Demonstration of Caustic-Side Solvent Extraction with Savannah River Site High Level Waste

International Nuclear Information System (INIS)

Walker, D.D.

2001-01-01

Researchers successfully demonstrated the chemistry and process equipment of the Caustic-Side Solvent Extraction (CSSX) flowsheet for the decontamination of high level waste using a 33-stage, 2-cm centrifugal contactor apparatus at the Savannah River Technology Center. This represents the first CSSX process demonstration using Savannah River Site (SRS) high level waste. Three tests lasting 6, 12, and 48 hours processed simulated average SRS waste, simulated Tank 37H/44F composite waste, and Tank 37H/44F high level waste, respectively

Use of geostatistics in high level radioactive waste repository site characterization

Energy Technology Data Exchange (ETDEWEB)

Doctor, P G [Pacific Northwest Laboratory, Richland, WA (USA)

1980-09-01

In evaluating and characterizing sites that are candidates for use as repositories for high-level radioactive waste, there is an increasing need to estimate the uncertainty in hydrogeologic data and in the quantities calculated from them. This paper discusses the use of geostatistical techniques to estimate hydrogeologic surfaces, such as the top of a basalt formation, and to provide a measure of the uncertainty in that estimate. Maps of the uncertainty estimate, called the kriging error, can be used to evaluate where new data should be taken to affect the greatest reduction in uncertainty in the estimated surface. The methods are illustrated on a set of site-characterization data; the top-of-basalt elevations at the Hanford Site near Richland, Washington.

The general situation of clay site for high-level waste geological disposal repository

International Nuclear Information System (INIS)

Wang Changxuan; Liu Xiaodong; Liu Pinghui

2008-01-01

Host medium is vitally important for safety of high-level radiaoactive waste (HLW) geological disposal. Clay, as host media of geological repository of HLW, has received greater attention for its inherent advantages. This paper summarizes IAEA and OECD/NEA's some safety guides on site selection and briefly introduces the process of the site selection, their studies and the characteristics of the clay formations in Switz-erland, France and Belgian. Based on these analyses, some suggestions are made to China's HLW repository clay site selection. (authors)

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks

Energy Technology Data Exchange (ETDEWEB)

ROGERS, C.A.

2000-02-17

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

Criticality Safety Evaluation of Hanford Site High-Level Waste Storage Tanks

International Nuclear Information System (INIS)

ROGERS, C.A.

2000-01-01

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

The Savannah River Site Replacement High Level Radioactive Waste Evaporator Project

International Nuclear Information System (INIS)

Brock Presgrove, S.

1992-01-01

The Replacement High Level Waste Evaporator Project was conceived in 1985 to reduce the volume of the high level radioactive waste currently stored at the DOE Savannah River Site Tank Farm. Process of the high level waste has been accomplished up to this time using Bent Tube type evaporators and therefore, that type evaporator was selected for this project. The Title I Design of the project was 70% completed in late 1990. The Department of Energy at that time hired an independent consulting firm to perform a complete review of the project. The DOE placed a STOP ORDER on purchasing the evaporator in January 1991. Essentially, no construction was to be done on the project until all findings and concerns dealing with the type and design of the evaporator are resolved. This report addresses two aspects of the DOE design review: Comparing the Bent Tube Evaporator with the Forced Circulation Evaporator; The design portion of the DOE Project Review - concentrated on the mechanical design properties of the evaporator. (author)

Development of a geoscience database for preselecting China's high level radioactive waste disposal sites

International Nuclear Information System (INIS)

Li Jun; Fan Ai; Huang Shutao; Wang Ju

1998-01-01

Taking the development of a geoscience database for China's high level waste disposal sites: Yumen Town, Gansu Province, northwest of China, as an example, the author introduces in detail the application of Geographical Information System (GIS) to high level waste disposal and analyses its application prospect in other fields. The development of GIS provides brand-new thinking for administrators and technicians at all levels. At the same time, the author also introduces the administration of maps and materials by using Geographical Information System

Development of a geoscience database for preselecting China's high level radioactive waste disposal sites

International Nuclear Information System (INIS)

Li Jun; Fan Ai; Huang Shutao; Wang Ju

2004-01-01

Taking the development of a geoscience database for China's high level waste disposal sites: Yumen Town, Guansu province, northwest of China, as an example, this paper introduces in detail the application of Geographical Information System (GIS) to high level waste disposal and analyses its application prospect in other fields. The development of GIS provides brand-new thinking for administrators and technicians at all levels. At the same time, this paper also introduces the administration of maps and materials by using Geographical Information System. (author)

Should high-level nuclear waste be disposed of at geographically dispersed sites?

International Nuclear Information System (INIS)

Bassett, G.W. Jr.

1992-01-01

Consideration of the technical feasibility of Yucca Mountain in Nevada as the site for a high-level nuclear waste repository has led to an intense debate regarding the economic, social, and political impacts of the repository. Impediments to the siting process mean that the nuclear waste problem is being resolved by adhering to the status quo, in which nuclear waste is stored at scattered sites near major population centers. To assess the merits of alternative siting strategies--including both the permanent repository and the status quo- we consider the variables that would be included in a model designed to select (1) the optimal number of disposal facilities, (2) the types of facilities (e.g., permanent repository or monitored retrievable facility), and (3) the geographic location of storage sites. The objective function in the model is an all-inclusive measure of social cost. The intent of the exercise is not to demonstrate the superiority of any single disposal strategy; uncertainties preclude a conclusive proof of optimality for any of the disposal options. Instead, we want to assess the sensitivity of a variety of proposed solutions to variations in the physical, economic, political, and social variables that influence a siting strategy

Site selection and characterization processes for deep geologic disposal of high level nuclear waste

International Nuclear Information System (INIS)

Costin, L.S.

1997-10-01

In this paper, the major elements of the site selection and characterization processes used in the US high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the US program, these processes, which are well defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the US program

Tentative job analysis for a high-level, fixed-site, nuclear security officer

International Nuclear Information System (INIS)

Adams, K.G.; Trujillo, A.A.

1977-10-01

A tentative job analysis for a high-level, fixed-site, nuclear security officer is presented. The primary objective of the report is to provide a framework for evaluating the functions of a security officer in physical protection systems. Several job requirements related to duties, basic skills, personal contacts, supervision, working conditions, and decision making are presented. Individual character traits desirable in security officers are described

Site selection and characterization processes for deep geologic disposal of high level nuclear waste

International Nuclear Information System (INIS)

Costin, L.S.

1997-01-01

In this paper, the major elements of the site selection and characterization processes used in the U. S. high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the U. S. program, these processes, which are well-defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the U. S. program. (author). 3 refs., 2 tabs., 5 figs

Site selection and characterization processes for deep geologic disposal of high level nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Costin, L.S. [Sandia National Labs., Albuquerque, NM (United States)

1997-12-31

In this paper, the major elements of the site selection and characterization processes used in the U. S. high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the U. S. program, these processes, which are well-defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the U. S. program. (author). 3 refs., 2 tabs., 5 figs.

Development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratories

International Nuclear Information System (INIS)

1977-06-01

Results of our mining, geological and geotechnical studies provided in support of the development of site suitability criteria for the high level waste repository are presented. The primary purpose of the work was the identification and development of appropriate geotechnical descriptors and coefficients required for the Site Suitability Repository Model. This model was developed by The Analytic Sciences Corporation (TASC) of Reading, Massachusetts and is not described in this report

Development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratories

Energy Technology Data Exchange (ETDEWEB)

1977-06-01

Results of our mining, geological and geotechnical studies provided in support of the development of site suitability criteria for the high level waste repository are presented. The primary purpose of the work was the identification and development of appropriate geotechnical descriptors and coefficients required for the Site Suitability Repository Model. This model was developed by The Analytic Sciences Corporation (TASC) of Reading, Massachusetts and is not described in this report.

Symposium on the development of nuclear waste policy: Siting the high-level nuclear waste repository

International Nuclear Information System (INIS)

Pijawka, K.D.; Mushkatel, A.H.

1991-01-01

The Nuclear Waste Policy Act of 1982 (NWPA) attempted to formulate a viable national policy for managing the disposal of high-level nuclear wastes. The NWPA authorized the selection of two repository sites: the first to be constructed in the West and a second site developed in the eastern United States. A detailed process for site selection was outlined in the NWPA. In addition, the NWPA authorized open-quotes the development of a waste transportation system; required the Department of Energy (DOE) to submit a proposal to construct a facility for monitored retrievable storage (MRS) after conducting a study of the need for, and feasibility of such a facility; and required the President to evaluate the use of the repositories ... for the disposal of high-level waste resulting from defense activitiesclose quotes (DOE, 1988, p. 1). A series of provisions granting oversight participation to states and Indian tribes, as well as a compensation package for the ultimate host state were also included. Responsibility for implementing the NWPA was assigned to DOE

Next Generation Extractants for Cesium Separation from High-Level Waste: From Fundamental Concepts to Site Implementation

International Nuclear Information System (INIS)

Moyer, Bruce A.; Bazelaire, Eve; Bonnesen, Peter V.; Bryan, Jeffrey C.; Delmau, Latitia H.; Engle, Nancy L.; Gorbunova, Maryna G.; Keever, Tamara J.; Levitskaia, Tatiana G.; Sachleben, Richard A.; Tomkins, Bruce A.; Bartsch, Richard A.

2004-01-01

General project objectives. This project seeks a fundamental understanding and major improvement in cesium separation from high-level waste by cesium-selective calixcrown extractants. Systems of particular interest involve novel solvent-extraction systems containing specific members of the calix[4]arene-crown-6 family, alcohol solvating agents, and alkylamines. Questions being addressed pertain to cesium binding strength, extraction selectivity, cesium stripping, and extractant solubility. Enhanced properties in this regard will specifically benefit cleanup projects funded by the USDOE Office of Environmental Management to treat and dispose of high-level radioactive wastes currently stored in underground tanks at the Savannah River Site (SRS), the Hanford site, and the Idaho National Environmental and Engineering Laboratory.1 The most direct beneficiary will be the SRS Salt Processing Project, which has recently identified the Caustic-Side Solvent Extraction (CSSX) process employing a calixcrown as its preferred technology for cesium removal from SRS high level tank waste.2 This technology owes its development in part to fundamental results obtained in this program

Next Generation Extractants for Cesium Separation from High-Level Waste: From Fundamental Concepts to Site Implementation

International Nuclear Information System (INIS)

Moyer, Bruce A; Bazelaire, Eve; Bonnesen, Peter V.; Bryan, Jeffrey C.; Delmau, Laetitia H.; Engle, Nancy L.; Gorbunova, Maryna G.; Keever, Tamara J.; Levitskaia, Tatiana G.; Sachleben, Richard A.; Tomkins, Bruce A.; Bartsch, Richard A.; Talanov, Vladimir S.; Gibson, Harry W.; Jones, Jason W.; Hay, Benjamin P.

2003-01-01

This project seeks a fundamental understanding and major improvement in cesium separation from high-level waste by cesium-selective calixcrown extractants. Systems of particular interest involve novel solvent-extraction systems containing specific members of the calix[4]arene-crown-6 family, alcohol solvating agents, and alkylamines. Questions being addressed pertain to cesium binding strength, extraction selectivity, cesium stripping, and extractant solubility. Enhanced properties in this regard will specifically benefit cleanup projects funded by the USDOE Office of Environmental Management to treat and dispose of high-level radioactive wastes currently stored in underground tanks at the Savannah River Site (SRS), the Hanford site, and the Idaho National Environmental and Engineering Laboratory.1 The most direct beneficiary will be the SRS Salt Processing Project, which has recently identified the Caustic-Side Solvent Extraction (CSSX) process employing a calixcrown as its preferred technology for cesium removal from SRS high-level tank waste.2 This technology owes its development in part to fundamental results obtained in this program

High-level core sample x-ray imaging at the Hanford Site

International Nuclear Information System (INIS)

Weber, J.R.; Keye, J.K.

1995-01-01

Waste tank sampling of radioactive high-level waste is required for continued operations, waste characterization, and site safety. Hanford Site Tank farms consist of 28 double-shell and 149 single-shell underground storage tanks. The single shell tanks are out-of-service and no longer receive liquid waste. Core samples of salt cake and sludge waste are remotely obtained using truck-mounted, core drill platforms. Samples are recovered from tanks through a 2.25 inch (in.) drill pipe in 26-in. steel tubes, 1.5 in. diameter. Drilling parameters vary with different waste types. Because sample recovery has been marginal and inadequate at times, a system was needed to provide drill truck operators with real-time feedback about the physical conditions of the sample and the percent recovery, prior to making nuclear assay measurements and characterizations at the analytical laboratory. Westinghouse hanford Company conducted proof-of -principal radiographic testing to verify the feasibility of a proposed imaging system

The Drigg low-level waste site

International Nuclear Information System (INIS)

1992-01-01

Safe disposal of waste is a vital aspect of any industrial operation whether it be production of plastics, steel or chemicals or handling of radioactive materials. Appropriate methods must be used in every case. Radioactive waste falls into three distinct categories - high, intermediate and low-level. It is the solid low-level waste making up over 90% of the total which this booklet discusses. British Nuclear Fuels plc (BNFL) operates a site for the disposal of solid low-level waste at Driggs, some six kilometres south of Sellafield in West Cumbria. The daily operations and control of the site, the responsibility of the BNFL Waste Management Unit is described. (author)

Site suitability criteria for solidified high level waste repositories

International Nuclear Information System (INIS)

Heckman, R.A.; Holdsworth, T.; Isherwood, D.; Towse, D.F.; Dayem, N.L.

1979-01-01

The NRC is developing a framework of regulations, criteria, and standards. Lawrence Livermore Laboratory provides broad technical support to the NRC for developing this regulatory framework, part of which involves site suitability criteria for solidified high-level wastes (SHLW). Both the regulatory framework and the technical base on which it rests have evolved in time. This document is the second report of the technical support project. It was issued as a draft working paper for a programmatic review held at LLL from August 16 to 18, 1977. It was printed and distributed solely as a briefing document on preliminary methodology and initial findings for the purpose of critical review by those in attendance. These briefing documents are being reprinted now in their original formats as UCID-series reports for the sake of the historical record. Analysis results have evolved as both the models and data base have changed. As a result, the methodology, models, and data base in this document are severely outmoded

Architecting Web Sites for High Performance

Directory of Open Access Journals (Sweden)

Arun Iyengar

2002-01-01

Full Text Available Web site applications are some of the most challenging high-performance applications currently being developed and deployed. The challenges emerge from the specific combination of high variability in workload characteristics and of high performance demands regarding the service level, scalability, availability, and costs. In recent years, a large body of research has addressed the Web site application domain, and a host of innovative software and hardware solutions have been proposed and deployed. This paper is an overview of recent solutions concerning the architectures and the software infrastructures used in building Web site applications. The presentation emphasizes three of the main functions in a complex Web site: the processing of client requests, the control of service levels, and the interaction with remote network caches.

Japan's Siting Process for the Geological Disposal of High-level Radioactive Waste - An International Peer Review

International Nuclear Information System (INIS)

Brassinnes, Stephane; Fabbri, Olivier; Rubenstone, James; Seppaelae, Timo; Siemann, Michael; ); Kwong, Gloria; )

2016-01-01

The Nuclear Energy Agency carried out an independent peer review of Japan's siting process and criteria for the geological disposal of high-level radioactive waste in May 2016. The review concluded that Japan's site screening process is generally in accordance with international practices. As the goal of the siting process is to locate a site - that is both appropriate and accepted by the community - to host a geological disposal facility for high-level radioactive waste, the international review team emphasises in this report the importance of maintaining an open dialogue and interaction between the regulator, the implementer and the public. Dialogue should begin in the early phases and continue throughout the siting process. The international review team also underlines the importance of taking into account feasibility aspects when selecting a site for preliminary investigations, but suggests that it would be inappropriate to set detailed scientific criteria for nationwide screening at this stage. The team has provided extensive advisory remarks in the report as opportunities for improvement, including the recommendation to use clear and consistent terminology in defining the site screening criteria as it is a critical factor in a successful siting process. (authors)

Regional groundwater chemical characteristics of Aqishan pre-selected site for high level radioactive waste repository and its hydrogeological significance

International Nuclear Information System (INIS)

Guo Yonghai; Dong Jiannan; Liu Shufen; Zhou Zhichao

2014-01-01

Aqishan area located in Xinjiang Uygur Automonous Region is one of the main preselected site of disposal repository for high-level radioactive waste (HLW) in our country. Groundwater chemical feature is one of the most important consideration factors in the siting and site evaluation for high-level radioactive waste repository, From 2012 to 2013, the regional field hydrogeochemical investigation was carried out in study area and more than 30 groundwater samples were collected. According to the measurement data, the groundwater chemical features for different subareas are discussed in the paper. Furthermore, the location of discharge area of groundwater in Aqishan area was estimated according to the chemical features of different subareas. (authors)

High-level core sample x-ray imaging at the Hanford Site

International Nuclear Information System (INIS)

Weber, J.R.; Keve, J.K.

