and three-axes thermal demagnetization of IRM, show the prevailing role of magnetite and Ti-magnetite. However, investigations on the chemical changes occurring during laboratory heating show overall bad thermal stability of the studied materials, which is not good indication concerning palaeointensity determination. Palaeodirection investigation of samples, taken from different parts of the walls and kiln's floor, reveals possible influence of magnetic refraction - higher Inclination values and azymuthal dependence of Declination for the samples from walls; lower Inclination values from floor's samples. Definitive directional results are determined by averaging data for all samples, which are well distributed all over walls and three kiln's floors. For palaeointensity evaluation rock-magnetic studies are carefully considered and strict acception criteria applied. Archaeomagnetic dating of the studied kiln was performed according to the newly developed method (Lanos, 2001). Final dating, taking into account directional and intensity results, gives the most probable time interval of the last kiln's usage between 5712-5571 BC. Dating result is in agreement with archaeological findings for Bulgarian Early Neolithic and most of 14C data available. This study is supported by EU-funded project AARCH, contract No HPRN-CT-2002-00219 and Mission archeologique de la Vallee du Strymon (Centre de Recherches Protohistorique de l

  2. Animal investigation program 1978 annual report: Nevada Test Site and vicinity

    International Nuclear Information System (INIS)

    Smith, D.D.; Bernhardt, D.E.; Giles, K.R.

    1980-12-01

    Data are presented from the radioanalyses of tissues collected from cattle, mule deer, desert bighorn sheep, rabbits, golden eagles, and other wildlife that resided on or near the Nevada Test Site during 1978. Routine and special activities of the Animal Investigation Program are also discussed. Other than the naturally occurring Potassium-40, gamma-emitting radionuclides were detected infrequently with the exception of short-lived radionuclides found in samples from animals collected soon after March 14 (the date of a nuclear test by the People's Republic of China). Strontium-90 concentrations in bones from deer, cattle, and desert bighorn sheep were consistent with those of recent years. Tritium concentrations were generally within expected environmental limits with the exception of animals exposed to sources of contamination; e.g., drainage ponds from Area 12 tunnels. Plutonium levels in all tissues from all species showed little variation from recent years. However, cattle tissue sampled in the fall were higher than those collected in the spring. Radionuclide tissue concentrations were generally higher in the tissues of animals residing in Area 15 than in similar animals collected from other Nevada Test Site areas. Hypothetical dose estimates to man were calculated on the basis of the daily consumption of 0.5 kilogram of liver or muscle from animals that contained peak radionuclide levels. The movements of 13 mule deer outfitted with collars containing a radio transmitter unit were monitored on a weekly basis. No gross or microscopic lesions were found in necropsied animals that could be directly attributed to the effects of ionizing radiation

  3. Animal investigation program 1980 annual report: Nevada Test Site and vicinity

    International Nuclear Information System (INIS)

    Smith, D.D.; Giles, K.R.; Bernhardt, D.E.

    1982-08-01

    Data are presented from the radioanalyses of tissues collected from cattle, mule deer, desert bighorn sheep, rabbits, and a horse that resided on or near the Nevada Test Site during 1980. Routine and special activities of the Animal Investigation Program are also discussed. Other than the naturally occurring 40 K, gamma-emitting radionuclides were detected infrequently. 131 I was found in the thyroid of a deer 3 weeks after a nuclear test by the People's Republic of China. Concentrations of 90 Sr in bones from deer, cattle, and desert bighorn sheep were similar to those of recent years. Plutonium levels in all tissues from all species showed little variation from those levels in samples collected in recent years. Radionuclide concentrations were generally higher in the tissues of animals residing in Area 15 than in similar animals collected from other Nevada Test Site areas. Surface soil samples from the Area 15 farm contained 238 Pu and 239 Pu in nanocurie per kilogram concentrations. Hypothetical annual dose estimates to man were calculated on the basis of the daily consumption of 0.5 kilogram of liver or muscle from animals that contained peak radionuclide levels. The highest postulated dose was 0.4 millirems to whole body for 137 Cs in muscle obtained from cattle. This dose is about 0.1 percent of the 500 millirems per year radiation protection guide for individuals in the general population. All other postulated doses for consumption of tissues containing other radionuclides were less than 0.1 percent of the standard

  4. MX Siting Investigation. Water Resources Program Industry Activity Inventory, Nevada-Utah.

    Science.gov (United States)

    1980-09-02

    Agua Caliente Existing 150 gpm *One of five sites shown on Plate II may be the site of this project. There are also three additional sites outside the...SOURCE: Wells WATER RECIRCULATED: 80%, hopefully WATER QUALITY: POTABLE : STOCK AGRICULTURE OTHER ? OPERATION - REOPENED: Reopened NEW: WATER...year _________ TYPE OF BENEFICIAL USE: __ * ~~WATER SOURCE: ____-____ WATER RECIRCULATED: ___ _____ WATER QUALITY: POTABLE : STOCK ___AGRICULTURE

  5. Nuclear-physical methods in macro- and microanalytical investigations of contamination with radionuclides at Semipalatinsk Nuclear Test Site

    International Nuclear Information System (INIS)

    Solodukhin, V.P.

    2005-01-01

    A complex of nuclear-physical methods developed in the Institute of Nuclear Physics of Kazakhstan National Nuclear Center for the investigations of the rate, character and peculiarities of contamination with radionuclides of the Semipalatinsk Nuclear Test Site (SNTS) is presented. The developed method combines both macroinvestigations (radionuclide analysis, NAA, XRFA, ESR- and NGR-spectroscopy) and microinvestigations (MS, micro-PIXE, electron microscopy). The results of the investigations at the main SNTS test sites 'Opytnoye pole' and 'Degelen' are presented. (author)

  6. Corrective Action Investigation Plan for Corrective Action Unit 576: Miscellaneous Radiological Sites and Debris Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick [Navarro, Las Vegas, NV (United States)

    2016-12-01

    Corrective Action Unit (CAU) 576 is located in Areas 2, 3, 5, 8, and 9 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 576 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 576, which comprises the following corrective action sites (CASs): 00-99-01, Potential Source Material; 02-99-12, U-2af (Kennebec) Surface Rad-Chem Piping; 03-99-20, Area 3 Subsurface Rad-Chem Piping; 05-19-04, Frenchman Flat Rad Waste Dump ; 09-99-08, U-9x (Allegheny) Subsurface Rad-Chem Piping; 09-99-09, U-9its u24 (Avens-Alkermes) Surface Contaminated Flex Line These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document (CADD).

  7. Site investigation SFR. Water-rock interaction and mixing modelling in the SFR

    Energy Technology Data Exchange (ETDEWEB)

    Gimeno, Maria J.; Auque, Luis F.; Gomez, Javier B.; Acero, Patricia (University of Zaragoza (Spain))

    2011-10-15

    During 2008, the Swedish Nuclear Fuel and Waste Management Company (SKB) initiated an investigation programme for a future expansion of the final repository for low and medium level radioactive operational waste, SFR, located about 150 km north of Stockholm. The purpose of the investigations was to define and characterise a bedrock volume large enough to allow further storage of operational waste from existing Swedish nuclear power plants and future waste from the decommissioning and dismantling of nuclear power plant reactors (SKB 2008). Of several alternatives, a selected location was investigated southwest of the present SFR tunnel system. As part of the SFR Site Descriptive Model, the objective of the hydrogeochemical site description is to describe the chemistry, origin and distribution of groundwaters in the bedrock and the hydrogeochemical processes involved in their evolution. Hydrogeochemical information (salinity distribution, groundwater residence time, palaeohydrogeochemical input, etc.) are also of importance to help constrain the hydrogeological descriptive model. The hydrogeochemical modelling work has been performed in three steps, resulting in three model versions (0.1, 0.2 and 1.0). In versions 0.1 and 0.2, explorative analyses using traditional geochemical approaches (trend plots, x-y scatter plots, 3D visualisations, etc.) were performed to describe the data and to provide an early insight and understanding of the site. The final hydrogeochemical site description version 1.0 (Nilsson et al. 2011) includes data from the previous versions, as well as subsequent complementary data from the SFR extension project, and all these data are further evaluated using additional modelling approaches and techniques. In this context, the present report gives a more detailed analysis of the available data for some hydrogeochemical systems and a detailed description of the results of the geochemical and statistical modelling. One of the main aims is to establish

  8. Site investigation SFR. Water-rock interaction and mixing modelling in the SFR

    International Nuclear Information System (INIS)

    Gimeno, Maria J.; Auque, Luis F.; Gomez, Javier B.; Acero, Patricia

    2011-10-01

    During 2008, the Swedish Nuclear Fuel and Waste Management Company (SKB) initiated an investigation programme for a future expansion of the final repository for low and medium level radioactive operational waste, SFR, located about 150 km north of Stockholm. The purpose of the investigations was to define and characterise a bedrock volume large enough to allow further storage of operational waste from existing Swedish nuclear power plants and future waste from the decommissioning and dismantling of nuclear power plant reactors (SKB 2008). Of several alternatives, a selected location was investigated southwest of the present SFR tunnel system. As part of the SFR Site Descriptive Model, the objective of the hydrogeochemical site description is to describe the chemistry, origin and distribution of groundwaters in the bedrock and the hydrogeochemical processes involved in their evolution. Hydrogeochemical information (salinity distribution, groundwater residence time, palaeohydrogeochemical input, etc.) are also of importance to help constrain the hydrogeological descriptive model. The hydrogeochemical modelling work has been performed in three steps, resulting in three model versions (0.1, 0.2 and 1.0). In versions 0.1 and 0.2, explorative analyses using traditional geochemical approaches (trend plots, x-y scatter plots, 3D visualisations, etc.) were performed to describe the data and to provide an early insight and understanding of the site. The final hydrogeochemical site description version 1.0 (Nilsson et al. 2011) includes data from the previous versions, as well as subsequent complementary data from the SFR extension project, and all these data are further evaluated using additional modelling approaches and techniques. In this context, the present report gives a more detailed analysis of the available data for some hydrogeochemical systems and a detailed description of the results of the geochemical and statistical modelling. One of the main aims is to establish

  9. Large scale seismic test research at Hualien site in Taiwan. Results of site investigation and characterization of the foundation ground

    International Nuclear Information System (INIS)

    Okamoto, Toshiro; Kokusho, Takeharu; Nishi, Koichi

    1998-01-01

    An international joint research program called ''HLSST'' is under way. Large-Scale Seismic Test (LSST) is to be conducted to investigate Soil-Structure Interaction (SSI) during large earthquakes in the field in Hualien, a high seismic region in Taiwan. A 1/4-scale model building was constructed on the excavated gravelly ground, and the backfill material of crushed stones was placed around the model plant. The model building and the foundation ground were extensively instrumented to monitor structure and ground response. To accurately evaluate SSI during earthquakes, geotechnical investigation and forced vibration test were performed during construction process namely before/after the base excavation, after the structure construction and after the backfilling. Main results are as follows. (1) The distribution of the mechanical properties of the gravelly soil are measured by various techniques including penetration tests and PS-logging and it found that the shear wave velocities (Vs) change clearly and it depends on changing overburden pressures during the construction process. (2) Measuring Vs in the surrounding soils, it found that the Vs is smaller than that at almost same depth in the farther location. Discussion is made further on the numerical soil model for SSI analysis. (author)