1995-10-01

Waste tank sampling of radioactive high-level waste is required for continued operations, waste characterization, and site safety. Hanford Site tank farms consist of 28 double-shell and 149 single-shell underground storage tanks. The single shell tanks are out-of-service an no longer receive liquid waste. Core samples of salt cake and sludge waste are remotely obtained using truck-mounted, core drill platforms. Samples are recovered from tanks through a 2.25 inch (in.) drill pipe in 26-in. steel tubes, 1.5 in. diameter. Drilling parameters vary with different waste types. Because sample recovery has been marginal an inadequate at times, a system was needed to provide drill truck operators with ''real-time feedback'' about the physical condition of the sample and the percent recovery, prior to making nuclear assay measurements and characterizations at the analytical laboratory. The Westinghouse Hanford Company conducted proof-of-principal radiographic testing to verify the feasibility of a proposed imaging system. Tests were conducted using an iridium 192 radiography source to determine the effects of high radiation on image quality. The tests concluded that samplers with a dose rate in excess of 5000 R/hr could be imaged with only a slight loss of image quality and samples less than 1000 R/hr have virtually no effect on image quality. The Mobile Core Sample X-Ray Examination System, a portable vendor-engineered assembly, has components uniquely configured to produce a real-time radiographic system suitable for safely examining radioactive tank core segments collected at the Hanford Site. The radiographic region of interest extends from the bottom (valve) of the sampler upward 19 to 20 in. The purpose of the Mobile Core Sample X-Ray Examination System is to examine the physical contents of core samples after removal from the tank and prior to placement in an onsite transfer cask

High-level radioactive waste disposal: Key geochemical issues and information needs for site characterization

International Nuclear Information System (INIS)

Brooks, D.J.; Bembia, P.J.; Bradbury, J.W.; Jackson, K.C.; Kelly, W.R.; Kovach, L.A.; Mo, T.; Tesoriero, J.A.

1986-01-01

Geochemistry plays a key role in determining the potential of a high-level radioactive waste disposal site for long-term radionuclide containment and isolation. The Nuclear Regulatory Commission (NRC) has developed a set of issues and information needs important for characterizing geochemistry at the potential sites being investigated by the Department of Energy Basalt Waste Isolation Project, Nevada Nuclear Waste Storage Investigations project, and Salt Repository Project. The NRC site issues and information needs consider (1) the geochemical environment of the repository, (2) changes to the initial geochemical environment caused by construction and waste emplacement, and (3) interactions that affect the transport of waste radionuclides to the accessible environment. The development of these issues and information needs supports the ongoing effort of the NRC to identify and address areas of geochemical data uncertainty during prelicensing interactions

Workshop material for state review of USNRC site suitability criteria for high-level radioactive waste repositories

International Nuclear Information System (INIS)

1977-08-01

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

High level waste repository site suitability criteria. Environmental impact statement methodology

International Nuclear Information System (INIS)

1977-06-01

The approach (methodology) which has been developed for the preparation of the environmental impact statement (EIS) is described. A suggested outline is presented for the High Level Waste Repository Site Suitability Criteria EIS together with a detailed description of the approach to be used in preparing the EIS. In addition, a methodology is presented by which the necessary cost/benefit/risk comparisons of alternative sets of site suitability criteria can be made. The TERA environmental research data bank, a computerized data bank which contained information on current and historical licensing activities for power plants was modified to include information on generic or programmatic EIS related issues. The content of the modified data bank was utilized to develop the EIS outline presented in this report. The report recommends that a modified matrix evaluation approach be used to make the cost/benefit/risk comparisons. The suggested matrix is designed to facilitate between criteria comparative analyses of economic, environmental, sociological and radiological risk factors. The quantitative compositing of dollar cost and benefits, environmental and sociological impacts, and radiological risks is to be performed using a semi-analytical, semi-visual procedure based on the concept of ''decision surfaces.''

Workshops for state review of site suitability criteria for high-level radioactive waste repositories: analysis and recommendations

International Nuclear Information System (INIS)

1978-02-01

The purpose of this report is to present the views and recommendations of invited State officials and legislators participating in a workshop concerned with preliminary site suitability criteria for high level radioactive waste repositories. The workshops were open to the public and were conducted by the U. S. Nuclear Regulatory Commission (NRC) during September 1977 in three regional locations across the United States. This contractor report is the second of two reports and consolidates the discussion by State officials on the role of a State in siting a repository, NRC's waste management program, the transportation of high level wastes, the number and location of repositories and concerns with the socio-economic impacts of siting a repository in a community. The recommendations to the NRC can be categorized into four areas. These were: (1) general recommendations, (2) procedural recommendations, (3) recommendations for improving communications, and (4) specific recommendations on the preliminary siting criteria. The recommendations emphasized the need for early State involvement in the siting process, the need for an impacted State to assess repository operations, the need for early solution of waste transportation concerns, and the requirement that any repository developed insure the protection of the public health and safety as its most important characteristic. Other participant recommendations are included in the body of the report

On-site storage of high level nuclear waste: Attitudes and perceptions of local residents

International Nuclear Information System (INIS)

Bassett, G.W. Jr.; Jenkins-Smith, H.C.; Silva, C.

1996-01-01

No public policy issue has been as difficult as high-level nuclear waste. Debates continue regarding Yucca Mountain as a disposal site, and - more generally - the appropriateness of geologic disposal and the need to act quickly. Previous research has focused on possible social, political, and economic consequences of a facility in Nevada. Impacts have been predicted to be potentially large and to emanate mainly from stigmatization of the region due to increased perceptions of risk. Analogous impacts from leaving waste at power plants have been either ignored or assumed to be negligible. This paper presents survey results on attitudes of residents in three countries where nuclear waste is currently stored. Topics include perceived risk, knowledge of nuclear waste and radiation, and impacts on jobs, tourism, and housing values from leaving waste on site. Results are similar to what has been reported for Nevada; the public is concerned about possible adverse effects from on-site storage of waste. 24 refs., 7 figs., 5 tabs

On-site storage of high level nuclear waste: attitudes and perceptions of local residents.

Science.gov (United States)

Bassett, G W; Jenkins-Smith, H C; Silva, C

1996-06-01

No public policy issue has been as difficult as high-level nuclear waste. Debates continue regarding Yucca Mountain as a disposal site, and-more generally-the appropriateness of geologic disposal and the need to act quickly. Previous research has focused on possible social, political, and economic consequences of a facility in Nevada. Impacts have been predicted to be potentially large and to emanate mainly from stigmatization of the region due to increased perceptions of risk. Analogous impacts from leaving waste at power plants have been either ignored or assumed to be negligible. This paper presents survey results on attitudes of residents in three counties where nuclear waste is currently stored. Topics include perceived risk, knowledge of nuclear waste and radiation, and impacts on jobs, tourism, and housing values from leaving waste on site. Results are similar to what has been reported for Nevada; the public is concerned about possible adverse effects from on-site storage of waste.

Workshops for state review of site suitability criteria for high-level radioactive waste repositories: analysis and recommendations

International Nuclear Information System (INIS)

1978-02-01

The responses from various discussion groups on site suitability criteria for high-level radioactive waste repositories are presented. The consensus, principal concern, and minority opinion on each issue are given. The visual aids used in the workshop are included

Siting, design and construction of a deep geological repository for the disposal of high level and alpha bearing wastes

International Nuclear Information System (INIS)

1990-06-01

The main objective of this document is to summarize the basic principles and approaches to siting, design and construction of a deep geological repository for disposal of high level and alpha bearing radioactive wastes, as commonly agreed upon by Member States. This report is addressed to decision makers and technical managers as well as to specialists planning for siting, design and construction of geological repositories for disposal of high level and alpha bearing wastes. This document is intended to provide Member States of the IAEA with a summary outline for the responsible implementing organizations to use for siting, designing and constructing confinement systems for high level and alpha bearing radioactive waste in accordance with the protection objectives set by national regulating authorities or derived from safety fundamentals and standards of the IAEA. The protection objectives will be achieved by the isolation of the radionuclides from the environment by a repository system, which consists of a series of man made and natural safety barriers. Engineered barriers are used to enhance natural geological containment in a variety of ways. They must complement the natural barriers to provide adequate safety and necessary redundancy to the barrier system to ensure that safety standards are met. Because of the long timescales involved and the important role of the natural barrier formed by the host rock, the site selection process is a key activity in the repository design and development programme. The choice of the site, the investigation of its geological setting, the exploration of the regional hydrogeological setting and the primary underground excavations are all considered to be part of the siting process. 16 refs

Public opposition to the siting of the high-level nuclear waste repository: The importance of trust

International Nuclear Information System (INIS)

Pijawka, K.D.; Mushkatel, A.H.

1991-01-01

This paper examines several dimensions of public opposition to the proposed siting of the high-level nuclear waste repository at Yucca Mountain. In order to provide a context for the public's views of the repository in metropolitan Clark County, both governmental studies of the repository siting process are analyzed, as well as elements of the Nuclear Waste Policy Act. This analysis suggests that one potentially key component of the public's opposition to the siting, as well as their perceptions of risk of the facility, may be the result of a lack of trust in the Department of Energy. Empirical analysis of survey data collected in Nevada in 1988 confirms the strong relationship between political trust and repository risk perceptions

A dynamic simulation model of the Savannah River Site high level waste complex

International Nuclear Information System (INIS)

Gregory, M.V.; Aull, J.E.; Dimenna, R.A.

1994-01-01

A detailed, dynamic simulation entire high level radioactive waste complex at the Savannah River Site has been developed using SPEEDUP(tm) software. The model represents mass transfer, evaporation, precipitation, sludge washing, effluent treatment, and vitrification unit operation processes through the solution of 7800 coupled differential and algebraic equations. Twenty-seven discrete chemical constituents are tracked through the unit operations. The simultaneous simultaneous simulation of concurrent batch and continuous processes is achieved by several novel, customized SPEEDUP(tm) algorithms. Due to the model's computational burden, a high-end work station is required: simulation of a years operation of the complex requires approximately three CPU hours on an IBM RS/6000 Model 590 processor. The model will be used to develop optimal high level waste (HLW) processing strategies over a thirty year time horizon. It will be employed to better understand the dynamic inter-relationships between different HLW unit operations, and to suggest strategies that will maximize available working tank space during the early years of operation and minimize overall waste processing cost over the long-term history of the complex. Model validation runs are currently underway with comparisons against actual plant operating data providing an excellent match

Draft environmental impact statement. High-level waste repository site suitability criteria

International Nuclear Information System (INIS)

1978-01-01

The purpose of HLWRSSC is to present guidelines which will help in the development of safe waste management schemes. Current regulations require solidification of all high-level waste within 5 years of their generation and transfer to a Federal waste repository within 10 years. Development of the proposed HLWRSSC is part of the overall NRC program to close the ''back end'' of the commercial LWR fuel cycle. In this document, the need for the HLWRSSC is reviewed, and the national energy policy, the need for electrical energy, and the nuclear fuel cycle are discussed. Considerations for HLWRSSC are presented, including the nature of the repository, important site-related factors, and radiological risk assessment methodology. Radiological and nonradiological environment impacts associated with the HLWRSSC are defined. Alternatives to the criteria are presented, and the cost-benefit-risk evaluation is reviewed

Cost estimate of high-level radioactive waste containers for the Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Russell, E.W.; Clarke, W. [Lawrence Livermore National Lab., CA (United States); Domian, H.A. [Babcock and Wilcox Co., Lynchburg, VA (United States); Madson, A.A. [Kaiser Engineers California Corp., Oakland, CA (United States)

1991-08-01

This report summarizes the bottoms-up cost estimates for fabrication of high-level radioactive waste disposal containers based on the Site Characterization Plan Conceptual Design (SCP-CD). These estimates were acquired by Babcock and Wilcox (B&S) under sub-contract to Lawrence Livermore National Laboratory (LLNL) for the Yucca Mountain Site Characterization Project (YMP). The estimates were obtained for two leading container candidate materials (Alloy 825 and CDA 715), and from other three vendors who were selected from a list of twenty solicited. Three types of container designs were analyzed that represent containers for spent fuel, and for vitrified high-level waste (HLW). The container internal structures were assumed to be AISI-304 stainless steel in all cases, with an annual production rate of 750 containers. Subjective techniques were used for estimating QA/QC costs based on vendor experience and the specifications derived for the LLNL-YMP Quality Assurance program. In addition, an independent QA/QC analysis is reported which was prepared by Kasier Engineering. Based on the cost estimates developed, LLNL recommends that values of $825K and $62K be used for the 1991 TSLCC for the spent fuel and HLW containers, respectively. These numbers represent the most conservative among the three vendors, and are for the high-nickel anstenitic steel (Alloy 825). 6 refs., 7 figs.

Cost estimate of high-level radioactive waste containers for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Russell, E.W.; Clarke, W.; Domian, H.A.; Madson, A.A.

1991-08-01

This report summarizes the bottoms-up cost estimates for fabrication of high-level radioactive waste disposal containers based on the Site Characterization Plan Conceptual Design (SCP-CD). These estimates were acquired by Babcock and Wilcox (B ampersand S) under sub-contract to Lawrence Livermore National Laboratory (LLNL) for the Yucca Mountain Site Characterization Project (YMP). The estimates were obtained for two leading container candidate materials (Alloy 825 and CDA 715), and from other three vendors who were selected from a list of twenty solicited. Three types of container designs were analyzed that represent containers for spent fuel, and for vitrified high-level waste (HLW). The container internal structures were assumed to be AISI-304 stainless steel in all cases, with an annual production rate of 750 containers. Subjective techniques were used for estimating QA/QC costs based on vendor experience and the specifications derived for the LLNL-YMP Quality Assurance program. In addition, an independent QA/QC analysis is reported which was prepared by Kasier Engineering. Based on the cost estimates developed, LLNL recommends that values of $825K and $62K be used for the 1991 TSLCC for the spent fuel and HLW containers, respectively. These numbers represent the most conservative among the three vendors, and are for the high-nickel anstenitic steel (Alloy 825). 6 refs., 7 figs

Site selection factors for repositories of solid high-level and alpha-bearing wastes in geological formations

International Nuclear Information System (INIS)

1977-01-01

The purpose of this report is to provide guidelines for the selection and evaluation of suitable areas and sites for the disposal of solid high-level and alpha-bearing wastes into geological formations. This report is also intended to provide summary information on many types of geological formations underlying the land masses that might be considered as well as guidance on the geological and hydrological factors that should be investigated to demonstrate the suitability of the formations. In addition, other factors that should be considered in selecting a site for a radioactive waste repository are discussed briefly. The information, as presented, was developed to the extent of current technology for application to the evaluation of deep (greater than about 300 metres below ground level) geological formations in the selection of suitable areas for the disposal of solid or solidified high-level and alpha-bearing wastes. The extreme complexity of many geological environments and of the rock features that govern the presence and circulation of groundwater does not make it feasible to derive strict criteria for the selection of a site for a radioactive waste repository in a geological formation. Each potential repository location must be evaluated according to its own unique geological and hydrological setting. Therefore, only general guidance is offered, and this is done through discussion of the many factors that need to be considered in order to obtain the necessary assurances that the radionuclides will be confined in the geological repository over the required period of time

Site selection factors for repositories of solid high-level and alpha-bearing wastes in geological formations

Energy Technology Data Exchange (ETDEWEB)

1977-01-01

The purpose of this report is to provide guidelines for the selection and evaluation of suitable areas and sites for the disposal of solid high-level and alpha-bearing wastes into geological formations. This report is also intended to provide summary information on many types of geological formations underlying the land masses that might be considered as well as guidance on the geological and hydrological factors that should be investigated to demonstrate the suitability of the formations. In addition, other factors that should be considered in selecting a site for a radioactive waste repository are discussed briefly. The information, as presented, was developed to the extent of current technology for application to the evaluation of deep (greater than about 300 meters below ground level) geological formations in the selection of suitable areas for the disposal of solid or solidified high-level and alpha-bearing wastes. The extreme complexity of many geological environments and of the rock features that govern the presence and circulation of groundwater does not make it feasible to derive strict criteria for the selection of a site for a radioactive waste repository in a geological formation. Each potential repository location must be evaluated according to its own unique geological and hydrological setting. Therefore, only general guidance is offered, and this is done through discussion of the many factors that need to be considered in order to obtain the necessary assurances that the radionuclides will be confined in the geological repository over the required period of time.

Conceptualization of a hypothetical high-level nuclear waste repository site in unsaturated, fractured tuff

International Nuclear Information System (INIS)

Parsons, A.M.; Olague, N.E.; Gallegos, D.P.

1991-01-01

Under the sponsorship of the US Nuclear Regulatory Commission (NRC), Sandia National Laboratories (SNL) is developing a performance assessment methodology for the analysis of long-term disposal and isolation of high-level nuclear wastes (HLW) in alternative geologic media. As part of this exercise, SNL created a conceptualization of ground-water flow and radionuclide transport in the far field of a hypothetical HLW repository site located in unsaturated, fractured tuff formations. This study provides a foundation for the development of conceptual mathematical, and numerical models to be used in this performance assessment methodology. This conceptualization is site specific in terms of geometry, the regional ground-water flow system, stratigraphy, and structure in that these are based on information from Yucca Mountain located on the Nevada Test Site. However, in terms of processes in unsaturated, fractured, porous media, the model is generic. This report also provides a review and evaluation of previously proposed conceptual models of unsaturated and saturated flow and solute transport. This report provides a qualitative description of a hypothetical HLW repository site in fractured tuff. However, evaluation of the current knowledge of flow and transport at Yucca Mountain does not yield a single conceptual model. Instead, multiple conceptual models are possible given the existing information

Conceptualization of a hypothetical high-level nuclear waste repository site in unsaturated, fractured tuff

Energy Technology Data Exchange (ETDEWEB)

Parsons, A.M.; Olague, N.E.; Gallegos, D.P. [Sandia National Labs., Albuquerque, NM (USA)

1991-01-01

Under the sponsorship of the US Nuclear Regulatory Commission (NRC), Sandia National Laboratories (SNL) is developing a performance assessment methodology for the analysis of long-term disposal and isolation of high-level nuclear wastes (HLW) in alternative geologic media. As part of this exercise, SNL created a conceptualization of ground-water flow and radionuclide transport in the far field of a hypothetical HLW repository site located in unsaturated, fractured tuff formations. This study provides a foundation for the development of conceptual mathematical, and numerical models to be used in this performance assessment methodology. This conceptualization is site specific in terms of geometry, the regional ground-water flow system, stratigraphy, and structure in that these are based on information from Yucca Mountain located on the Nevada Test Site. However, in terms of processes in unsaturated, fractured, porous media, the model is generic. This report also provides a review and evaluation of previously proposed conceptual models of unsaturated and saturated flow and solute transport. This report provides a qualitative description of a hypothetical HLW repository site in fractured tuff. However, evaluation of the current knowledge of flow and transport at Yucca Mountain does not yield a single conceptual model. Instead, multiple conceptual models are possible given the existing information.