  10. Investigation of ground water aquifer at Tlogorejo Site Karangawen District, Demak Regency, Central Java

    International Nuclear Information System (INIS)

    Lilik Subiantoro; Priyo Sularto; Slamet Sudarto

    2009-01-01

    Demak is one of regency are placed at north beach central Java. Some part of this area especially Tlogorejo site Karangawen have the problem of fresh water availability. Conditions of insufficient Standard Water have been recognized in some part of the region, those are Karangrowo area, Undaan District. The problem of clean water in this area is caused by sea water trapped in sedimentary material during sedimentation process, so the trapped ground water character is brine or brackish. One of the alternatives to overcome water problem is election or delineated of the prospect area for exploiting of ground water. Referring to those problems Pusbang Geologi Nuklir BATAN means to conduct investigation of ground water in some location which has problem of clean water. The ground investigation activity is to get information about the geology, hydrogeology and sub surface geophysical characteristic, which is needed to identification of ground water aquifer. To obtain those targets, conducted by topographic measurement in 1:5000 scale maps, measurement of soil radioactivity, geology and hydrogeology mapping, geo-electrical 2-D image measurement Base on observation, analysis, evaluation and discussion was identified the existence of potential confined aquifer that happened at the layer sand that is trapped in the in impermeable layer of clay, which is potential for confined aquifer. Potency of aquifer with the best condition from bad, there are placed on geophysical measurement is ''Sand Aquifer Layer-1'' are located at RB 1 (TLG-5), RB 2 (TLG-4) and RB 3 (TLG-22). Physical characterized of aquifer: resistivity 22-46 Ωm, the depth of surface water 110 to 146 meter. (author)

  11. House Church: Investigating Chinese Urban Christians’ Choice of Religious Practicing Site in Wuhan, China

    Directory of Open Access Journals (Sweden)

    Junqiang Han

    2018-03-01

    Full Text Available In this paper, we discuss the reasons why urban Christians choose certain sites for religious activities and explain the rapid development of house churches in urban areas in China from the perspective of individual Christians, through survey data obtained by the Chinese Urban Research Center for Ethnic and Religious Affairs Management in the city of Wuhan. We found that Christians who attend religious activities in urban house churches are generally younger in age, higher in education level, and more likely to be working in independent, private, or foreign-invested enterprises. Further investigation reveals that “Three-Self churches” are few in number and poorly planned geographically, resulting in very limited service abilities, thus being far from satisfactory for all believers. Moreover, the activities of such churches are unvaried and lack attractiveness. On the other hand, in house churches, Christians are able to build tight-knit social networks and house churches are more competitively aware in the “religious market”, leading some urban Christians to choose house churches, thereby inciting the fast development of house churches in Chinese urban areas.

  12. Animal investigation program, 1981 annual report: Nevada Test Site and vicinity

    International Nuclear Information System (INIS)

    Smith, D.D.; Giles, K.R.

    1982-01-01

    Data are presented from the radioanalysis of tissues, collected from animals that resided on or near the Nevada Test Site (NTS). Other than naturally occurring potassium-40, cesium-137 was the only gamma-emitting radionuclide frequently detected and was within a narrow range of activity. For example, 12 of 14 cattle muscle samples contained 15 to 65 pCi of cesium-137 per kilogram. Strontium-90 and plutonium-238 or -239 tissue concentrations were similar to those of recent years. Nanocurie levels of tritium were found in tissue from two deer that drank contaminated water draining from the tunnel test areas. Annual dose estimates to man were calculated based on the daily consumption of 0.5 kg of tissue with peak radionuclide levels. The highest postulated dose was 45 millirems to the whole body from ingestion of deer muscle that drank from the tritium contaminated waters. This dose is about 9% of the radiation protection guide. Movement of deer on the NTS is discussed. In general, deer from Pahute Mesa winter in the Timber Mt. area with some movement off the NTS, while deer from Rainier Mesa winter in the Shoshone Mt. area. The sudden death of an offsite goat kid was investigated and death was attributed to enterotoxemia. No gross or microscopic lesions in necropsied animals were found that could be attributed to the effect of ionizing radiation

  13. Investigating the differential effects of social networking site addiction and Internet gaming disorder on psychological health.

    Science.gov (United States)

    Pontes, Halley M

    2017-12-01

    Background and aims Previous studies focused on examining the interrelationships between social networking site (SNS) addiction and Internet gaming disorder (IGD) in isolation. Moreover, little is known about the potential simultaneous differential effects of SNS addiction and IGD on psychological health. This study investigated the interplay between these two technological addictions and ascertained how they can uniquely and distinctively contribute to increasing psychiatric distress when accounting for potential effects stemming from sociodemographic and technology-related variables. Methods A sample of 509 adolescents (53.5% males) aged 10-18 years (mean = 13.02, SD = 1.64) were recruited. Results It was found that key demographic variables can play a distinct role in explaining SNS addiction and IGD. Furthermore, it was found that SNS addiction and IGD can augment the symptoms of each other, and simultaneously contribute to deterioration of overall psychological health in a similar fashion, further highlighting potentially common etiological and clinical course between these two phenomena. Finally, the detrimental effects of IGD on psychological health were found to be slightly more pronounced than those produced by SNS addiction, a finding that warrants additional scientific scrutiny. Discussion and conclusion The implications of these results are further discussed in light of the existing evidence and debates regarding the status of technological addictions as primary and secondary disorders.