High-level waste processing and disposal

International Nuclear Information System (INIS)

Crandall, J.L.; Krause, H.; Sombret, C.; Uematsu, K.

1984-01-01

The national high-level waste disposal plans for France, the Federal Republic of Germany, Japan, and the United States are covered. Three conclusions are reached. The first conclusion is that an excellent technology already exists for high-level waste disposal. With appropriate packaging, spent fuel seems to be an acceptable waste form. Borosilicate glass reprocessing waste forms are well understood, in production in France, and scheduled for production in the next few years in a number of other countries. For final disposal, a number of candidate geological repository sites have been identified and several demonstration sites opened. The second conclusion is that adequate financing and a legal basis for waste disposal are in place in most countries. Costs of high-level waste disposal will probably add about 5 to 10% to the costs of nuclear electric power. The third conclusion is less optimistic. Political problems remain formidable in highly conservative regulations, in qualifying a final disposal site, and in securing acceptable transport routes

The Beishan underground research laboratory for geological disposal of high-level radioactive waste in China: Planning, site selection, site characterization and in situ tests

Directory of Open Access Journals (Sweden)

Ju Wang

2018-06-01

Full Text Available With the rapid development of nuclear power in China, the disposal of high-level radioactive waste (HLW has become an important issue for nuclear safety and environmental protection. Deep geological disposal is internationally accepted as a feasible and safe way to dispose of HLW, and underground research laboratories (URLs play an important and multi-faceted role in the development of HLW repositories. This paper introduces the overall planning and the latest progress for China's URL. On the basis of the proposed strategy to build an area-specific URL in combination with a comprehensive evaluation of the site selection results obtained during the last 33 years, the Xinchang site in the Beishan area, located in Gansu Province of northwestern China, has been selected as the final site for China's first URL built in granite. In the process of characterizing the Xinchang URL site, a series of investigations, including borehole drilling, geological mapping, geophysical surveying, hydraulic testing and in situ stress measurements, has been conducted. The investigation results indicate that the geological, hydrogeological, engineering geological and geochemical conditions of the Xinchang site are very suitable for URL construction. Meanwhile, to validate and develop construction technologies for the Beishan URL, the Beishan exploration tunnel (BET, which is a 50-m-deep facility in the Jiujing sub-area, has been constructed and several in situ tests, such as drill-and-blast tests, characterization of the excavation damaged zone (EDZ, and long-term deformation monitoring of surrounding rocks, have been performed in the BET. The methodologies and technologies established in the BET will serve for URL construction. According to the achievements of the characterization of the URL site, a preliminary design of the URL with a maximum depth of 560 m is proposed and necessary in situ tests in the URL are planned. Keywords: Beishan, Xinchang site, Granite

Management of scientific and engineering data collected during site characterization of a potential high-level waste repository

International Nuclear Information System (INIS)

Newbury, C.M.; Heitland, G.W.

1992-01-01

This paper discusses the characterization of Yucca Mountain as a potential site for a high-level nuclear waste repository encompasses many diverse investigations to determine the nature of the site. Laboratory and on-site investigations are being conducted of the geology, hydrology, mineralogy, paleoclimate, geotechnical properties, and past use of the area, to name a few. Effective use of the data from these investigations requires development of a system for the collection, storage, and dissemination of those scientific and engineering data needed to support model development, design, and performance assessment. The time and budgetary constraints associated with this project make sharing of technical data within the geoscience community absolutely critical to the successful solution of the complex scientific problem challenging us

Site safety requirements for high level waste disposal

International Nuclear Information System (INIS)

Chen Weiming; Wang Ju

2006-01-01

This paper outlines the content, status and trend of site safety requirements of International Atomic Energy Agency, America, France, Sweden, Finland and Japan. Site safety requirements are usually represented as advantageous vis-a-vis disadvantagous conditions, and potential advantage vis-a-vis disadvantage conditions, respectively in aspects of geohydrology, geochemistry, lithology, climate and human intrusion etc. Study framework and steps of site safety requirements for China are discussed under the view of systems science. (authors)

Resolution of the ferrocyanide safety issue for the Hanford site high-level waste tanks

International Nuclear Information System (INIS)

Cash, R.J.

1996-01-01

This paper describes the approach used to resolve the ferrocyanide safety issue, a process that began in 1990 after heightened concern was expressed by various government agencies about the safety of Hanford site high-level waste tanks. At the time, little was known about ferrocyanide-nitrate/nitrite reactions and the potential for offsite releases of radioactivity from the Hanford Site. Recent studies have shown that the combined effects of temperature, radiation, and pH during more than 38 years of storage have destroyed most of the ferrocyanide originally added to tanks. This has been proven in the laboratory using flowsheet-derived waste simulants and confirmed by waste samples obtained from the ferrocyanide tanks. The resulting tank waste sludges are too dilute to support a sustained exothermic reaction, even if dried out and heated to temperatures of at least 250 C. The US Department of Energy (DOE) has been requested to close the ferrocyanide safety issue

Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects

International Nuclear Information System (INIS)

Meyer, R.E.; Arnold, W.D.; O'Kelley, G.D.; Case, F.I.; Land, J.F.

1989-08-01

Information that is being developed by projects within the Department of Energy (DOE) pertinent to the potential geochemical behavior of radionuclides at candidate sites for a high-level radioactive waste repository is being evaluated by Oak Ridge National Laboratory (ORNL) for the Nuclear Regulatory Commission (NRC). During this report period, all experiments were conducted with tuff from the proposed high-level nuclear waste site at Yucca Mountain, Nevada. The principal emphasis in this report period was on column studies of migration of uranium and technetium in water from well J-13 at the Yucca Mountain site. Columns 1 cm in diameter and about 5 cm long were constructed and carefully packed with ground tuff. The characteristics of the columns were tested by determination of elution curves of tritium and TcO 4 - . Elution peaks obtained in past studies with uranium were asymmetrical and the shapes were often complex, observations that suggested irreversibilities in the sorption reaction. To try to understand these observations, the effects of flow rate and temperature on uranium migration were studied in detail. Sorption ratios calculated from the elution peaks became larger as the flow rate decreased and as the temperature increased. These observations support the conclusion that the sorption of uranium is kinetically hindered. To confirm this, batch sorption ratio experiments were completed for uranium as a function of time for a variety of conditions

Siting the nation's first high-level nuclear waste repository: Social impacts for Utah

International Nuclear Information System (INIS)

Olshansky, S.J.

1986-01-01

The siting of a high-level nuclear waste repository in the United States has been an issue of great controversy, particulary for the states under consideration. In addition to concerns expressed about the geological stability of the proposed sites, numerous social issues have been raised by the general public--most of which have been addressed by the draft environmental impact statements. Among the social impacts raised by the Department of Engery and the general public, those receiving the greatest attention were the potential influence of the repository on local economics, tourism, and the health status of the local residents. The major issues of interest in the present study include 1) the effects of respondent knowledge of nuclear waste disposal issues on opinions of health effects and tourism, particularly as they are affected by visitation patterns, and 2) the effects of occupation and education (in particular) on knowledge of nuclear waste disposal issues and opinions on technical and non-technical aspects of siting the repository. Preliminary results indicate that only about 40 percent of the respondents have visited the national parks in southeastern Utah, but over 70 percent feel they are informed about the issues associated with siting the repository. Over 60 percent of the respondents were very concerned about the possible negative effect the repository could have on jobs, tourism, health effects, and environmental quality. Cross-tabulations indicate that the respondents self rating on knowledge of nuclear disposal issues has a statistically significant influence on responses to socioeconomic issues, yet the same self rating scale is significantly influenced by the frequency with which respondents have visited the national parks in southeastern Utah

Discussion of quantitative assessment index system of suitability of the site for geological disposal repository of high-level radioactive waste

International Nuclear Information System (INIS)

Su Rui; Wang Ju

2014-01-01

Site selection and suitability assessment of site are one of important tasks of research and development of geological disposal engineering for high-level radioactive waste (HLW). Quantitative assessment of suitability of the site is based on the scientific, reasonable and operational index system. The discussion of index screening of quantitative assessment of suitability of the site is conducted. Principle of index screening is presented and index systems are established for different stages of site selection, including planning stage of site selection, region or area investigation stage, site characterization and site confirmation stage. But the considerations are taken of the complexity of site selection of geological disposal engineering for HLW and itself development of quantitative assessment method, so improvement of the index systems presented above is needed in the further. (authors)

Surveys for desert tortoise on the proposed site of a high-level nuclear waste repository at the Nevada Test Site

International Nuclear Information System (INIS)

Collins, E.; Sauls, M.L.; O'Farrell, T.P.

1983-01-01

The National Waste Terminal Storage Program is a national search for suitable sites to isolate commercial spent nuclear fuel or high-level radioactive waste. The Nevada Nuclear Waste Storage Investigation (NNWSI) managed by the U.S. Department of Energy (DOE), Nevada Operations Office, was initiated to study the suitability of a portion of Yucca Mountain on the DOE's Nevada Test Site (NTS) as a location for such a repository. EG and G was contracted to provide information concerning the ecosystems encountered on the site. A comprehensive literature survey was conducted to evaluate the status and completeness of the existing biological information for the previously undisturbed area. Site specific studies were begun in 1981 when preliminary field surveys confirmed the presence of the desert tortoise (Gopherus agassizi) within the project area FY82 studies were designed to determine the overall distribution and abundance of the tortoise within the area likely to be impacted by NNWSI activities. The Yucca Mountain area of the Nevada Test Site is situated close to the northern range limit of the desert tortoise. Prior to the 1982 surveys, the desert tortoise was reported from only nine locations on NTS. A known population had been under study in Rock Valley about 25 miles southeast of the project area. However, the distribution and population densities of tortoise in the southwest portion of NTS were virtually unknown. Results of our surveys indicate that desert tortoise can be expected, albeit in small numbers, in a wide range of Mojavean and Transitional habitats

Geo-metadata design for the GIS of the pre-selected site for China's high-level radioactive waste repository

International Nuclear Information System (INIS)

Zhong Xia; Wang Ju; Huang Shutao; Wang Shuhong; Gao Min

2008-01-01

The information system for the geological disposal of high-level radioactive waste aims at the integrated management and full application of multi-sourceful information in the research for geological disposal of high-level radioactive waste. And the establishment and operation of the system need geo-metadata's support of multi-sourceful information. In the paper, on the basis of geo-data analysis for pre-selected site of disposal of high-level radioactive waste, we can apply the existing metadata standards. Also we can research and design the content information, management pattern and application for geo-metadata of the multi-sourceful information. (authors)

Region-scale groundwater flow modelling of generic high level waste disposal sites

International Nuclear Information System (INIS)

Metcalfe, D.

1996-02-01

Regional-scale groundwater flow modelling analyses are performed on generic high level waste (HLW) disposal sites to assess the extent to which a large crystalline rock mass such as a pluton or batholith can be expected to contain and isolate HLW in terms of hydraulic considerations, for a variety of geologic and hydrogeologic conditions. The two-dimensional cross-sectional conceptual models of generic HLW disposal sites are evaluated using SWIFT III, which is a finite-difference flow and transport code. All steps leading to the final results and conclusions are incorporated in this report. The available data and information on geological and hydrogeologic conditions in plutons and batholiths are summarized. The generic conceptual models developed from this information are defined in terms of the finite difference grid, the geologic and hydrogeologic properties and the hydrologic boundary conditions used. The modelled results are described with contour maps showing the modelled head fields, groundwater flow paths and travel times and groundwater flux rates within the modelled systems. The results of the modelling analyses are used to develop general conclusions on the scales and patterns of groundwater flow in granitic plutons and batholiths. The conclusions focus on geologic and hydrogeologic characteristics that can result in favourable conditions, in terms of hydraulic considerations, for a HLW repository. (author) 43 refs., 9 tabs., 40 figs

National high-level waste systems analysis report

Energy Technology Data Exchange (ETDEWEB)

Kristofferson, K.; Oholleran, T.P.; Powell, R.H.

1995-09-01

This report documents the assessment of budgetary impacts, constraints, and repository availability on the storage and treatment of high-level waste and on both existing and pending negotiated milestones. The impacts of the availabilities of various treatment systems on schedule and throughput at four Department of Energy sites are compared to repository readiness in order to determine the prudent application of resources. The information modeled for each of these sites is integrated with a single national model. The report suggests a high-level-waste model that offers a national perspective on all high-level waste treatment and storage systems managed by the Department of Energy.

National high-level waste systems analysis report

International Nuclear Information System (INIS)

Kristofferson, K.; Oholleran, T.P.; Powell, R.H.

1995-09-01

This report documents the assessment of budgetary impacts, constraints, and repository availability on the storage and treatment of high-level waste and on both existing and pending negotiated milestones. The impacts of the availabilities of various treatment systems on schedule and throughput at four Department of Energy sites are compared to repository readiness in order to determine the prudent application of resources. The information modeled for each of these sites is integrated with a single national model. The report suggests a high-level-waste model that offers a national perspective on all high-level waste treatment and storage systems managed by the Department of Energy

Overview of Hanford Site High-Level Waste Tank Gas and Vapor Dynamics

Energy Technology Data Exchange (ETDEWEB)

Huckaby, James L.; Mahoney, Lenna A.; Droppo, James G.; Meacham, Joseph E.

2004-08-31

Hanford Site processes associated with the chemical separation of plutonium from uranium and other fission products produced a variety of volatile, semivolatile, and nonvolatile organic and inorganic waste chemicals that were sent to high-level waste tanks. These chemicals have undergone and continue to undergo radiolytic and thermal reactions in the tanks to produce a wide variety of degradation reaction products. The origins of the organic wastes, the chemical reactions they undergo, and their reaction products have recently been examined by Stock (2004). Stock gives particular attention to explaining the presence of various types of volatile and semivolatile organic species identified in headspace air samples. This report complements the Stock report by examining the storage of volatile and semivolatile species in the waste, their transport through any overburden of waste to the tank headspaces, the physical phenomena affecting their concentrations in the headspaces, and their eventual release into the atmosphere above the tanks.

High-Level Waste Melter Study Report

Energy Technology Data Exchange (ETDEWEB)

Perez, Joseph M.; Bickford, Dennis F.; Day, Delbert E.; Kim, Dong-Sang; Lambert, Steven L.; Marra, Sharon L.; Peeler, David K.; Strachan, Denis M.; Triplett, Mark B.; Vienna, John D.; Wittman, Richard S.

2001-07-13

At the Hanford Site in Richland, Washington, the path to site cleanup involves vitrification of the majority of the wastes that currently reside in large underground tanks. A Joule-heated glass melter is the equipment of choice for vitrifying the high-level fraction of these wastes. Even though this technology has general national and international acceptance, opportunities may exist to improve or change the technology to reduce the enormous cost of accomplishing the mission of site cleanup. Consequently, the U.S. Department of Energy requested the staff of the Tanks Focus Area to review immobilization technologies, waste forms, and modifications to requirements for solidification of the high-level waste fraction at Hanford to determine what aspects could affect cost reductions with reasonable long-term risk. The results of this study are summarized in this report.

Final storage high-level radioactive waste in Sweden - the way to the 2009 siting decision

International Nuclear Information System (INIS)

Schneider, Horst

2010-01-01

In Sweden, high-level radioactive waste producing heat, i.e. spent fuel, is to be emplaced for final storage on the site of Forsmark, which also holds three reactor units. The siting decision was taken in June 2009. A 100 percent private company, a merger of the commercial nuclear power plant operators as producers of the waste, is responsible for the siting decision as well as for waste storage. Major impulses were given to the back-end fuel cycle policy in the early 1970s. Sweden practically gave up the reprocessing option very soon, but kept on pursuing final storage in deep geologic formations. Between 1977, when legislation was adopted with conditions relating to repository storage, and 2009, when the decision in favour of the Forsmark site was taken, the path followed was not always a straight line. The boundary conditions, such as the organization of the repository and procedural and safety criteria established by the government, are interesting with regard to their influence on the siting decision, if any. For this reason, the approaches chosen and their connections with government criteria and with geological conditions in Sweden, including their impacts on the repository concept chosen, will be examined. After a summary review of developments in Sweden, filing of the licensing application and the accompanying documents up to commissioning of the repository, a short comparison will be made with the situation in Germany, especially the status reached of the Gorleben salt dome, highlighting and evaluating important criteria and parameters. Sweden as a model is important especially in these respects: A repository site was found by a private company in consensus with the local government within the framework of government criteria, and with ultimate responsibility resting with the government; the local government of a place not winning the siting decision is disappointed although it will have the conditioning plant and receive higher grants; it was not only

Low-level waste disposal site selection demonstration

International Nuclear Information System (INIS)

Rogers, V.C.