  14. Double tracks test site characterization report

    International Nuclear Information System (INIS)

    1996-05-01

    This report presents the results of site characterization activities performed at the Double Tracks Test Site, located on Range 71 North, of the Nellis Air Force Range (NAFR) in southern Nevada. Site characterization activities included reviewing historical data from the Double Tracks experiment, previous site investigation efforts, and recent site characterization data. The most recent site characterization activities were conducted in support of an interim corrective action to remediate the Double Tracks Test Site to an acceptable risk to human health and the environment. Site characterization was performed using a phased approach. First, previously collected data and historical records sere compiled and reviewed. Generalized scopes of work were then prepared to fill known data gaps. Field activities were conducted and the collected data were then reviewed to determine whether data gaps were filled and whether other areas needed to be investigated. Additional field efforts were then conducted, as required, to adequately characterize the site. Characterization of the Double Tracks Test Site was conducted in accordance with the US Department of Energy's (DOE) Streamlined Approach for Environmental Restoration (SAFER)

  15. Corrective Action Investigation Plan for Corrective Action Unit 145: Wells and Storage Holes, Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    David A. Strand

    2004-09-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 145: Wells and Storage Holes. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental samples. Corrective Action Unit 145 is located in Area 3 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 145 is comprised of the six Corrective Action Sites (CASs) listed below: (1) 03-20-01, Core Storage Holes; (2) 03-20-02, Decon Pad and Sump; (3) 03-20-04, Injection Wells; (4) 03-20-08, Injection Well; (5) 03-25-01, Oil Spills; and (6) 03-99-13, Drain and Injection Well. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. One conceptual site model with three release scenario components was developed for the six CASs to address all releases associated with the site. The sites will be investigated based on data quality objectives (DQOs) developed on June 24, 2004, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQOs process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 145.

  16. Archaeological Investigations at Sites 45-OK-287 and 45-OK-288, Chief Joseph Dam Project, Washington.

    Science.gov (United States)

    1984-01-01

    cells dis- closed six prehistoric components contained in overbank, colluvial and aeoi ian deposits. The first occupation, dated prior to 4800 B.P...location, colluvial and aeoi Ian deposition have been relatively more Important at the site than at many other * project sites. The sites are at the...varying contib’itlons of colluvium, slopewash, and aeoi Ian sedimensts (Tables 2-3 and 2-4). All of the * cultural zones are associated with deposits above

  17. Data for the geochemical investigation of UMTRAP designated site at Monument Valley, Arizona

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.

    1983-09-01

    This report contains the geochemical data and the methods of data collection from the former tailings site at Monument Valley, Arizona. Data are from a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. Selected solid samples are water extracted to remove easily soluble salts. The waters and extracts of solid samples were analyzed for selected major and trace elements. 3 refs., 2 figs., 1 tab

  18. Issues and recent advances in optimal experimental design for site investigation (Invited)

    Science.gov (United States)

    Nowak, W.

    2013-12-01

    with the ongoing site investigation, such that surprises in the data are immediately accounted for to restrict the conceptual uncertainty and update the optimization of the plan.

  19. Investigating the Watukosek fault system using combined geophysical methods around Lusi eruption site

    Science.gov (United States)

    Husein, Alwi; Mazzini, Adriano; Lupi, Matteo; Mauri, Guillaume; Kemna, Andreas; Santosa, Bagus; Hadi, Soffian

    2017-04-01

    The Lusi mud eruption is located in the Sidoarjo area, Indonesia and is continuously erupting hot mud since its birth in May 2006. Lusi sits upon the Watukosek fault system that originates from the neighboring Arjuno-Welirang volcanic complex and develops in back-arc basin extending towards the NE of Java. After the 27-06-2006 M 6.3 earthquake this fault system was reactivated and hosted numerous hot mud eruptions in the Sidoarjo area. Until now, no targeted investigations have been conducted to understand the geometry of the faults system crossing the Lusi eruption site. A comprehensive combined electrical resistivity and self-potential (SP) survey was performed in the 7 km2 area inside the Lusi embankment that was built to contain the erupted mud and to prevent flooding of the surrounding roads and settlements. Additional profiles were also acquired outside the SW part of the embankment towards the Watukosek escarpment and on the west of Lusi. The goal of the geophysical survey is to map the near-surface occurrence of the Watukosek fault system, delineate its spatial pattern, and monitor its development. In total nine lines of resistivity measurements using Wenner and Wenner-Schlumberger configuration and SP measurements using roll-along technique were completed. The resistivity data were inverted into 2-D resistivity images with a maximum penetration depth of almost 200 m. The profiles collected in the region inside the Lusi embankment consistently reveal the presence of a region of 300 m in width (between 30-90 m depth) characterized by anomalous resistivities, which are lower than the values observed in the surrounding area. The profiles outside the embankment show consistent results. Here the contrast between anomalous low resistivity zones (perceived as the fault system) and the surrounding area with higher resistivity value is more pronounced. The profiles also shows that the distance between the main crater and the boundary of mud body observed on the