1984-01-01

This paper discusses the results of recent studies undertaken at EPRI related to low-level waste disposal technology. The initial work provided an overview of the state of the art including an assessment of its influence upon transportation costs and waste form requirements. The paper discusses work done on the overall system design aspects and computer modeling of disposal site performance characteristics. The results of this analysis are presented and provide a relative ranking of the importance of disposal parameters. This allows trade-off evaluations to be made of factors important in the design of a shallow land burial facility. To help minimize the impact of a shortage of low-level radioactive waste disposal sites, EPRI is closely observing the development of bellweather projects for developing new sites. The purpose of this activity is to provide information about lessons learned in those projects in order to expedite the development of additional disposal facilities. This paper describes most of the major stems in selecting a low-level radioactive waste disposal site in Texas. It shows how the Texas Low-Level Radioactive Waste Disposal Authority started with a wide range of potential siting areas in Texas and narrowed its attention down to a few preferred sites. The parameters used to discriminate between large areas of Texas and, eventually, 50 candidate disposal sites are described, along with the steps in the process. The Texas process is compared to those described in DOE and EPRI handbooks on site selection and to pertinent NRC requirements. The paper also describes how an inventory of low-level waste specific to Texas was developed and applied in preliminary performance assessments of two candidate sites. Finally, generic closure requirements and closure operations for low-level waste facilities in arid regions are given

Reading level of privacy policies on Internet health Web sites.

Science.gov (United States)

Graber, Mark A; D'Alessandro, Donna M; Johnson-West, Jill

2002-07-01

Most individuals would like to maintain the privacy of their medical information on the World Wide Web (WWW). In response, commercial interests and other sites post privacy policies that are designed to inform users of how their information will be used. However, it is not known if these statements are comprehensible to most WWW users. The purpose of this study was to determine the reading level of privacy statements on Internet health Web sites and to determine whether these statements can inform users of their rights. This was a descriptive study. Eighty Internet health sites were examined and the readability of their privacy policies was determined. The selected sample included the top 25 Internet health sites as well as other sites that a user might encounter while researching a common problem such as high blood pressure. Sixty percent of the sites were commercial (.com), 17.5% were organizations (.org), 8.8% were from the United Kingdom (.uk), 3.8% were United States governmental (.gov), and 2.5% were educational (.edu). The readability level of the privacy policies was calculated using the Flesch, the Fry, and the SMOG readability levels. Of the 80 Internet health Web sites studied, 30% (including 23% of the commercial Web sites) had no privacy policy posted. The average readability level of the remaining sites required 2 years of college level education to comprehend, and no Web site had a privacy policy that was comprehensible by most English-speaking individuals in the United States. The privacy policies of health Web sites are not easily understood by most individuals in the United States and do not serve to inform users of their rights. Possible remedies include rewriting policies to make them comprehensible and protecting online health information by using legal statutes or standardized insignias indicating compliance with a set of privacy standards (eg, "Health on the Net" [HON] http://www.hon.ch).

Workshops for state review of site suitability criteria for high-level radioactive waste repositories. Discussion Group reports

International Nuclear Information System (INIS)

1977-10-01

The NRC Waste Management Program and the Office of State Programs held three regional workshops to solicit ideas from State executives and legislators on the siting and licensing procedures for high level waste repositories and to solicit comments on the NRC preliminary site suitability criteria. The workshops were held in Denver, Colorado; New Orleans, Louisiana; and Philadelphia, Pennsylvania during the period 19-30 September 1977. The reports from these workshops are contained herein. The workshops were attended by 170 invited State executives and legislators from 46 states. In addition, there were over 80 observers from diverse backgrounds including the general public, government, industry, professional consultants and university faculty. The workshops were announced in the Federal Register on September 1, 1977

An opinion survey on the image of incidents or accidents at a final disposal site for high-level radioactive waste

International Nuclear Information System (INIS)

Tanigaki, Toshihiko

2008-01-01

Previous studies show that a major psychological factor of attitudes toward final disposal sites for high-level radioactive waste (hereinafter referred to as 'disposal sites') is risk perception. On the basis of this finding, the present survey attempted to identify mental images of assumable incidents and accidents likely to occur at disposal sites. Specifically, 402 respondents in the Kansai Area were asked to describe their mental image of what kind/level of incident or accident could possibly occur at a Disposal Site by what cause and what size of damage was expectable from such incident/accident. The results showed that following: regarding assumable incidents/accidents (1) people are most afraid of a large-scale natural disaster including a major earthquake beyond an assumed level of intensity, that they feel would probably generate the heaviest damage, (2) people assume that no major accident leading to serious damage is likely to occur in the early days after the launch of operation, (3) people have an impression that the longer the passage of time, the higher the probability of incident/accident occurrence becomes, regardless of the size of resulting damage. Those who strongly feel that Disposal Sites are dangerous are, when compared to others who do not have such a strong impression, apt to overestimate the size of assumable damage regardless of the cause of damage and also to overestimate the growth rate of the probability of incident/accident occurrence over the course of time. (author)

Peculiarities of the High-Level Concrete-Encased Radwaste Repository Disposition at the Radwaste Disposal Site of the Russian Research Center 'Kurchatov Institute'

International Nuclear Information System (INIS)

Volkov, V.G.; Ponomarev-Stepnoi, N.N.; Gorodetsky, G.G.; Zverkov, Yu.A.; Ivanov, O.P.; Lemus, A.V.; Semenov, S.G.; Stepanov, V.E.; Chesnokov, A.V.; Shisha, A.D.

2006-01-01

The paper presents peculiarities of organization and performance of activities on disposition of the old repository that contained high-level waste and located at the radwaste disposal site of the Russian Research Center 'Kurchatov Institute' in Moscow. The repository was constructed in the late 1950's. A large number of cases with high-level waste were placed in the repository along with low- and intermediate-level waste. When the repository was filled in 1973, the entire radwaste mass was encased in concrete matrix which caused difficulties with the radwaste extraction and made the work on the repository disposition highly hazardous in terms of radiation conditions. Based on results of the preliminary radiation survey of the repository, technologies and equipment to be used in disposition works were selected, and a decision on construction of external radiation shielding around the repository to maintain normal radiation conditions during these works was made. Specific features of the selected radiation shielding design constructed around the repository and of a technology used for the radwaste extraction from the repository are provided. According to the technology, conventional construction machines equipped with a hydraulic hammer or a clamshell were used for destruction of the concrete-encased radwaste mass and extraction of low-level waste. Intermediate- and high-level waste was extracted by remotely controlled robots operating inside the radiation shielding structure. Video cameras and a gamma imager were used for detection of high-level waste or fragments of such radwaste in the mass concrete being destroyed and for guiding remotely controlled robots. Peculiarities of rapid control of changes in radiation conditions in the working areas are presented. This control was performed using a gamma locator with on-line transmission of its data to a PC for their processing. With disposition of this not easily accessible repository, the stage of remediation of old

Use of an analog site near Raymond, California, to develop equipment and methods for characterizing a potential high-level, nuclear waste repository site at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Umari, A.M.J.; Geldon, A.; Patterson, G.; Gemmell, J.; Earle, J.; Darnell, J.

1994-01-01

Yucca Mountain, Nevada, currently is being investigated by the U.S. Geological Survey as a potential site for a high-level nuclear waste repository. Planned hydraulic-stress and tracer tests in fractured, tuffaceous rocks below the water table at Yucca Mountain will require work at depths in excess of 1,300 feet. To facilitate prototype testing of equipment and methods to be used in aquifer tests at Yucca Mountain, an analog site was selected in the foothills of the Sierra Nevada near Raymond, California. Two of nine 250- to 300-feet deep wells drilled into fractured, granitic rocks at the Raymond site have been instrumented with packers, pressure transducers, and other equipment that will be used at Yucca Mountain. Aquifer tests conducted at the Raymond site to date have demonstrated a need to modify some of the equipment and methods conceived for use at Yucca Mountain

Attitudes and opposition in siting a high level nuclear waste repository

International Nuclear Information System (INIS)

Sjoeberg, L.; Viklund, M.; Truedsson, J.

1998-09-01

In Sweden, the Swedish Nuclear Fuel and Waste Management Company (SKB) handles all issues concerning nuclear waste, including the siting process, in which the final outcome is intended to be a repository for high level nuclear waste placed deep down in bedrock. The main objective of the siting process is to find a host community fulfilling two important conditions: the safety demands have been met and agreements with the municipality can be accomplished. Only in such municipalities, so-called feasibility studies will be conducted. After conducting general studies in the whole country, SKB, in October 1992, sent letters with information about the intended feasibility studies to all Swedish municipalities. As a result, feasibility studies are or have been considered - and in some cases also been conducted - in eleven Swedish municipalities up until 1998. These are the municipalities where the attitudes and opposition towards a feasibility study, and possibly a final repository, are studied. The discussion can be divided into three main parts: Management of the siting process; Inherent 'chaotic' processes and/or factors and risk perception. It is argued that two important problems could have been avoided at least partly: The citizens in many municipalities were uncertain of the relationship between a feasibility study and a final repository, and in many municipalities the citizens were afraid that the Government could overrule the municipal veto. Because of these fears, a common argument among the opponents of a feasibility study was: 'to be sure of not receiving a final repository, we say no to a feasibility study'. Some inherent factors, more or less prevalent in the municipalities as well as in society in general, may also partly explain the outcome of the siting process. The municipalities in which the debate has been heated, and where public support has been more difficult to reach, share some common characteristics. Esp. in the municipalities in the north of

Attitudes and opposition in siting a high level nuclear waste repository

Energy Technology Data Exchange (ETDEWEB)

Sjoeberg, L.; Viklund, M.; Truedsson, J

1998-09-01

In Sweden, the Swedish Nuclear Fuel and Waste Management Company (SKB) handles all issues concerning nuclear waste, including the siting process, in which the final outcome is intended to be a repository for high level nuclear waste placed deep down in bedrock. The main objective of the siting process is to find a host community fulfilling two important conditions: the safety demands have been met and agreements with the municipality can be accomplished. Only in such municipalities, so-called feasibility studies will be conducted. After conducting general studies in the whole country, SKB, in October 1992, sent letters with information about the intended feasibility studies to all Swedish municipalities. As a result, feasibility studies are or have been considered - and in some cases also been conducted - in eleven Swedish municipalities up until 1998. These are the municipalities where the attitudes and opposition towards a feasibility study, and possibly a final repository, are studied. The discussion can be divided into three main parts: Management of the siting process; Inherent `chaotic` processes and/or factors and risk perception. It is argued that two important problems could have been avoided at least partly: The citizens in many municipalities were uncertain of the relationship between a feasibility study and a final repository, and in many municipalities the citizens were afraid that the Government could overrule the municipal veto. Because of these fears, a common argument among the opponents of a feasibility study was: `to be sure of not receiving a final repository, we say no to a feasibility study`. Some inherent factors, more or less prevalent in the municipalities as well as in society in general, may also partly explain the outcome of the siting process. The municipalities in which the debate has been heated, and where public support has been more difficult to reach, share some common characteristics. Esp. in the municipalities in the north of

The siting record: An account of the programs of federal agencies and events that have led to the selection of a potential site for a geologic respository for high-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Lomenick, T.F.

1996-03-01

This record of siting a geologic repository for high-level radioactive wastes (HLW) and spent fuel describes the many investigations that culminated on December 22, 1987 in the designation of Yucca Mountain (YM), as the site to undergo detailed geologic characterization. It recounts the important issues and events that have been instrumental in shaping the course of siting over the last three and one half decades. In this long task, which was initiated in 1954, more than 60 regions, areas, or sites involving nine different rock types have been investigated. This effort became sharply focused in 1983 with the identification of nine potentially suitable sites for the first repository. From these nine sites, five were subsequently nominated by the U.S. Department of Energy (DOE) as suitable for characterization and then, in 1986, as required by the Nuclear Waste Policy Act of 1982 (NWPA), three of these five were recommended to the President as candidates for site characterization. President Reagan approved the recommendation on May 28, 1986. DOE was preparing site characterization plans for the three candidate sites, namely Deaf Smith County, Texas; Hanford Site, Washington; and YM. As a consequence of the 1987 Amendment to the NWPA, only the latter was authorized to undergo detailed characterization. A final Site Characterization Plan for Yucca Mountain was published in 1988. Prior to 1954, there was no program for the siting of disposal facilities for high-level waste (HLW). In the 1940s and 1950s, the volume of waste, which was small and which resulted entirely from military weapons and research programs, was stored as a liquid in large steel tanks buried at geographically remote government installations principally in Washington and Tennessee.

The siting record: An account of the programs of federal agencies and events that have led to the selection of a potential site for a geologic respository for high-level radioactive waste

International Nuclear Information System (INIS)

Lomenick, T.F.

1996-03-01

This record of siting a geologic repository for high-level radioactive wastes (HLW) and spent fuel describes the many investigations that culminated on December 22, 1987 in the designation of Yucca Mountain (YM), as the site to undergo detailed geologic characterization. It recounts the important issues and events that have been instrumental in shaping the course of siting over the last three and one half decades. In this long task, which was initiated in 1954, more than 60 regions, areas, or sites involving nine different rock types have been investigated. This effort became sharply focused in 1983 with the identification of nine potentially suitable sites for the first repository. From these nine sites, five were subsequently nominated by the U.S. Department of Energy (DOE) as suitable for characterization and then, in 1986, as required by the Nuclear Waste Policy Act of 1982 (NWPA), three of these five were recommended to the President as candidates for site characterization. President Reagan approved the recommendation on May 28, 1986. DOE was preparing site characterization plans for the three candidate sites, namely Deaf Smith County, Texas; Hanford Site, Washington; and YM. As a consequence of the 1987 Amendment to the NWPA, only the latter was authorized to undergo detailed characterization. A final Site Characterization Plan for Yucca Mountain was published in 1988. Prior to 1954, there was no program for the siting of disposal facilities for high-level waste (HLW). In the 1940s and 1950s, the volume of waste, which was small and which resulted entirely from military weapons and research programs, was stored as a liquid in large steel tanks buried at geographically remote government installations principally in Washington and Tennessee

Siting process for disposal site of low level radiactive waste in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sriyotha, P.; Thiengtrongjit, S.; Sriyotha, K.

1992-01-01

The radioactive waste in Thailand is composed of low level waste from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. In addition, the high activity of sealed radiation sources i.e. Cs-137 Co-60 and Ra-226 are also accumulated. Since the volume of treated waste has been gradually increased, the general needs for a repository become apparent. The near surface disposal method has been chosen for this aspect. The feasibility study on the underground disposal site has been done since 1982. The site selection criteria have been established, consisting of the rejection criteria, the technical performance criteria and the economic criteria. About 50 locations have been picked for consideration and 5 candidate sites have been selected and subsequent investigated. After thoroughly investigation, a definite location in Ratchburi Province, about 180 kilometers southwest of Bangkok, has been selected as the most suitable place for the near surface disposal of radioactive waste in Thailand

Plans for managing high level waste at the Savannah River Site

International Nuclear Information System (INIS)

Sheikh, N.A.; Salaymeh, S.R.

1994-01-01

Design and evaluation guidelines for DOE facilities subject to earthquake, wind/tornado, and flood have been developed. This paper describes the philosophy and procedures for the design of facilities managing high level waste, with respect to ground shaking and tornado generated missiles. The intent is to meet the probabilistic based performance goals for each category of structure, system, and component of such facilities. Described performance goals can be achieved by specifying hazard probabilities of exceedance. The seismic and tornado effects can be controlled through the level of conservatism already introduced in the design of such facilities. This will eliminate any level of risk to personnel and environment in the event of high seismic activity or high wind/tornado event. When dealing with complex processes, facilities will have to be divided into various segments and assigned different categories depending on their mission, value, or toxic/radioactive material content

A construction of Japanese consensus-formation model for the selection of last disposal site of high-level radioactive wastes

International Nuclear Information System (INIS)

Oki, Naotaka; Saigusa, Shin; Yonehara, Hidenori

2010-01-01

A group with Shizuoka University as the center one is promoting the investigation of the subject 'A construction of Japanese consensus - formation model for the selection of last disposal site of high-level radioactive wastes' adopted in 'Atomic Energy Fundamental Strategic Initiative' at the 20th fiscal year of Heisei, the Ministry of Education, Culture, Sports, Science and Technology. The result of this investigation is described here. (M.H.)

Siting simulation for low-level waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Rope, R.C.

1985-01-01

The Mock Site Licensing Demonstration Project has developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This paper describes the development, content, and usefulness of the siting simulation. The simulation can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions; in the first, participants negotiate the selection of siting criteria, and in the second, a preferred disposal site is chosen from three candidate sites. The project has sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation has been conducted for persons concerned with LLW management issues. It is concluded that the simulation can be valuable as a tool for disseminating information about LLW management; a vehicle that can foster communication; and a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

National survey of crystalline rocks and recommendations of regions to be explored for high-level radioactive waste repository sites

International Nuclear Information System (INIS)

Smedes, H.W.

1983-04-01

A reconnaissance of the geological literature on large regions of exposed crystalline rocks in the United States provides the basis for evaluating if any of those regions warrant further exploration toward identifying potential sites for development of a high-level radioactive waste repository. The reconnaissance does not serve as a detailed evaluation of regions or of any smaller subunits within the regions. Site performance criteria were selected and applied insofar as a national data base exists, and guidelines were adopted that relate the data to those criteria. The criteria include consideration of size, vertical movements, faulting, earthquakes, seismically induced ground motion, Quaternary volcanic rocks, mineral deposits, high-temperature convective ground-water systems, hydraulic gradients, and erosion. Brief summaries of each major region of exposed crystalline rock, and national maps of relevant data provided the means for applying the guidelines and for recommending regions for further study. It is concluded that there is a reasonable likelihood that geologically suitable repository sites exist in each of the major regions of crystalline rocks. The recommendation is made that further studies first be conducted of the Lake Superior, Northern Appalachian and Adirondack, and the Southern Appalachian Regions. It is believed that those regions could be explored more effectively and suitable sites probably could be found, characterized, verified, and licensed more readily there than in the other regions

National survey of crystalline rocks and recommendations of regions to be explored for high-level radioactive waste repository sites

Energy Technology Data Exchange (ETDEWEB)

Smedes, H.W.

1983-04-01

A reconnaissance of the geological literature on large regions of exposed crystalline rocks in the United States provides the basis for evaluating if any of those regions warrant further exploration toward identifying potential sites for development of a high-level radioactive waste repository. The reconnaissance does not serve as a detailed evaluation of regions or of any smaller subunits within the regions. Site performance criteria were selected and applied insofar as a national data base exists, and guidelines were adopted that relate the data to those criteria. The criteria include consideration of size, vertical movements, faulting, earthquakes, seismically induced ground motion, Quaternary volcanic rocks, mineral deposits, high-temperature convective ground-water systems, hydraulic gradients, and erosion. Brief summaries of each major region of exposed crystalline rock, and national maps of relevant data provided the means for applying the guidelines and for recommending regions for further study. It is concluded that there is a reasonable likelihood that geologically suitable repository sites exist in each of the major regions of crystalline rocks. The recommendation is made that further studies first be conducted of the Lake Superior, Northern Appalachian and Adirondack, and the Southern Appalachian Regions. It is believed that those regions could be explored more effectively and suitable sites probably could be found, characterized, verified, and licensed more readily there than in the other regions.

The Savannah River Site Replacement High Level Radioactive Waste Evaporator Project

International Nuclear Information System (INIS)

Presgrove, S.B.

1992-01-01

The Replacement High Level Waste Evaporator Project was conceived in 1985 to reduce the volume of the high level radioactive waste Process of the high level waste has been accomplished up to this time using Bent Tube type evaporators and therefore, that type evaporator was selected for this project. The Title I Design of the project was 70% completed in late 1990. The Department of Energy at that time hired an independent consulting firm to perform a complete review of the project. The DOE placed a STOP ORDER on purchasing the evaporator in January 1991. Essentially, no construction was to be done on this project until all findings and concerns dealing with the type and design of the evaporator are resolved. This report addresses two aspects of the DOE design review; (1) Comparing the Bent Tube Evaporator with the Forced Circulation Evaporator, (2) The design portion of the DOE Project Review - concentrated on the mechanical design properties of the evaporator. 1 ref

Summary Of Cold Crucible Vitrification Tests Results With Savannah River Site High Level Waste Surrogates

Energy Technology Data Exchange (ETDEWEB)

Stefanovsky, Sergey; Marra, James; Lebedev, Vladimir

2014-01-13

The cold crucible inductive melting (CCIM) technology successfully applied for vitrification of low- and intermediate-level waste (LILW) at SIA Radon, Russia, was tested to be implemented for vitrification of high-level waste (HLW) stored at Savannah River Site, USA. Mixtures of Sludge Batch 2 (SB2) and 4 (SB4) waste surrogates and borosilicate frits as slurries were vitrified in bench- (236 mm inner diameter) and full-scale (418 mm inner diameter) cold crucibles. Various process conditions were tested and major process variables were determined. Melts were poured into 10L canisters and cooled to room temperature in air or in heat-insulated boxes by a regime similar to Canister Centerline Cooling (CCC) used at DWPF. The products with waste loading from ~40 to ~65 wt.% were investigated in details. The products contained 40 to 55 wt.% waste oxides were predominantly amorphous; at higher waste loadings (WL) spinel structure phases and nepheline were present. Normalized release values for Li, B, Na, and Si determined by PCT procedure remain lower than those from EA glass at waste loadings of up to 60 wt.%.

Overview: Defense high-level waste technology program

International Nuclear Information System (INIS)

Shupe, M.W.; Turner, D.A.

1987-01-01

Defense high-level waste generated by atomic energy defense activities is stored on an interim basis at three U.S. Department of Energy (DOE) operating locations; the Savannah River Plant in South Carolina, the Hanford Site in Washington, and the Idaho National Engineering Laboratory in Idaho. Responsibility for the permanent disposal of this waste resides with DOE's Office of Defense Waste and Transportation Management. The objective of the Defense High-Level Wast Technology Program is to develop the technology for ending interim storage and achieving permanent disposal of all U.S. defense high-level waste. New and readily retrievable high-level waste are immobilized for disposal in a geologic repository. Other high-level waste will be stabilized in-place if, after completion of the National Environmental Policy Act (NEPA) process, it is determined, on a site-specific basis, that this option is safe, cost effective and environmentally sound. The immediate program focus is on implementing the waste disposal strategy selected in compliance with the NEPA process at Savannah River, while continuing progress toward development of final waste disposal strategies at Hanford and Idaho. This paper presents an overview of the technology development program which supports these waste management activities and an assessment of the impact that recent and anticipated legal and institutional developments are expected to have on the program

DOE management of high-level waste at the Hanford Site

International Nuclear Information System (INIS)

1993-01-01

Approximately 60 million gallons of high-level radioactive waste--caustic liquids, slurries, saltcakes, and sludges--are stored in underground tanks at the Department of Energy's Hanford Site. At least one-third of the tanks are known to have leaked waste into the enviroranent, and there are many unresolved tank safety issues. In order to resolve the environmental and safety concerns, the Department plans to retrieve the waste, immobilize it, and dispose of it in a permanent geologic repository. Processing all of the tank waste in this manner could cost $40 billion, including $1.2 billion to construct the Hanford Waste Vitrification Plant. The purpose of our audit was to examine the reasons for cost estimate increases and schedule delays on the Hanford vitrification program. We also wanted to report on outstanding technical, safety, and environmental issues that could make the project even more costly and further delay its completion. We found that the Department managed the Hanford remediation system as a number of separate projects not fully integrated into one major system acquisition. Total costs have, therefore, been obscured, and the Department has not yet clearly defined system requirements or developed overall cost and schedule baselines. This lack of visibility could result in additional cost growth and schedule delays. We also noted a vast array of technical uncertainties, including tank safety and inadequate information about the makeup of tank waste, that could significantly affect the program's cost and ultimate success. To increase visibility of program cost and schedule, we are recommending that all separate projects relating to tank waste be included in a single major system acquisition, and that the Department complete its ongoing baselining effort to the extent practical before making major funding commitments. Management concurred with our finding and recommendations

Development of technical information database for high level waste disposal

International Nuclear Information System (INIS)

Kudo, Koji; Takada, Susumu; Kawanishi, Motoi

2005-01-01

A concept design of the high level waste disposal information database and the disposal technologies information database are explained. The high level waste disposal information database contains information on technologies, waste, management and rules, R and D, each step of disposal site selection, characteristics of sites, demonstration of disposal technology, design of disposal site, application for disposal permit, construction of disposal site, operation and closing. Construction of the disposal technologies information system and the geological disposal technologies information system is described. The screen image of the geological disposal technologies information system is shown. User is able to search the full text retrieval and attribute retrieval in the image. (S.Y. )

Low-Level Radioactive Waste siting simulation information package

International Nuclear Information System (INIS)

1985-12-01

The Department of Energy's National Low-Level Radioactive Waste Management Program has developed a simulation exercise designed to facilitate the process of siting and licensing disposal facilities for low-level radioactive waste. The siting simulation can be conducted at a workshop or conference, can involve 14-70 participants (or more), and requires approximately eight hours to complete. The exercise is available for use by states, regional compacts, or other organizations for use as part of the planning process for low-level waste disposal facilities. This information package describes the development, content, and use of the Low-Level Radioactive Waste Siting Simulation. Information is provided on how to organize a workshop for conducting the simulation. 1 ref., 1 fig

Climax Granite, Nevada Test Site, as a host for a rock mechanics test facility related to the geologic disposal of high level nuclear wastes

International Nuclear Information System (INIS)

Heuze, F.E.

1981-02-01

This document discusses the potential of the Climax pluton, at the Nevada Test Site, as the host for a granite mechanics test facility related to the geologic disposal of high-level nuclear waste. The Climax granitic pluton has been the site of three nuclear weapons effects tests: Hard Hat, Tiny Tot, and Piledriver. Geologic exploration and mapping of the granite body were performed at the occasion of these tests. Currently, it is the site Spent Fuel Test (SFT-C) conducted in the vicinity of and at the same depth as that of the Piledriver drifts. Significant exploration, mapping, and rock mechanics work have been performed and continue at this Piledriver level - the 1400 (ft) level - in the context of SFT-C. Based on our technical discussions, and on the review of the significant geological and rock mechanics work already achieved in the Climax pluton, based also on the ongoing work and the existing access and support, it is concluded that the Climax site offers great opportunities for a rock mechanics test facility. It is not claimed, however, that Climax is the only possible site or the best possible site, since no case has been made for another granite test facility in the United States. 12 figures, 3 tables

Site selection handbook: Workshop on site selection for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

1987-10-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires the Department of Energy (DOE) to provide technical assistance to ''...those compact regions, host States and nonmember States determined by the Secretary to require assistance.'' Technical assistance has been defined to include, but not be limited to, ''technical guidelines for site selection.'' This site selection workshop was developed to assist States and Compacts in developing new low-level radioactive waste (LLW) disposal sites in accordance with the requirements of the LLRWPAA. The workshop comprises a series of lectures, discussion topics, and exercises, supported by this Site Selection Workshop Handbook, designed to examine various aspects of a comprehensive site selection program. It is not an exhaustive treatment of all aspects of site selection, nor is it prescriptive. The workshop focuses on the major elements of site selection and the tools that can be used to implement the site selection program

Disposal of high level and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Flowers, R.H.

1991-01-01

The waste products from the nuclear industry are relatively small in volume. Apart from a few minor gaseous and liquid waste streams, containing readily dispersible elements of low radiotoxicity, all these products are processed into stable solid packages for disposal in underground repositories. Because the volumes are small, and because radioactive wastes are latecomers on the industrial scene, a whole new industry with a world-wide technological infrastructure has grown up alongside the nuclear power industry to carry out the waste processing and disposal to very high standards. Some of the technical approaches used, and the Regulatory controls which have been developed, will undoubtedly find application in the future to the management of non-radioactive toxic wastes. The repository site outlined would contain even high-level radioactive wastes and spent fuels being contained without significant radiation dose rates to the public. Water pathway dose rates are likely to be lowest for vitrified high-level wastes with spent PWR fuel and intermediate level wastes being somewhat higher. (author)

Managing the process for storage and disposal of immobilized high- and low-level tank waste at the Hanford Site

International Nuclear Information System (INIS)

Murkowski, R.J.

1998-01-01

Lockheed Martin Hanford Corporation (LMHC) is one of six subcontractors under Fluor Daniel Hanford, Inc., the Management and Integration contractor for the Project Hanford Management Contract working for the US Department of Energy. One of LMHC's responsibilities is to prepare storage and disposal facilities to receive immobilized high and low-level tank waste by June of 2002. The immobilized materials are to be produced by one or more vendors working under a privatization contract. The immobilized low-activity waste is to be permanently disposed of at the Hanford Site while the immobilized high-level waste is to be stored at the Hanford Site while awaiting shipment to the offsite repository. Figure 1 is an overview of the entire cleanup mission with the disposal portion of the mission. Figure 2 is a representation of major activities required to complete the storage and disposal mission. The challenge for the LNIHC team is to understand and plan for accepting materials that are described in the Request for Proposal. Private companies will submit bids based on the Request for Proposal and other Department of Energy requirements. LMHC, however, must maintain sufficient flexibility to accept modifications that may occur during the privatization bid/award process that is expected to be completed by May 1998. Fundamental to this planning is to minimize the risks of stand-by costs if storage and disposal facilities are not available to receive the immobilized waste. LMHC has followed a rigorous process for the identification of the functions and requirements of the storage/disposal facilities. A set of alternatives to meet these functions and requirements were identified and evaluated. The alternatives selected were (1) to modify four vaults for disposal of immobilized low-activity waste, and (2) to retrofit a portion of the Canister Storage Building for storage of immobilized high-level waste

Social acceptance process model for ensuring the high-level radioactive waste disposal site

International Nuclear Information System (INIS)

Wada, Ryutaro; Tanaka, Satoru; Nagasaki, Shinya

2009-01-01

Generally speaking, a vast, advanced and unfamiliar science and technology are unacceptable to the public for fear of their unknown nature. Here, the social acceptance process model was examined on the basis of the analysis of the cause phenomenon and numerical grounds, by referring to the problems on the application of literature documentation for location examination of a high-level radioactive waste disposal site in Toyo town in Kochi Pref. in April 2007. In analyzing the Toyo town case, we have found a possibility that the majority of local residents knew very little about the object opposed by the fringe route processing. To ensure a healthy decision making by the public, it is vital to convey fundamental information using sufficient wide-area PR media before the issue becomes actual. After the issue becomes actual, dialog with residents through a careful technology assessment is indispensable. The authors focus attention on the decision-making process of human beings from the social and psychological viewpoints, and point out that it is desirable for promoting social acceptance by adopting two approaches: a direct approach aiming at better intelligibility for the different resident layers and a deductive approach in technological essence. (author)

The performance assessment impacts of disposal of high-moisture, low-level radioactive waste at the Nevada Test Site

International Nuclear Information System (INIS)

Crowe, B.M.; Hansen, W.; Hechnova, A.; Voss, C.; Waters, R.; Sully, M.; Levitt, D.

1999-01-01

A panel of independent scientists was convened by the Department of Energy to assess the performance impacts of disposal of low-level radioactive waste from the Fernald Environmental Management Project. This waste stream was involved in a transportation incident in December 1997. A resulting outgrowth of investigations of the transportation incident was the recognition that the waste was transported and disposed in stress-fractured metal boxes and some of the waste contained excess moisture (high volumetric water contents). The panel was charged with determining whether disposal of this waste in the Area 5 radioactive waste management site on the Nevada Test Site has impacted the conclusions of the completed performance assessment. Three questions were developed by the panel to assess performance impacts: (1) the performance impacts of reduced container integrity, (2) the impact of reduced container integrity on subsidence of waste in the disposal pits and (3) the performance impacts of excess moisture. No performance or subsidence impacts were noted from disposal of the Fernald waste. The impacts of excess moisture were assessed through simulation modeling of the movement of moisture in the vadose zone assuming high water contents (wet waste) for different percentages of the waste inventory. No performance impacts were noted for either the base-case scenario (ambient conditions) or a scenario involving subsidence and flooding of the waste cells. The absence of performance impacts results form the extreme conservatism used in the Area 5-performance assessment and the robust nature of the disposal site

High-Level Waste System Process Interface Description

International Nuclear Information System (INIS)

D'Entremont, P.D.

1999-01-01

The High-Level Waste System is a set of six different processes interconnected by pipelines. These processes function as one large treatment plant that receives, stores, and treats high-level wastes from various generators at SRS and converts them into forms suitable for final disposal. The three major forms are borosilicate glass, which will be eventually disposed of in a Federal Repository, Saltstone to be buried on site, and treated water effluent that is released to the environment

Siting of a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Alvarado, R.A.

1983-01-01

The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

Mineralogy and clinoptilolite K/Ar results from Yucca Mountain, Nevada, USA: A potential high-level radioactive waste repository site

International Nuclear Information System (INIS)

WoldeGabriel, G.; Broxton, D.E.; Bish, D.L.; Chipera, S.J.

1993-11-01

The Yucca Mountain Site Characterization Project is investigating Yucca Mountain, Nevada, as a potential site for a high-level nuclear waste repository. An important aspect of this evaluation is to understand the geologic history of the site including the diagenetic processes that are largely responsible for the present-day chemical and physical properties of the altered tuffs. This study evaluates the use of K/Ar geochronology in determining the alteration history of the zeolitized portions of Miocene tuffs at Yucca Mountain. Clinoptilolite is not generally regarded as suitable for dating because of its open structure and large ion-exchange capacity. However, it is the most abundant zeolite at Yucca Mountain and was selected for this study to assess the feasibility of dating the zeolitization process and/or subsequent processes that may have affected the zeolites. In this study we examine the ability of this mineral to retain all or part of its K and radiogenic Ar during diagenesis and evaluate the usefulness of the clinoptilolite K/Ar dates for determining the history of alteration

Study on the methodology of hydrogeological character in preselected site for high-level waste repository in Beishan area, Gansu province

International Nuclear Information System (INIS)

Guo Yonghai; Liu Shufen; Su Rui; Yang Tianxiao

2003-01-01

The results of regional hydrogeological investigations conducted during 1996-2000 were summarized. The study was started with the surface hydrogeological, hydrogeochemical, and groundwater isotopic and humic acid investigations. The key-points are focused on the characteristics of water-bearing formation, hydrogeochemistry, groundwater isotopes as well as humic acid. On the bases of a large quantity of hydrogeological data, the hydrogeological conditions of each groundwater unit, groundwater circulation characteristics, groundwater hydrodynamics and hydrgeochemistry are described. In addition, the modeling about groundwater flow state, groundwater chemical balance, interaction among water-rock-nuclear waste is carried out, then the suitability of the Beishan site for the high-level radioactive waste disposal is evaluated. The report comprehensively and deeply shows the hydrogeological characteristics of weak water bearing, low permeability and slow moving as well as the hydrogeochemical features of mild alkalinity and high mineralization in Beishan area. The results will provide an important basis for the evaluation of the site. (authors)

Experiences from risk communication in the siting of a geological repository for high level waste in Sweden

Energy Technology Data Exchange (ETDEWEB)

Thegerstroem, C.; Engstroem, S. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

1999-12-01

SKB is planning in the year 2001 to designate two siting alternatives for further site characterisation. The work in the municipalities of Oesthammar, Nykoeping, Oskarshamn and Tierp is taking place in an atmosphere of constructive discussions. There is a growing feeling in Sweden among broad categories of the public that the nuclear waste exists and should be taken care of by our generation, without many of these people ever getting positive to the use of nuclear energy. While the NIMBY syndrome might still have a good grip on some, there has never been a more constructive debate about the nuclear waste than now, even though there still is a lot of work to do. Siting a geological repository for high level waste puts our democratic system under hard tests. The decision making process is about openness, skills in interacting with the public, respect of people's fears and concerns and at last but not the least independent, competent and visible participation by other stakeholders (politicians locally and nationally, regulatory bodies etc). Good skills in risk communication are important ingredients that might facilitate SKB's task as a developer. Far more important however, is the trust we might get from past and present record of handling the waste and from the way we work and behave in the feasibility studies in the municipalities where SKB is involved.