  20. Corrective Action Investigation Plan for Corrective Action Unit 569: Area 3 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Patrick Matthews; Christy Sloop

    2012-02-01

    Corrective Action Unit (CAU) 569 is located in Area 3 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 569 comprises the nine numbered corrective action sites (CASs) and one newly identified site listed below: (1) 03-23-09, T-3 Contamination Area (hereafter referred to as Annie, Franklin, George, and Moth); (2) 03-23-10, T-3A Contamination Area (hereafter referred to as Harry and Hornet); (3) 03-23-11, T-3B Contamination Area (hereafter referred to as Fizeau); (4) 03-23-12, T-3S Contamination Area (hereafter referred to as Rio Arriba); (5) 03-23-13, T-3T Contamination Area (hereafter referred to as Catron); (6) 03-23-14, T-3V Contamination Area (hereafter referred to as Humboldt); (7) 03-23-15, S-3G Contamination Area (hereafter referred to as Coulomb-B); (8) 03-23-16, S-3H Contamination Area (hereafter referred to as Coulomb-A); (9) 03-23-21, Pike Contamination Area (hereafter referred to as Pike); and (10) Waste Consolidation Site 3A. Because CAU 569 is a complicated site containing many types of releases, it was agreed during the data quality objectives (DQO) process that these sites will be grouped. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each study group. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the DQOs developed on September 26, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO

  1. Streamlining of the Decontamination and Demolition Document Preparation Process

    International Nuclear Information System (INIS)

    Durand, Nick; Meincke, Carol; Peek, Georgianne

    1999-01-01

    During the past five years, the Sandia National Labo- ratories Decontamination, Decommissioning, Demolition, and Reuse (D3R) Program has evolved and become more focused and efficient. Historical approaches to project documentation, requirements, and drivers are discussed detailing key assumptions, oversight authority, and proj- ect approvals. Discussion of efforts to streamline the D3R project planning and preparation process include the in- corporation of the principles of graded approach, Total Quality Management, and the Observational Method (CH2MHILL April 1989).1 Process improvements were realized by clearly defining regulatory requirements for each phase of a project, establishing general guidance for the program and combining project-specific documents to eliminate redundant and unneeded information. Proc- ess improvements to cost, schedule, and quality are dis- cussed in detail for several projects

  2. The Zig-zag Instability of Streamlined Bodies

    Science.gov (United States)

    Guillet, Thibault; Coux, Martin; Quere, David; Clanet, Christophe

    2017-11-01

    When a floating bluff body, like a sphere, impacts water with a vertical velocity, its trajectory is straight and the depth of its dive increases with its initial velocity. Even though we observe the same phenomenon at low impact speed for axisymmetric streamlined bodies, the trajectory is found to deviate from the vertical when the velocity overcomes a critical value. This instability results from a competition between the destabilizing torque of the lift and the stabilizing torque of the Archimede's force. Balancing these torques yields a prediction on the critical velocity above which the instability appears. This theoretical value is found to depend on the position of the gravity center of the projectile and predicts with a full agreement the behaviour observed in our different experiments. Project funded by DGA.

  3. Streamlining air import operations by trade facilitation measures

    Directory of Open Access Journals (Sweden)

    Yuri da Cunha Ferreira

    2017-12-01

    Full Text Available Global operations are subject to considerable uncertainties. Due to the Trade Facilitation Agreement that became effective in February 2017, the study of measures to streamline customs controls is urgent. This study aims to assess the impact of trade facilitation measures on import flows. An experimental study was performed in the largest cargo airport in South America through discrete-event simulation and design of experiments. Operation impacts of three trade facilitation measures are assessed on import flow by air. We shed light in the following trade facilitation measures: the use of X-ray equipment for physical inspection; increase of the number of qualified companies in the trade facilitation program; performance targets for customs officials. All trade facilitation measures used indicated potential to provide more predictability, cost savings, time reduction, and increase in security in international supply chain.

  4. State Models to Incentivize and Streamline Small Hydropower Development

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, Taylor [National Renewable Energy Lab. (NREL), Golden, CO (United States); Levine, Aaron [National Renewable Energy Lab. (NREL), Golden, CO (United States); Johnson, Kurt [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2017-10-31

    In 2016, the hydropower fleet in the United States produced more than 6 percent (approximately 265,829 gigawatt-hours [GWh]) of the total net electricity generation. The median-size hydroelectric facility in the United States is 1.6 MW and 75 percent of total facilities have a nameplate capacity of 10 MW or less. Moreover, the U.S. Department of Energy's Hydropower Vision study identified approximately 79 GW hydroelectric potential beyond what is already developed. Much of the potential identified is at low-impact new stream-reaches, existing conduits, and non-powered dams with a median project size of 10 MW or less. To optimize the potential and value of small hydropower development, state governments are crafting policies that provide financial assistance and expedite state and federal review processes for small hydroelectric projects. This report analyzes state-led initiatives and programs that incentivize and streamline small hydroelectric development.

  5. Corrective Action Investigation Plan for Corrective Action Unit 567: Miscellaneous Soil Sites, Nevada National Security Site, Nevada, with ROTC 1 Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick K.

    2013-07-01

    Corrective Action Unit (CAU) 567 is located in Areas 1, 3, 5, 20, and 25 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 567 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 567, which comprises the following corrective action sites (CASs): • 01-23-03, Atmospheric Test Site T-1 • 03-23-25, Seaweed E Contamination Area • 05-23-07, A5b RMA • 20-23-08, Colby Mud Spill • 25-23-23, J-11 Soil RMA These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on May 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 567. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 567 releases are nuclear test operations and other NNSS operations. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary

  6. Investigation of nucleation events vertical extent: a long term study at two different altitude sites

    Directory of Open Access Journals (Sweden)

    J. Boulon

    2011-06-01

    Full Text Available In this work we present an analysis of the occurrence of nucleation events during more than three years of measurements at two different rural altitude sites, the puy de Dôme research station (1465 m a.s.l. and the Opme station (660 m a.s.l., central France. The collected database is a unique combination of scanning mobility particle sizer (10–400 nm, air ion spectrometers (from 0.8 to 42 nm for NTP-conditions, and, neutral clusters and air ion spectrometers (from 0.8 to 42 nm for NTP-conditions measurements at these two different altitudes nearly located research stations, from February 2007 to June 2010. The seasonality of the frequency of nucleation events was studied at the puy de Dôme station and maximum of events frequency was found during early spring and early autumn. During the measurement period, neither the particle formation rates (J2= 1.382 ± 0.195 s−1 nor the growth rates (GR1.3−20 nm = 6.20 ± 0.12 nm h−1 differ from one site to the other on average. Hovewer, we found that, on 437 sampling days in common to the two sites, the nucleation frequency was higher at the puy de Dôme station (35.9 %, 157 days than at the low elevation station of Opme (20.8 %, 91 days. LIDAR measurements and the evolution of the potential equivalent temperature revealed that the nucleation could be triggered either (i within the whole low tropospheric column at the same time from the planetary boundary layer to the top of the interface layer (29.2 %, 47 events, (ii above the planetary boundary layer upper limit (43.5 %, 70 events, and (iii at low altitude and then transported, conserving dynamic and properties, at high altitude (24.8 %, 40 events. This is the first time that the vertical extent of nucleation can be studied over a long observational period, allowing for a rigorous

  7. Streamlined bioreactor-based production of human cartilage tissues.

    Science.gov (United States)

    Tonnarelli, B; Santoro, R; Adelaide Asnaghi, M; Wendt, D

    2016-05-27

    Engineered tissue grafts have been manufactured using methods based predominantly on traditional labour-intensive manual benchtop techniques. These methods impart significant regulatory and economic challenges, hindering the successful translation of engineered tissue products to the clinic. Alternatively, bioreactor-based production systems have the potential to overcome such limitations. In this work, we present an innovative manufacturing approach to engineer cartilage tissue within a single bioreactor system, starting from freshly isolated human primary chondrocytes, through the generation of cartilaginous tissue grafts. The limited number of primary chondrocytes that can be isolated from a small clinically-sized cartilage biopsy could be seeded and extensively expanded directly within a 3D scaffold in our perfusion bioreactor (5.4 ± 0.9 doublings in 2 weeks), bypassing conventional 2D expansion in flasks. Chondrocytes expanded in 3D scaffolds better maintained a chondrogenic phenotype than chondrocytes expanded on plastic flasks (collagen type II mRNA, 18-fold; Sox-9, 11-fold). After this "3D expansion" phase, bioreactor culture conditions were changed to subsequently support chondrogenic differentiation for two weeks. Engineered tissues based on 3D-expanded chondrocytes were more cartilaginous than tissues generated from chondrocytes previously expanded in flasks. We then demonstrated that this streamlined bioreactor-based process could be adapted to effectively generate up-scaled cartilage grafts in a size with clinical relevance (50 mm diameter). Streamlined and robust tissue engineering processes, as the one described here, may be key for the future manufacturing of grafts for clinical applications, as they facilitate the establishment of compact and closed bioreactor-based production systems, with minimal automation requirements, lower operating costs, and increased compliance to regulatory guidelines.

  8. Black History, Inc! Investigating the Production of Black History through Walmart's Corporate Web Site

    Science.gov (United States)

    King, LaGarrett J.; Brown, Anthony L.

    2012-01-01

    Social and public sites are becoming a popular medium for intellectual consumption of Black history. Given the educational climate in which many students' exposure to Black history may come from outside of schools, the authors examine how Walmart's Black History Month Web site produced simplistic and safe narratives about African American history.

  9. The role of historical operations information for supporting remedial investigation work at the former Harshaw Chemical Site

    International Nuclear Information System (INIS)

    Johnson, R.; Peterson, J.; Picel, K.; Kolhoff, A.; Devaughn, J.

    2008-01-01

    In the early stages of hazardous, toxic, and radioactive waste (HTRW) site investigations, basic record searches are performed to help direct the agencies investigating contaminated sites to areas of concern and to identify contaminants of interest (COI). Plans developed on the basis of this preliminary research alone are often incomplete and result in unexpected discoveries either while in the field investigating the site or after the reports have been written. Many of the sites investigated under the Formerly Utilized Sites Remedial Action program (FUSRAP) have complex histories that are slowly uncovered over the life of the project. Because of programmatic constraints, nuances of these sites are often discovered late in their programs and result in increased expenditures in order to fully characterize the site, perform a robust feasibility study, and recommend appropriate alternatives for remediation. By identifying resources for public records, classified records, historic aerial photographs, and other sources of site-specific historical information, a process can be established to optimize the collection of information and to develop efficient and complete project plans. In many cases, interviews with past site employees are very useful tools. In combining what is found in the records, observed on historic aerial photographs, and heard from former employees and family members, teams investigating these sites can begin to compile sound and more complete conceptual site models (CSMs). The former Harshaw Chemical Site (HCS) illustrates this discovery process. HCS is part of FUSRAP. Preliminary investigations by the US Department of Energy (DOE) in the 1970s provided an initial CSM of activities that had taken place that may have resulted in contamination. The remedial investigation (RI) conducted by the US Army Corps of Engineers (USACE) was designed around this CSM. The RI work, however, identified a number of site conditions that were unexpected, including new