Experiences from risk communication in the siting of a geological repository for high level waste in Sweden

International Nuclear Information System (INIS)

Thegerstroem, C.; Engstroem, S.

1999-01-01

SKB is planning in the year 2001 to designate two siting alternatives for further site characterisation. The work in the municipalities of Oesthammar, Nykoeping, Oskarshamn and Tierp is taking place in an atmosphere of constructive discussions. There is a growing feeling in Sweden among broad categories of the public that the nuclear waste exists and should be taken care of by our generation, without many of these people ever getting positive to the use of nuclear energy. While the NIMBY syndrome might still have a good grip on some, there has never been a more constructive debate about the nuclear waste than now, even though there still is a lot of work to do. Siting a geological repository for high level waste puts our democratic system under hard tests. The decision making process is about openness, skills in interacting with the public, respect of people's fears and concerns and at last but not the least independent, competent and visible participation by other stakeholders (politicians locally and nationally, regulatory bodies etc). Good skills in risk communication are important ingredients that might facilitate SKB's task as a developer. Far more important however, is the trust we might get from past and present record of handling the waste and from the way we work and behave in the feasibility studies in the municipalities where SKB is involved

Some interactive factors affecting trench-cover integrity on low-level waste sites

International Nuclear Information System (INIS)

Hakonson, T.E.; Lane, L.J.; Steger, J.G.; DePoorter, G.L.

1982-01-01

This paper describes important mechanisms by which radionuclide can be transported from low-level waste disposal sites into biological pathways, discuss interactions of abiotic and biotic processes, and recommends environmental characteristics that should be measured to design sites that minimize this transport. Past experience at shallow land burial sites for low-level radioactive wastes suggest that occurrences of waste exposure and radionuclide transport are often related to inadequate trench cover designs. Meeting performance standards at low-level waste sites can only be achieved by recognizing that physical, chemical, and biological processes operating on and in a trench cover profile are highly interactive. Failure to do so can lead to improper design criteria and subsequent remedial action procedures that can adversely affect site stability. Based upon field experiments and computer modeling, recommendations are made on site characteristics that require measurement in order to design systems that reduce surface runoff and erosion, manage soil moisture and biota in the cover profile to maximize evapotranspiration and minimize percolation, and place bounds on the intrusion potential of plants and animals into the waste material. Major unresolved problems include developing probabilistic approaches that include climatic variability, improved knowledge of soil-water-plant-erosion relationships, development of practical vegetation establishment and maintenance procedures, prediction and quantification of site potential and plant succession, and understanding the interaction of processes occurring on and in the cover profile with deeper subsurface processes

Enhancement of high density polyethylene high integrity containers at a low level radioactive waste disposal site

International Nuclear Information System (INIS)

Sauer, R.E.; Wong, O.P.

1989-01-01

High integrity containers (HIC) made of high density polyethylene (HDPE) have been used for disposal in South Carolina since the late seventies. With the recent definitive position taken by the NRC on the suitability of these containers for disposal, alternative means of assuring the structural integrity of the containers for the long term became necessary. The authors' company has developed an utilized reinforced concrete caissons at the Hanford, Washington site as an additional barrier and structural element to assure the long term high integrity function of the current HDPE HIC's also known as Poly HIC's on the market. This paper outlines the background of the HIC's in question, the NRC positions and ruling, and presents technical bases for the applicability of appropriately designed concrete overpacks to augment the structural integrity of HIC's

Isotope method for the recognition of groundwater formation in China's preselected high level radioactive waste disposal repository site

International Nuclear Information System (INIS)

Guo Yonghai; Wang Ju; Liu Shufen; Su Rui; Lu Chuanhe

2005-01-01

Yemaquan region in Beishan area. Gansu province, is one of the preselected sites of disposal repository for high level radioactive waste (HLW) in our country. Hydrogeological condition is an important aspect for site evaluation and the groundwater formation is a key factor to reflect the hydrogeological conditions for a certain area. Isotopic method is the one of the important means to determine the groundwater formation. Through the sampling and analysis of shallow groundwater isotopes of Yemaquan region, combined with geological, hydrogeological and hydrogeochemical characteristics, the issue of groundwater formation in the study region was discussed. The main cognition is that the groundwater in the region was formed from the infiltration of modern rainfall and the strong evaporation was happened for the shallow groundwater, which indicates the circulation conditions were relatively good for the shallow groundwater. This cognition provides very important hydrogeological information and basis for the evaluation of Yemaquan preselected site. (authors)

Radiolytic bubble formation and level changes in simulated high-level waste salts and sludges -- application to Savannah River Site and Hanford Storage tanks

International Nuclear Information System (INIS)

Walker, D.D.; Crawford, C.L.; Bibler, N.E.

1993-01-01

Radiolytically-produced bubbles of trapped gas are observed in simulated high-level waste (HLW) damp salt cake exposed to Co-60 gamma radiation. As the damp salt cake is irradiated, its volume increases due to the formation of trapped gas bubbles. Based on the increase in volume, the rate of trapped gas generation varies between 0.04 and 0.2 molecules/100 eV of energy deposited in the damp salt cake. The maximum volume of trapped gas observed in experiments is in the range 21--26 vol %. After reaching these volumes, the gas bubbles begin to escape. The generated gas includes hydrogen, oxygen, and nitrous oxide. The ratio in which these components are produced depends on the composition of the waste. Nitrous oxide production increases with the amount of sodium nitrite. Gases trapped by this mechanism may account for some of the observed level changes in Savannah River Site and Hanford waste tanks

Industrial Sites Project Establishment of Final Action Levels

International Nuclear Information System (INIS)

Boehlecke, Robert F.

2006-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) oversees numerous sites on the Nevada Test Site (NTS) and other locations in the State of Nevada that have been impacted by activities related to the development and testing of nuclear devices and by other activities. NNSA/NSO is responsible for protecting members of the public, including site workers, from harmful exposure to both chemical and radiological contaminants at these sites as they remediate these sites. The Nevada Division of Environmental Protection (NDEP) is the primary state agency responsible for protection of human health and the environment with respect to chemical and radiological wastes. In 1996 the DOE, U.S. Department of Defense, and the State of Nevada entered into an agreement known as the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996). Appendix VI to the FFACO describes the strategy employed to plan, implement, and complete environmental corrective action activities at NTS and other locations in the state of Nevada. One of the categories of corrective action units (CAUs) is Industrial Sites, which consists of approximately 1,150 locations that may require some level of investigation and corrective action. To evaluate the need for the extent of corrective action at a particular site, NNSA/NSO assesses the potential impacts to receptors by comparing measurements of contaminant concentrations to risk-based (chemical) and dose-based (radionuclide) standards (action levels). Preliminary action levels (PALs) are established as part of the data quality objective (DQO) process, and are presented in one or more FFACO documents generated as part of the corrective action process. This document formally defines and clarifies the NDEP-approved process NNSA/NSO Industrial Sites Project uses to fulfill the requirements of the FFACO and state regulations. This process establishes final action levels (FALs) based on the risk

Considerations for alternative low-level radioactive disposal sites

International Nuclear Information System (INIS)

Beck, J.M.

1986-01-01

In the immediate future, there is a need for low-level radioactive disposal sites to accommodate wastes that would otherwise be placed at a later date in permanent, government sanctioned ''compact'' sites. Until these ''compact'' sites become operational, a potential, relatively low-cost alternative exists in the numerous inactive uranium processing sites that are likewise proposed for remedial action removal or stabilization operations. This paper addressed disposal from the aspects of engineering design, economics and liability of participating parties. Many uranium (and by-product) processing facilities in the western states now stand idle due to current economic conditions within the industry. Many more were previously deactivated for various reasons. All must be dealt with under the UMTRA Program Guidelines with regard to removal, reclamation or other remedial action activities. With cooperative efforts, some of these sites would appear to be suitable for disposal of small volume, low-level radioactive wastes that presently render urban properties valueless in terms of real estate and aesthetic values. Likely sites would appear to be those slated for in-place stabilization and reclamation, particularly where the urban property material has a lower level of radioactivity than the disposal site material. The resultant impacts for site stabilization and reclamation would be solely in the areas of increased material volumes (generally requiring a minimal increase in engineering design complexity) and liability. Clearly, liability will be the overriding factor in such an approach. With the complex hierarchy of regulatory agencies involved and the private sector, what appears to be a relative simple and economic approach may have extreme difficulty in achieving reality

Site-specific evaluation of safety issues for high-level waste disposal in crystalline rocks. Final report

Energy Technology Data Exchange (ETDEWEB)

Jobmann, M. (ed.) [DBE Technology GmbH, Peine (Germany)

2016-03-31

In the past, German research and development (R and D) activities regarding the disposal of radioactive waste, including spent nuclear fuel, focused mainly on domal rock salt because rock salt was the preferred host rock formation. In addition, generic R and D work regarding alternative host rocks (crystalline rocks and claystones) had been performed as well for a long time but with lower intensity. Around the year 2000, as a consequence of the moratorium on the Gorleben site, the Federal Government decided to have argillaceous rocks and crystalline rocks investigated in more detail. As Germany does not have any underground research and host rock characterization facilities, international cooperation received a high priority in the German R and D programme for high-level waste (HLW) disposal in order to increase the knowledge regarding alternative host rocks. Major cornerstones of the cooperation are joint projects and experiments conducted especially in underground research laboratories (URL) in crystalline rocks at the Grimsel Test Site (Switzerland) and the Hard Rock Laboratory (HRL) Aespoe(Sweden) and in argillaceous rocks at the URL Mont Terri (Switzerland) and Bure (France). In 2001, the topic of radioactive waste disposal was integrated into the agreement between the former Russian Ministry of Atomic Energy (Minatom, now Rosatom) and the German Ministry of Labor (BMWA), now Ministry of Economic Affairs and Energy (BMWi), on cooperation regarding R and D on the peaceful utilization of nuclear power (agreement on ''Wirtschaftlich-Technische Zusammenarbeit'' WTZ). The intention was to have a new and interesting opportunity for international R and D cooperation regarding HLW disposal in crystalline rocks and the unique possibility to perform site-specific work, to test the safety demonstration tools available, and to expand the knowledge to all aspects specific to these host rocks. Another motivation for joining this cooperation was the

Technetium Chemistry in High-Level Waste

International Nuclear Information System (INIS)

Hess, Nancy J.

2006-01-01

Tc contamination is found within the DOE complex at those sites whose mission involved extraction of plutonium from irradiated uranium fuel or isotopic enrichment of uranium. At the Hanford Site, chemical separations and extraction processes generated large amounts of high level and transuranic wastes that are currently stored in underground tanks. The waste from these extraction processes is currently stored in underground High Level Waste (HLW) tanks. However, the chemistry of the HLW in any given tank is greatly complicated by repeated efforts to reduce volume and recover isotopes. These processes ultimately resulted in mixing of waste streams from different processes. As a result, the chemistry and the fate of Tc in HLW tanks are not well understood. This lack of understanding has been made evident in the failed efforts to leach Tc from sludge and to remove Tc from supernatants prior to immobilization. Although recent interest in Tc chemistry has shifted from pretreatment chemistry to waste residuals, both needs are served by a fundamental understanding of Tc chemistry

Drumlins - Potential low-level radioactive waste sites

International Nuclear Information System (INIS)

Maxwell, H.W.

1988-01-01

A drumlin is a subglacially produced low, streamlined elongate oval hill, mound or ridge with its long axis parallel to the direction of ice flow. It may be composed entirely of till, particularly basal till, or it may have a bedrock core and a relatively thin till outer layer. Most drumlins are less than a half mile long, 400 to 600 feet wide at their base and less than 100 feet high. There are some that are more than a mile long, 1500 to 2000 feet wide and more than 200 feet high. A drumlin has many characteristics which are advantageous to the siting of a low-level radioactive disposal facility. Most drumlins in New York State are composed of basal till which, because of its mode of deposition, may be as dense and impervious as concrete. This composition makes several disposal concepts feasible. Preliminary data and conceptualization indicates a subsurface mined repository paralleling the long axis of a drumlin would meet physical, environmental and long range public safety requirements. A drumlin site could answer many intervenor concerns such as longevity, esthetics, monitoring ability, and inadvertent entry. This paper will describe the structure, composition and engineering significant of the components of a drumlin and will present some alternative concepts for LLRW disposal using a drumlin as a host

Multi-scale habitat selection in highly territorial bird species: Exploring the contribution of nest, territory and landscape levels to site choice in breeding rallids (Aves: Rallidae)

Science.gov (United States)

Jedlikowski, Jan; Chibowski, Piotr; Karasek, Tomasz; Brambilla, Mattia

2016-05-01

Habitat selection often involves choices made at different spatial scales, but the underlying mechanisms are still poorly understood, and studies that investigate the relative importance of individual scales are rare. We investigated the effect of three spatial scales (landscape, territory, nest-site) on the occurrence pattern of little crake Zapornia parva and water rail Rallus aquaticus at 74 ponds in the Masurian Lakeland, Poland. Habitat structure, food abundance and water chemical parameters were measured at nests and random points within landscape plots (from 300-m to 50-m radius), territory (14-m) and nest-site plots (3-m). Regression analyses suggested that the most relevant scale was territory level, followed by landscape, and finally by nest-site for both species. Variation partitioning confirmed this pattern for water rail, but also highlighted the importance of nest-site (the level explaining the highest share of unique variation) for little crake. The most important variables determining the occurrence of both species were water body fragmentation (landscape), vegetation density (territory) and water depth (at territory level for little crake, and at nest-site level for water rail). Finally, for both species multi-scale models including factors from different levels were more parsimonious than single-scale ones, i.e. habitat selection was likely a multi-scale process. The importance of particular spatial scales seemed more related to life-history traits than to the extent of the scales considered. In the case of our study species, the territory level was highly important likely because both rallids have to obtain all the resources they need (nest site, food and mates) in relatively small areas, the multi-purpose territories they defend.

A data base for low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Daum, M.L.; Moskowitz, P.D.

1989-07-01

A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs

Using geologic conditions and multiattribute decision analysis to determine the relative favorability of selected areas for siting a high-level radioactive waste repository

International Nuclear Information System (INIS)

Harrison, W.; Edgar, D.E.; Baker, C.H.

1988-05-01

A method is presented for determining the relative favorability of geologically complex areas for isolating high-level radioactive wastes. In applying the method to the northeastern region of the United States, seismicity and tectonic activity were the screening criteria used to divide the region into three areas of increasing seismotectonic risk. Criteria were then used to subdivide the area of lowest seismotectonic risk into six geologically distinct subareas including characteristics, surface-water and groundwater hydrology, potential human intrusion, site geometry, surface characteristics, and tectonic environment. Decision analysis was then used to identify the subareas most favorable from a geologic standpoint for further investigation, with a view to selecting a site for a repository. Three subareas (parts of northeastern Vermont, northern New Hampshire, and western Maine) were found to be the most favorable, using this method and existing data. However, because this study assessed relative geologic favorability, no conclusions should be drawn concerning the absolute suitability of individual subareas for high-level radioactive waste isolation. 34 refs., 7 figs., 20 tabs

Geographic factors related to site suitability of low-level waste disposal

Science.gov (United States)

Zittel, H. E.

Factors related to the site suitability of low level waste disposal sites are discussed including those which might be considered environmental and those dealing with site criteria. Possible population criteria, alternative site selection, transportation criteria, and community involvement are considered. All these factors are based on the premise that the technology exists to carry out low level waste disposal in a manner such that public health and safety can be insured. It is concluded that problems encountered in siting low level waste facilities are largely societal and political in nature.

SPECIFIC SITES OF BONE EXPANSION DEPEND ON THE LEVEL OF VOLLEYBALL PRACTICE IN PREPUBESCENT BOYS

Directory of Open Access Journals (Sweden)

Hamada Chaari

2013-06-01

Full Text Available The purpose of this study was to investigate the effect of 18 months of high and low levels of volleyball practice on bone acquisition. 130 prepubescent boys (mean age 11.4 ± 0.7 were divided into a high-level training group (HLG, low-level training group (LLG, and controls. Bone mineral content (BMC and bone area at the whole body, lumbar spine L2-L4, femoral neck of the dominant leg, and right and left radius were measured using dual-photon X-ray absorptiometry. Enhanced BMC resulted from high-training volleyball activity in all measured sites except the third left and right distal radius, which is not modified by low-level training in prepubescent players but it was accompanied by a bone area expansion in radius and weight-bearing sites for the HLG, and in legs, whole right and left radius for the LLG. Significant improvement of skeletal tissues is associated with the intensity and duration of volleyball training.