  10. Investigation of radionuclides and anthropic tracer migration in groundwater at the Chernobyl site

    Science.gov (United States)

    Le Gal La Salle, Corinnne; Simonucci, Caroline; Roux, Céline; Bugai, Dmitry; Aquilina, Luc; Fourré, Elise; Jean-Baptiste, Philippe; Labasque, Thierry; Michelot, Jean-Luc; Fifield, Keith; Team Aster Team; Van Meir, Nathalie; Kashparov, Valeriy; Diez, Olivier; Bassot, Sylvain; Lancelot, Joel

    2013-04-01

    Following the reactor 4 explosion of the Chernobyl Nuclear Power Plant (ChNPP), at least 1019 Bq of radionuclides (RN) were released in the environment. In order to protect workers and prevent further atmospheric RN dispersion in the area adjacent to the ChNPP, contaminated wastes including fuel particles, topsoil layer and forest remains were buried in approximately 800 shallow trenches in the sand formation in the Red Forest waste dump site [1]. No containment measures were taken, and since then RN have leaked to the unsaturated zone and to the groundwater. Since 1999, migration of RN in the vicinity of the trench 22 at Red Forest site has been investigated within the frame of the EPIC program carried out by IRSN in collaboration with UIAR and IGS [2, 3]. A plume of 90Sr was shown downgradient from the trench 22 with activites reaching 3750 Bq/L [2]. In 2008, further studies were initiated through the TRASSE research group, based on a collaboration between IRSN and CNRS. These programs aim at combining groundwater dating with RN migration monitoring studies in order to constrain RN transport models [3]. Groundwater residence time was investigated based on 3H/He and CFC. Both tracers led to ages ranging from modern (1-3 y) at 2 m depth below the groundwater table to significantly higher apparent ages of 50-60 y at 27 m below the groundwater table [3]. 36Cl/Cl ratios 2 to 4 orders of magnitude higher than the theoretical natural ratio are measured in groundwater. Similarly, SF6 shows concentrations as high as 1200 pptv while natural concentrations are in the order of 6-7 pptv. Based on apparent groundwater ages, both contaminations are linked to the Chernobyl explosion. Hence those tracers show excellent potential to constrain conservative and reactive transport, respectively. In contrast, 238U/235U ratio down gradient from trench 22 remains similar to the natural ratio. This suggests that either most of the U contained in the trench is in a non soluble form

  11. In Vivo Investigation of Escitalopram’s Allosteric Site on the Serotonin Transporter

    Science.gov (United States)

    Murray, Karen E.; Ressler, Kerry J.; Owens, Michael J.

    2015-01-01

    Escitalopram is a commonly prescribed antidepressant of the selective serotonin reuptake inhibitor class. Clinical evidence and mapping of the serotonin transporter (SERT) identified that escitalopram, in addition to its binding to a primary uptake-blocking site, is capable of binding to the SERT via an allosteric site that is hypothesized to alter escitalopram’s kinetics at the SERT. The studies reported here examined the in vivo role of the SERT allosteric site in escitalopram action. A knockin mouse model that possesses an allosteric-null SERT was developed. Autoradiographic studies indicated that the knockin protein was expressed at a lower density than endogenous mouse SERT (approximately 10–30% of endogenous mouse SERT), but the knockin mice are a viable tool to study the allosteric site. Microdialysis studies in the ventral hippocampus found no measurable decrease in extracellular serotonin response after local escitalopram challenge in mice without the allosteric site compared to mice with the site (p = 0.297). In marble burying assays there was a modest effect of the absence of the allosteric site, with a larger systemic dose of escitalopram (10-fold) necessary for the same effect as in mice with intact SERT (p = 0.023). However, there was no effect of the allosteric site in the tail suspension test. Together these data suggest that there may be a regional specificity in the role of the allosteric site. The lack of a robust effect overall suggests that the role of the allosteric site for escitalopram on the SERT may not produce meaningful in vivo effects. PMID:26621784

  12. Economical and technical optimization of site investigations - a multivariate approach based on Stripa F1 and F2 borehole information

    International Nuclear Information System (INIS)

    Schunnesson, H.; Lundholm, I.

    1992-01-01

    In this report multivariate analysis is presented and used as a tool to optimize site investigations. The technique is tested on earlier accumulated data from bore hole F1 and F2 in the Stripa mine, in an attempt to predict the hydraulic conductivity of the rock. Different investigation methods can be selected only on behalf of their correlation to the hydraulic conductivity and accurate predictions can be made with as high resolution as the core mapping data and the data from the geophysical logging allows. In the second part of the report the integration of this technique in the pre-investigation is discussed. The most important steps is to form a site analysis group, responsible for data collection, analysis and investigation, utilize all at the time available data to improve the investigation. This will also lead to a less rigid and more flexible pre-investigation that will improve the quality and reduce time consumption. (12 refs.)(au)

  13. On-site management of investigational products and drug delivery systems in conformity with Good Clinical Practices (GCPs).