High-Level Waste Tank Lay-Up Assessment - Year-End Progress Report

International Nuclear Information System (INIS)

Elmore, Monte R.; Henderson, Colin

2002-01-01

This report documents the preliminary needs assessment of high-level waste (HLW) tank lay-up requirements and considerations for the Hanford Site, Idaho National Engineering and Environmental Lab (INEEL), Savannah River Site (SRS) and Oak Ridge Reservation (ORR). This assessment includes the development of a high-level requirements and considerations list that evolved from work done for the West Valley Demonstration Project (WVDP) earlier in fiscal year (FY) 2001, and is based on individual site conditions and tank retrieval/tank closure schedules. Because schedules are continually subject to change, this assessment is considered preliminary and needs review and validation by the individual sites. The lay-up decision methodology developed for WVDP was based on standard systems engineering principles, and provided a structured framework for producing an effective, technically-defensible lay-up strategy

Low-level siting, Edgemont, South Dakota

International Nuclear Information System (INIS)

Andrews, L.J.

1984-01-01

The siting of a low-level radwaste disposal facility and characterization activities to date in Edgemont, South Dakota are discussed. By using past and present experience the author sets forth the major problem, the social and political considerations, community acceptance, media and public officials' attitudes, criteria for acceptance and significance of countywide vote in support of facility. Characterization activities, site selection planning and criteria, above-grade and below-grade technical evaluation, NRC interface, 10 CFR Part 61 related to technical work, as well as community acceptance and license application are covered. The paper deals with specific problems, solutions and ongoing activities

Application of ArcGIS to the geoscience data management of the preselected site in Beishan high-level radioactive waste repository

International Nuclear Information System (INIS)

Zhong Xia; Wang Ju; Huang Shutao; Wang Shuhong; Gao Min

2010-01-01

The site selection of a high-level radioactive waste (HLW) repository is long-term and complicated system project. In the study, the information and data are not only related to different research fields, but also of large volume, diverse types and dispersed storage. In order to wholly manage and effectively make use of the information, the authors study how to set up the platform of the geoscience database to store, manage and apply the diverse type, based on ArcGIS, and present the data management and sharing solution. (authors)

Geographic factors related to site suitability of low-level waste disposal

International Nuclear Information System (INIS)

Zittel, H.E.

1981-01-01

A number of factors related to the site suitability of low-level waste disposal sites are discussed. The factors are a combination of those which might be considered environmental and those dealing with site criteria. Among the factors covered are: possible population criteria, alternative site selection, transportation criteria and community involvement considerations. All these factors are discussed in a manner based on the premise that the technology exists to carry out low-level waste disposal in a manner such that public health and safety can be insured. The conclusion of the discussion is that problems encountered in siting low-level waste facilities will be largely societal and political in nature

Final repositories for high-level radioactive waste; Endlagerung hochradioaktiver Abfaelle

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-10-15

The brochure on final repositories for high-level radioactive waste covers the following issues: What is the origin of radioactive wastes? How large are the waste amounts? What is going to happen with the wastes? What is the solution for the Waste disposal? A new site search is started. Safety requirements for the final disposal of high-level radioactive wastes. Comparison of host rocks. Who is responsible and who will pay? Final disposal of high-level radioactive wastes worldwide. Short summary: History of the search for a final repository for high-level radioactive wastes in Germany.

Study on quality assurance for high-level radioactive waste disposal project

International Nuclear Information System (INIS)

Takada, Susumu

2005-01-01

The U.S. Department of Energy (DOE) has developed comparatively detailed quality assurance requirements for the high-level radioactive waste disposal systems. Quality assurance is recognized as a key issue for confidence building and smooth implementation of the HLW program in Japan, and Japan is at an initial phase of repository development. Then the quality assurance requirements at site research and site selection, site characterization, and site suitability analysis used in the Yucca Mountain project were examined in detail and comprehensive descriptions were developed using flow charts. Additionally, the applicability to the Japan high-level radioactive waste disposal project was studied. The examination and study were performed for the following QA requirements: The requirements that have the relative importance at site research and site selection, site characterization, and site suitability analysis (such as planning and performing scientific investigations, sample control, data control, model development and use, technical report review, software control, and control of the electric management of data). The requirements that have the relative importance at the whole repository phases (such as quality assurance program, document control, and control of quality assurance records). (author)

Impact of transporting defense high-level waste to a geologic repository

International Nuclear Information System (INIS)

Joy, D.S.; Shappert, L.B.; Boyle, J.W.

1984-12-01

The Nuclear Waste Policy Act of 1982 (Public Law 97-425) provides for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel and requires the Secretary of Energy to evaluate five potential repository sites. One factor that is to be examined is transportation of radioactive materials to such a repository and whether transportation might be affected by shipments to a defense-only repository, or to one that accepts both defense and commercial waste. In response to this requirement, The Department of Energy has undertaken an evaluation of the cost and risk associated with the potential shipments. Two waste-flow scenarios are considered which are related to the total quantity of defense high-level waste which will be placed in a repository. The low-flow case is based on a total of 6700 canisters being transported from one site, while the high-flow case assumes that a total of 20,000 canisters will be transported from three sites. For the scenarios considered, the estimated shipping costs range from $105 million to $257 million depending upon the mode of transport and the repository location. The total risks associated with shipping defense high-level waste to a repository are estimated to be significantly smaller than predicted for other transportation activities. In addition, the cost of shipping defense high-level waste to a repository does not depend on whether the site is a defense-only or a commercial repository. Therefore, the transportation considerations are not a basis for the selection of one of the two disposal options

High-frequency EPR on high-spin transition-metal sites

NARCIS (Netherlands)

Mathies, Guinevere

2012-01-01

The electronic structure of transition-metal sites can be probed by electron-paramagnetic-resonance (EPR) spectroscopy. The study of high-spin transition-metal sites benefits from EPR spectroscopy at frequencies higher than the standard 9.5 GHz. However, high-frequency EPR is a developing field. In

Ozone concentrations at a selected high-elevation forest site downwind Mexico City

Science.gov (United States)

Torres-JArdon, R.

2013-05-01

Torres-Jardón, R.*, Rosas-Pérez, I., Granada-Macías, L. M., Ruiz-Suárez, L. G. Centro de Ciencias de la Atmósfera, UNAM, México D. F. México * rtorres@unam.mx For many years, the vegetation of forest species such as Abies religiosa in natural parks located in the southwest mountains of Mexico City has attracted much attention since these parks have been experiencing a severe decline of unclear etiology. The high ozone levels in the area and the observed naked eye macroscopic, histological and cytological injuries on these species, strongly suggest an important contribution of tropospheric ozone to this deterioration process. Apart of historical short monitoring campaigns for measuring ozone levels in these mountains, it is known just a little is known about the present exposure levels at which the local vegetation is exposed. A continuous ozone analyzer has been in operation since 2011 at a high-elevation forest site (Parque Nacional Miguel Hidalgo, PNMH; 3110 m above mean sea level) located downwind of Mexico City Metropolitan Area (MCMA), in order to characterize the local ozone diel amplitude and its seasonal trend, as well as the influence of MCMA on the local O3 concentrations. Hourly average ozone data in PNMH shows that in general, the diel of ozone concentrations in the forest site has a statistical significant correlation with the pattern of ozone levels observed in several monitoring sites (smog receptor sites) within the MCMA, although the high elevation O3 levels are relatively lower than those in the urban area (around 2200 m above mean sea level). It is possible that a part of the oxidants in the air masses are removed by sink deposition processes during the air mass transport across the hills. The diel amplitude of ozone concentrations is small in the cold season, increasing as the seasons advance to June. As in the city, the highest ozone concentrations occur in April or May and the lowest levels during the rainy season, which extends from

Low-level siting, Edgemont, South Dakota

International Nuclear Information System (INIS)

Andrews, L.J.

1984-01-01

The siting of a low-level radwaste disposal facility and characterization activities to date, at Edgemont, South Dakota are given. Using past and present experience setting forth the major problem as viewed by the author, the social and political considerations, community acceptance, media and public officials' attitudes, criteria for acceptance and significance of countywide vote in support of facility are presented. Characterization activities, site selection planning and criteria, above-grade and below-grade technical evaluation, NRC interface, 10 CFR Part 61 related to technical work, as well as community acceptance and license application are included. The paper deals with specific problems, solutions and ongoing activities

Framework for DOE mixed low-level waste disposal: Site fact sheets

Energy Technology Data Exchange (ETDEWEB)

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

1994-11-01

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

Evaluation of possible host rocks for China's high level radioactive waste repository and the progress in site characterization at the Beishan potential site in NW China's Gansu province

International Nuclear Information System (INIS)

Wang Ju; Jin Yuanxin; Chen Zhangru; Chen Weiming; Wang Wenguang

2000-01-01

Evaluation of possible host rocks for China's high level radioactive waste repository is summarized in this paper. The distribution and characteristics of granite, tuff, clay stone, salt and loess in China are described, while maps showing the distribution of host rocks are presented. Because of the wide distribution, large scale, good heat conductivity and suitable mechanical properties, granite is considered as the most potential host rock. Some granite bodies distributed in NW China, SW China, South China and Inner Mongolia have been selected as potential areas. Detailed site characterization at Beishan area, Gansu Province NW China is in progress

Characterization and reaction behavior of ferrocyanide simulants and Hanford Site high-level ferrocyanide waste

International Nuclear Information System (INIS)

Jeppson, D.W.; Simpson, B.C.

1994-02-01

Nonradioactive waste simulants and initial ferrocyanide tank waste samples were characterized to assess potential safety concerns associated with ferrocyanide high-level radioactive waste stored at the Hanford Site in underground single-shell tanks (SSTs). Chemical, physical, thermodynamic, and reaction properties of the waste simulants were determined and compared to properties of initial samples of actual ferrocyanide wastes presently in the tanks. The simulants were shown to not support propagating reactions when subjected to a strong ignition source. The simulant with the greatest ferrocyanide concentration was shown to not support a propagating reaction that would involve surrounding waste because of its high water content. Evaluation of dried simulants indicated a concentration limit of about 14 wt% disodium mononickel ferrocyanide, below which propagating reactions could not occur in the ambient temperature bulk tank waste. For postulated localized hot spots where dried waste is postulated to be at an initial temperature of 130 C, a concentration limit of about 13 wt% disodium mononickel ferrocyanide was determined, below which propagating reactions could not occur. Analyses of initial samples of the presently stored ferrocyanide waste indicate that the waste tank ferrocyanide concentrations are considerably lower than the limit for propagation for dry waste and that the water content is near that of the as-prepared simulants. If the initial trend continues, it will be possible to show that runaway ferrocyanide reactions are not possible under present tank conditions. The lower ferrocyanide concentrations in actual tank waste may be due to tank waste mixing and/or degradation from radiolysis and/or hydrolysis, which may have occurred over approximately 35 years of storage

Financing a new low-level radioactive waste disposal site

International Nuclear Information System (INIS)

Dressen, A.L.; Serie, P.J.; McGarvey, R.S.; Lemmon, R.A.

1982-01-01

No new commercial low-level radioactive waste disposal site has been licensed in the past decade. During the time, inflation has wreaked havoc on the costs for the labor, equipment, and buildings that will be necessary to develop and operate new sites. The regulatory environment has become much more complex with enactment of the National Environmental Policy Act (NEPA) and the recent issuance by the Nuclear Regulatory Commission (NRC) of a draft set of comprehensive regulations for land disposal of low-level waste (10 CFR Part 61). Finally, the licensing process itself has become much lengthier as both the site developers and regulators respond to the public's desire to be more involved in decisions that may affect their lives

Effects of post-disposal gas generation in a repository for spent fuel, high-level waste and long-lived intermediate level waste sited in opalinus clay

International Nuclear Information System (INIS)

Johnson, L.; Marschall, P.; Zuidema, P.; Gribi, P.

2004-07-01

This comprehensive report issued by the Swiss National Cooperative for the Disposal of Radioactive Waste NAGRA takes a look at post-disposal gas generation in a repository for spent fuel and highly radioactive wastes in Opalinus clay strata. This study provides a comprehensive treatment of the issue of gas generation in a repository for spent fuel (SF), vitrified high-level waste (HLW) and long-lived intermediate-level waste (ILW), sited in the Opalinus clay of the Zuercher Weinland in northern Switzerland. The issue of how gas generation in and transport from waste repositories may influence disposal system performance has been under study for many years, both at Nagra and internationally. The report consists of three main parts: (i) A synthesis of basic information on the host rock and on details of repository construction; (ii) A discussion on gas transport characteristics of the engineered barrier system and the geosphere; (iii) A discussion on the effects of gas on system performance, based on the available information on gas generation, gas transport properties and gas pathways provided in the previous parts of the report. Simplified model calculations based on a mass balance approach for the gas generated within the repository are presented and discussed

The socioeconomic impacts of high-level nuclear waste facility siting

International Nuclear Information System (INIS)

Murdock, S.H.; Leistritz, F.L.; Hamm, R.R.

1987-01-01

High-level nuclear waste repositories will be located in sparsely settled rural areas in the U.S. These projects will significantly effect the economic, demographic, public service, fiscal, and social (the socioeconomic) dimensions of those rural areas. This paper examines some of the potential socioeconomic impacts and the characteristics of mitigation programs necessary, if these impacts are to be addressed. Both standard impacts, those resulting from the fact that--like many other large-scale developments--repositories will involve a substantial number of new workers and residents (relative to the size of existing communities) and special impacts, those resulting from the fact that repositories store radioactive materials, are examined

Conflict resolution in low-level waste facility siting

International Nuclear Information System (INIS)

English, M.R.

1989-01-01

Siting a low-level waste facility is only one part of the low-level waste management process. But it is a crucial part, a prism that focuses many of the other issues in low-level waste management. And, as the 1990 and 1992 milestones approach, siting has a urgency that makes the use of alternative dispute resolution (ADR) techniques especially appropriate, to avoid protracted and expensive litigation and to reach creative and durable solutions. Drawing upon literature in the ADR field, this paper discusses ADR techniques as they apply to low-level waste management and the groundwork that must be laid before they can be applied. It also discusses questions that can arise concerning the terms under which negotiations are carried out. The paper then give suggestions for achieving win/win negotiations. Potential objections to negotiated agreements and potential answers to those objections are reviewed, and some requisites for negotiation are given

Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

International Nuclear Information System (INIS)

Mohamed, Yasser T.

2013-01-01

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

High-level waste management technology program plan

Energy Technology Data Exchange (ETDEWEB)

Harmon, H.D.

1995-01-01

The purpose of this plan is to document the integrated technology program plan for the Savannah River Site (SRS) High-Level Waste (HLW) Management System. The mission of the SRS HLW System is to receive and store SRS high-level wastes in a see and environmentally sound, and to convert these wastes into forms suitable for final disposal. These final disposal forms are borosilicate glass to be sent to the Federal Repository, Saltstone grout to be disposed of on site, and treated waste water to be released to the environment via a permitted outfall. Thus, the technology development activities described herein are those activities required to enable successful accomplishment of this mission. The technology program is based on specific needs of the SRS HLW System and organized following the systems engineering level 3 functions. Technology needs for each level 3 function are listed as reference, enhancements, and alternatives. Finally, FY-95 funding, deliverables, and schedules are s in Chapter IV with details on the specific tasks that are funded in FY-95 provided in Appendix A. The information in this report represents the vision of activities as defined at the beginning of the fiscal year. Depending on emergent issues, funding changes, and other factors, programs and milestones may be adjusted during the fiscal year. The FY-95 SRS HLW technology program strongly emphasizes startup support for the Defense Waste Processing Facility and In-Tank Precipitation. Closure of technical issues associated with these operations has been given highest priority. Consequently, efforts on longer term enhancements and alternatives are receiving minimal funding. However, High-Level Waste Management is committed to participation in the national Radioactive Waste Tank Remediation Technology Focus Area. 4 refs., 5 figs., 9 tabs.

High-level waste management technology program plan

International Nuclear Information System (INIS)

Harmon, H.D.

1995-01-01

The purpose of this plan is to document the integrated technology program plan for the Savannah River Site (SRS) High-Level Waste (HLW) Management System. The mission of the SRS HLW System is to receive and store SRS high-level wastes in a see and environmentally sound, and to convert these wastes into forms suitable for final disposal. These final disposal forms are borosilicate glass to be sent to the Federal Repository, Saltstone grout to be disposed of on site, and treated waste water to be released to the environment via a permitted outfall. Thus, the technology development activities described herein are those activities required to enable successful accomplishment of this mission. The technology program is based on specific needs of the SRS HLW System and organized following the systems engineering level 3 functions. Technology needs for each level 3 function are listed as reference, enhancements, and alternatives. Finally, FY-95 funding, deliverables, and schedules are s in Chapter IV with details on the specific tasks that are funded in FY-95 provided in Appendix A. The information in this report represents the vision of activities as defined at the beginning of the fiscal year. Depending on emergent issues, funding changes, and other factors, programs and milestones may be adjusted during the fiscal year. The FY-95 SRS HLW technology program strongly emphasizes startup support for the Defense Waste Processing Facility and In-Tank Precipitation. Closure of technical issues associated with these operations has been given highest priority. Consequently, efforts on longer term enhancements and alternatives are receiving minimal funding. However, High-Level Waste Management is committed to participation in the national Radioactive Waste Tank Remediation Technology Focus Area. 4 refs., 5 figs., 9 tabs

Siting a low-level waste facility

International Nuclear Information System (INIS)

English, M.R.