    Science.gov (United States)

    Méthot, Julie; Brisson, Diane; Gaudet, Daniel

    2012-04-01

    Investigators and research teams participating in clinical trials have to deal with complex investigational products, study designs, and research environments. The emergence of new drug delivery systems and investigational products combining more than one drug and the development of biodrugs such as monoclonal antibodies, peptides, siRNA, and gene therapy to treat orphan or common diseases constitute a new challenge for investigators and clinical sites. We describe the requirements and challenges of drug management in conformity with Good Clinical Practices (GCPs) for investigators and sites participating in clinical trials. Review At all sites participating in clinical trials, standard operating procedures (SOPs) covering the critical path of drug and drug delivery systems management are required. All steps should be auditable, including reception, validation, storage, access, preparation, distribution, techniques of administration, use, return, and destruction of research products. Biodrugs require traceability and specific SOPs on the management of potential immune reactions. Investigational products must be stored under standard auditable conditions. The traceability of storage conditions (including temperature) requires these conditions to be monitored on a continuous basis. A dedicated space with restricted access limited to authorized qualified personnel facilitates the monitoring. The development of standardized, auditable settings and the application of dedicated, site-specific SOPs for the management of investigational products and drug delivery systems contribute to guarantee the compliance to GCP requirements.

  14. Corrective Action Investigation Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Patrick Matthews

    2011-09-01

    Corrective Action Unit 366 comprises the six corrective action sites (CASs) listed below: (1) 11-08-01, Contaminated Waste Dump No.1; (2) 11-08-02, Contaminated Waste Dump No.2; (3) 11-23-01, Radioactively Contaminated Area A; (4) 11-23-02, Radioactively Contaminated Area B; (5) 11-23-03, Radioactively Contaminated Area C; and (6) 11-23-04, Radioactively Contaminated Area D. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed July 6, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 366. The presence and nature of contamination at CAU 366 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample locations to the dose-based final action level (FAL). The TED will be calculated by summing the estimates of internal and external dose. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at each sample location will be used to measure external radiological dose. Based on historical documentation of the releases

  15. 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)

  16. Strategy for the use of laboratory methods in the site investigations programme for the transport properties of the rock

    Energy Technology Data Exchange (ETDEWEB)

    Widestrand, Henrik; Byegaard, Johan [Geosigma AB, Kungaelv (Sweden); Ohlsson, Yvonne [SWECO VIAK AB, Stockholm (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden)

    2003-06-01

    This report comprises a strategy for the handling of laboratory investigations of diffusivity and sorption characteristics within the discipline-specific programme 'Transport Properties of the Rock' in the SKB site investigations. The aim of the transport programme is to investigate the solute transport properties at a site in order to acquire data that are required for an assessment of the long-term performance and radiological safety of the deep repository. The result of the transport programme is the Transport Properties Site Descriptive Model, i.e. a description of the site-specific properties for the transport of solutes in the groundwater at a site. A strategy for the methodology, control of sampling and characterisation programme and interpretation of the results, is proposed. The basis for the laboratory investigations is a conceptual geological model based on the geological model produced in the geology programme. Major and minor types of rock and fractures are defined and characterised according to the quality of the general database and site-specific needs. The selection of samples and analyses is determined in close co-operation with the geology, hydrogeology, hydrogeochemistry and rock mechanics programmes. The result of the laboratory investigations is a retardation model, which is used as an input in the Transport Properties Site Descriptive Model. The interpretation and production of a retardation model is described and exemplified. Lastly, method-specific strategies and recommendations are given, including strategies for the selection of tracers in the experiments and for the treatment of the sampled geologic materials.

  17. Work plan for the remedial investigation/feasibility study-environmental assessment for the Colonie site, Colonie, New York

    International Nuclear Information System (INIS)

    1990-06-01

    This work plan has been prepared to document the scoping and planning process performed by the US Department of Energy (DOE) to support remedial action activities at the Colonie site. The site is located in eastern New York State in the town of Colonie near the city of Albany. Remedial action of the Colonie site is being planned as part of DOE's Formerly Utilized Sites Remedial Action Program. The DOE is responsible for controlling the release of all radioactive and chemical contaminants from the site. Under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), a remedial investigation/feasibility study (RI/FS) must be prepared to support the decision-making process for evaluating remedial action alternatives. This work plan contains a summary of information known about the site as of January 1988, presents a conceptual site model that identifies potential routes of human exposure to site containments, identifies data gaps, and summarizes the process and proposed studies that will be used to fill the data gaps. In addition, DOE activities must be conducted in compliance with the National Environmental Policy Act (NEPA), which requires consideration of the environmental consequences of a proposed action as part of its decision-making process. This work also describes the approach that will be used to evaluate potential remedial action alternatives and includes a description of the organization, project controls, and task schedules that will be employed to fulfill the requirements of both CERCLA and NEPA. 48 refs., 18 figs., 25 tabs

  18. The Social Influence Qualities of Social Network Sites: A Qualitative and Experimental Investigation

    Science.gov (United States)

    2009-03-01

    Guadagno and Cialdini, 2005). This is especially true with the unique social arrangements and organizational forms found on social network sites...their true feelings to others. According to Respondent #18, “it’s easier to talk on the phone than it is in person. To say something important...include things like weather, horoscope , graffiti, etc. • In addition to these tasks, how do you use this site as part of your daily life? o Do you use

  19. Investigation of Trap Sites and Their Roles in Organic Triphenylamine-Based Photorefractive Materials

    OpenAIRE

    Tsujimura, Sho

    2016-01-01

    Organic photorefractive (PR) materials have been studied during the last quarter-century, and they have recently received much attention due to their updatable