1988-01-01

In processes to site disposal facilities for low-level radioactive waste, volunteerism and incentives packages hold more promise for attracting host communities than they have for attracting host states. But volunteerism and incentives packages can have disadvantages as well as advantages. This paper discusses their pros and cons and summarizes the different approaches that states are using in their relationships with local governments

Direct atomic-level insight into the active sites of a high-performance PGM-free ORR catalyst

Science.gov (United States)

Chung, Hoon T.; Cullen, David A.; Higgins, Drew; Sneed, Brian T.; Holby, Edward F.; More, Karren L.; Zelenay, Piotr

2017-08-01

Platinum group metal-free (PGM-free) metal-nitrogen-carbon catalysts have emerged as a promising alternative to their costly platinum (Pt)-based counterparts in polymer electrolyte fuel cells (PEFCs) but still face some major challenges, including (i) the identification of the most relevant catalytic site for the oxygen reduction reaction (ORR) and (ii) demonstration of competitive PEFC performance under automotive-application conditions in the hydrogen (H2)-air fuel cell. Herein, we demonstrate H2-air performance gains achieved with an iron-nitrogen-carbon catalyst synthesized with two nitrogen precursors that developed hierarchical porosity. Current densities recorded in the kinetic region of cathode operation, at fuel cell voltages greater than ~0.75 V, were the same as those obtained with a Pt cathode at a loading of 0.1 milligram of Pt per centimeter squared. The proposed catalytic active site, carbon-embedded nitrogen-coordinated iron (FeN4), was directly visualized with aberration-corrected scanning transmission electron microscopy, and the contributions of these active sites associated with specific lattice-level carbon structures were explored computationally.

Hanford Site River Protection Project (RPP) High-Level Waste Storage

International Nuclear Information System (INIS)

KRISTOFZSKI, J.G.

2000-01-01

The CH2M HILL Hanford Group (CHG) conducts business to achieve the goals of the U.S. Department of Energy's (DOE) Office of River Protection at the Hanford Site. The CHG is organized to manage and perform work to safely store, retrieve, etc

High level radioactive waste management facility design criteria

International Nuclear Information System (INIS)

Sheikh, N.A.; Salaymeh, S.R.

1993-01-01

This paper discusses the engineering systems for the structural design of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). At the DWPF, high level radioactive liquids will be mixed with glass particles and heated in a melter. This molten glass will then be poured into stainless steel canisters where it will harden. This process will transform the high level waste into a more stable, manageable substance. This paper discuss the structural design requirements for this unique one of a kind facility. A special emphasis will be concentrated on the design criteria pertaining to earthquake, wind and tornado, and flooding

Nonradiological groundwater quality at low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Goode, D.J.

1986-04-01

The NRC is investigating appropriate regulatory options for disposal of low-level radioactive waste containing nonradiological hazardous constituents, as defined by EPA regulations. Standard EPA/RCRA procedures to determine hazardous organics, metals, indicator parameters, and general water quality are applied to samples from groundwater monitoring wells at two commercial low-level radioactive waste disposal sites. At the Sheffield, IL site (nonoperating), several typical organic solvents are identified in elevated concentrations in onsite wells and in an offsite area exhibiting elevated tritium concentrations. At the Barnwell, SC site (operating), only very low concentrations of three organics are found in wells adjacent to disposal units. Hydrocarbons associated with petroleum products are detected at both sites. Hazardous constituents associated with previosuly identified major LLW mixed waste streams, toluene, xylene, chromium, and lead, are at or below detection limits or at background levels in all samples. Review of previously collected data also supports the conclusion that organic solvents are the primary nonradiological contaminants associated with LLW disposal

Site-level progression of periodontal disease during a follow-up period

Science.gov (United States)

Morozumi, Toshiya; Nakagawa, Taneaki; Sugaya, Tsutomu; Kawanami, Masamitsu; Suzuki, Fumihiko; Takahashi, Keiso; Abe, Yuzo; Sato, Soh; Makino-Oi, Asako; Saito, Atsushi; Takano, Satomi; Minabe, Masato; Nakayama, Yohei; Ogata, Yorimasa; Kobayashi, Hiroaki; Izumi, Yuichi; Sugano, Naoyuki; Ito, Koichi; Sekino, Satoshi; Numabe, Yukihiro; Fukaya, Chie; Yoshinari, Nobuo; Fukuda, Mitsuo; Noguchi, Toshihide; Kono, Tomoo; Umeda, Makoto; Fujise, Osamu; Nishimura, Fusanori; Yoshimura, Atsutoshi; Hara, Yoshitaka; Nakamura, Toshiaki; Noguchi, Kazuyuki; Kakuta, Erika; Hanada, Nobuhiro; Takashiba, Shogo; Amitani, Yasuharu; Yoshie, Hiromasa

2017-01-01

Periodontal disease is assessed and its progression is determined via observations on a site-by-site basis. Periodontal data are complex and structured in multiple levels; thus, applying a summary statistical approach (i.e., the mean) for site-level evaluations results in loss of information. Previous studies have shown the availability of mixed effects modeling. However, clinically beneficial information on the progression of periodontal disease during the follow-up period is not available. We conducted a multicenter prospective cohort study. Using mixed effects modeling, we analyzed 18,834 sites distributed on 3,139 teeth in 124 patients, and data were collected 5 times over a 24-month follow-up period. The change in the clinical attachment level (CAL) was used as the outcome variable. The CAL at baseline was an important determinant of the CAL changes, which varied widely according to the tooth surface. The salivary levels of periodontal pathogens, such as Porphyromonas gingivalis and Aggregatibacter actinomycetemcomitans, were affected by CAL progression. “Linear”- and “burst”-type patterns of CAL progression occurred simultaneously within the same patient. More than half of the teeth that presented burst-type progression sites also presented linear-type progression sites, and most of the progressions were of the linear type. Maxillary premolars and anterior teeth tended to show burst-type progression. The parameters identified in this study may guide practitioners in determining the type and extent of treatment needed at the site and patient levels. In addition, these results show that prior hypotheses concerning "burst" and "linear" theories are not valid. PMID:29206238

Spent fuel and high-level radioactive waste storage

International Nuclear Information System (INIS)

Trigerman, S.

1988-06-01

The subject of spent fuel and high-level radioactive waste storage, is bibliographically reviewed. The review shows that in the majority of the countries, spent fuels and high-level radioactive wastes are planned to be stored for tens of years. Sites for final disposal of high-level radioactive wastes have not yet been found. A first final disposal facility is expected to come into operation in the United States of America by the year 2010. Other final disposal facilities are expected to come into operation in Germany, Sweden, Switzerland and Japan by the year 2020. Meanwhile , stress is placed upon the 'dry storage' method which is carried out successfully in a number of countries (Britain and France). In the United States of America spent fuels are stored in water pools while the 'dry storage' method is still being investigated. (Author)

Directions in low-level radioactive waste management. The siting process: establishing a low-level waste-disposal facility

International Nuclear Information System (INIS)

1982-11-01

The siting of a low-level radioactive waste disposal facility encompasses many interrelated activities and, therefore, is inherently complex. The purpose of this publication is to assist state policymakers in understanding the nature of the siting process. Initial discussion focuses on the primary activities that require coordination during a siting effort. Available options for determining site development, licensing, regulating, and operating responsibilities are then considered. Additionally, the document calls attention to technical services available from federal agencies to assist states in the siting process; responsibilities of such agencies are also explained. The appendices include a conceptual plan for scheduling siting activities and an explanation of the process for acquiring agreement state status. An agreement state takes responsibility for licensing and regulating a low-level waste facility within its borders

Evaluation of kriging techniques for high level radioactive waste repository site characterization

International Nuclear Information System (INIS)

Doctor, P.G.

1979-01-01

Kriging is a statistical method for estimating functions that describe spatially distributed phenomena such as groundwater elevation and depth to basalt. It produces a contour model of the geologic formation of a potential site with an associated measure of uncertainty, and it can be used to optimize the selection of additional sampling locations. Kriging was applied to water potential data and top-of-basalt elevations from the Hanford site; the computer code BLUEPACK was used to perform the computations. The water potential contours were in close agreement with a hand-drawn contour map which is used as a standard. It is concluded that kriging can be a useful tool for geologic waste repository site characterization

A New Approach to Site Demand-Based Level Inventory Optimization

Science.gov (United States)

2016-06-01

Note: If probability distributions are estimated based on mean and variance , use ˆ qix  and 2ˆ( )qi to generate these. q in , number of...TO SITE DEMAND-BASED LEVEL INVENTORY OPTIMIZATION by Tacettin Ersoz June 2016 Thesis Advisor: Javier Salmeron Second Reader: Emily...DATES COVERED Master’s thesis 4. TITLE AND SUBTITLE A NEW APPROACH TO SITE DEMAND-BASED LEVEL INVENTORY OPTIMIZATION 5. FUNDING NUMBERS 6

Site characterization and performance assessment for a low-level radioactive waste management site in the American Southwest

International Nuclear Information System (INIS)

Shott, G.J.; Sully, M.J.; Muller, C.J.; Hammermeister, D.P.; Ginanni, J.M.

1995-01-01

The Area 5 Radioactive Waste Management Site located in southern Nevada, has been used for the disposal of low-level radioactive waste since 1961. The site is located in the Mohave Desert of the American Southwest, an extremely arid region receiving as little as 0.1 m/yr of precipitation. Site characterization studies have measured the physical, hydrologic, and geochemical properties of core samples collected from 10 shallow boreholes and 3 deep boreholes that extend through the unsaturated zone to the uppermost aquifer. Results indicate that the unsaturated zone consists of 240 m of dry alluvial sediments and is remarkably uniform with respect to most physical parameters. Measurements of saturated hydraulic conductivity with depth showed no evidence of trends, layering, or anisotropy. Parameters for hydraulic functions were not highly variable and exhibited little trend with depth. Water potential profiles indicate that water movement in the upper alluvium is upward, except immediately following a precipitation event. Below the evaporative zone, the liquid flux was downward and of the same order of magnitude as the upward thermal vapor flux induced by the geothermal gradient. The extreme climatic conditions at the site reduce or eliminate many radionuclide release and transport mechanisms. Downward transport of radionuclides to the uppermost aquifer appears unlikely under current climatic conditions. Important radionuclide transport pathways appear to be limited to upward diffusion and advection of gases and biologically-mediated transport. Conceptual models of disposal site performance have been developed based on site characterization studies. The limited transport pathways and limited land use potential of the site provide reasonable assurance that regulatory performance objectives can be met

Ore levels in Paleozoic of Semipalatinsk test site

International Nuclear Information System (INIS)

Ergaliev, G.Kh.; Myasnikov, A.K.; Fomichev, V.I.

1999-01-01

The regularity of the deposition of main mineralization of industrial types within Semipalatinsk test site proves and here and there defines more exactly location of the ore levels in Eastern Kazakhstan. Two mega levels, namely: Cambrian-Ordovician (siliceous-basalt, island-arc) and Carboniferous (especially carbonaceous-tarragons) ones are the most perspective for localizing the leading gold mineralization in the region

Siting of repositories for high level nuclear waste geological and institutional issues

International Nuclear Information System (INIS)

Ahagen, H.

1993-01-01

Two studies have been conducted in Sweden under contract from SKN-National Board for Spent Nuclear Fuel. The responsibilities of SKN has been transferred to SKI as of July 1, 1992. The first study is related to a compilation of experience and lessons learned from siting of nuclear waste repositories and other controversial facilities in seven countries. The second study is aimed at compiling examples of the state of knowledge related to the regional geological information with relevance to siting of a repository in Sweden. This paper is drawing the general combined conclusions from both these studies. The first study reviewed programs for siting of nuclear and hazardous waste disposal facilities in Canada, Finland, France, Sweden, Switzerland, United Kingdom and USA. The main topics reviewed are related to a/ The use of technical screening, b/ Legal framework and local veto, c/ Public involvement, d/ Interim storage and schedule flexibility, e/ Sequential vs. parallel characterization. The second study focused on the regional geological information available for Sweden and if this information allows for a ''grouping'' of tectonic regions in Sweden with significant differences in history and characteristics. Factors studied as potentially important for siting are bedrock properties, mineralizations, ground water conditions and available volume for a repository. The experience gained from these studies is aimed to be used as background information in the review of the program conducted for the Swedish nuclear utilities by SKB. SKB will according to current plans initiate siting for a repository for spent nuclear fuel in Sweden during 1993. (author). 2 refs

Apparatus for Crossflow Filtration Testing of High Level Waste Samples

International Nuclear Information System (INIS)

Nash, C.

1998-05-01

Remotely-operated experimental apparatuses for verifying crossflow filtration of high level nuclear waste have been constructed at the Savannah River Site (SRS). These units have been used to demonstrate filtration processes at the Savannah River Site, Oak Ridge National Laboratory, the Idaho National Engineering and Environmental Laboratory, and Pacific Northwest National Laboratory. The current work covers the design considerations for experimentation as well as providing results from testing at SRS

Site selection criteria for the shallow land burial of low-level radioactive waste

International Nuclear Information System (INIS)

Falconer, K.L.; Hull, L.C.; Mizell, S.A.

The shallow land burial of low-level waste must be accomplished in a manner that ensures the public and biosphere are protected from harmful amounts of radiation. This can be attained by selecting, designing, operating and closing sites such that contaminants never leave the site boundary in levels above regulatory limits. Site design, operation and closure are all functions of the characteristics of the site selected. As a result, the site selection process offers the most effective means for optimizing safe, efficient and economical low-level waste burial practices. The purpose of this document is to set forth criteria for the selection of shallow land burial sites. Criteria are standard rules, by which the ability of a site to meet waste management goals can be judged. They are comprehensive, universal, and qualitative and are applicable in any geologic environment. Site selection criteria provide the framework for the siting process

Low-level radioactive waste management at the Nevada Test Site - Current status

International Nuclear Information System (INIS)

Becker, B.D.; Crowe, B.M.; Gertz, C.P.; Clayton, W.A.

1999-01-01

The performance objectives of the Department of Energy's Low-Level Radioactive Waste (LLW) disposal facilities located at the Nevada Test Site transcend those of any other radioactive waste disposal site in the US. Situated at the southern end of the Great Basin, 800 feet above the water table, the Area 5 Radioactive Waste Management Site (RWMS) has utilized a combination of engineered shallow land disposal cells and deep augured shafts to dispose a variety of waste streams. These include high volume low-activity wastes, classified materials, and high-specific-activity special case wastes. Twenty miles north of Area 5 is the Area 3 RWMS. Here bulk LLW disposal takes place in subsidence craters formed from underground testing of nuclear weapons. Earliest records indicate that documented LLW disposal activities have occurred at the Area 5 and Area 3 RWMS's since 1961 and 1968, respectively. However, these activities have only been managed under a formal program since 1978. This paper describes the technical attributes of the facilities, present and future capacities and capabilities, and provides a description of the process from waste approval to final disposition. The paper also summarizes the current status of the waste disposal operations

Evaluation and selection of candidate high-level waste forms

International Nuclear Information System (INIS)

1982-03-01

Seven candidate waste forms being developed under the direction of the Department of Energy's National High-Level Waste (HLW) Technology Program, were evaluated as potential media for the immobilization and geologic disposal of high-level nuclear wastes. The evaluation combined preliminary waste form evaluations conducted at DOE defense waste-sites and independent laboratories, peer review assessments, a product performance evaluation, and a processability analysis. Based on the combined results of these four inputs, two of the seven forms, borosilicate glass and a titanate based ceramic, SYNROC, were selected as the reference and alternative forms for continued development and evaluation in the National HLW Program. Both the glass and ceramic forms are viable candidates for use at each of the DOE defense waste-sites; they are also potential candidates for immobilization of commercial reprocessing wastes. This report describes the waste form screening process, and discusses each of the four major inputs considered in the selection of the two forms

Siting a low-level radioactive waste disposal facility in California

International Nuclear Information System (INIS)

Romano, S.A.; Gaynor, R.K.

1991-01-01

US Ecology is the State of California's designee to site, develop and operate a low-level radioactive waste disposal facility. In March 1988, a site in the Ward Valley of California's Mojave Desert was chosen for development. Strong local community support has been expressed for the site. US Ecology anticipates licensing and constructing a facility to receive waste by early 1991. This schedule places California well ahead of the siting milestones identified in Federal law. (author) 1 fig., 2 refs

Comparative approaches to siting low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Newberry, W.F.

1994-07-01

This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection

Estimating microcystin levels at recreational sites in western Lake Erie and Ohio

Science.gov (United States)

Francy, Donna S.; Brady, Amie M. G.; Ecker, Christopher D.; Graham, Jennifer L.; Stelzer, Erin A.; Struffolino, Pamela; Loftin, Keith A.

2016-01-01

Cyanobacterial harmful algal blooms (cyanoHABs) and associated toxins, such as microcystin, are a major global water-quality issue. Water-resource managers need tools to quickly predict when and where toxin-producing cyanoHABs will occur. This could be done by using site-specific models that estimate the potential for elevated toxin concentrations that cause public health concerns. With this study, samples were collected at three Ohio lakes to identify environmental and water-quality factors to develop linear-regression models to estimate microcystin levels. Measures of the algal community (phycocyanin, cyanobacterial biovolume, and cyanobacterial gene concentrations) and pH were most strongly correlated with microcystin concentrations. Cyanobacterial genes were quantified for general cyanobacteria, general Microcystis and Dolichospermum, and for microcystin synthetase (mcyE) for Microcystis, Dolichospermum, and Planktothrix. For phycocyanin, the relations were different between sites and were different between hand-held measurements on-site and nearby continuous monitor measurements for the same site. Continuous measurements of parameters such as phycocyanin, pH, and temperature over multiple days showed the highest correlations to microcystin concentrations. The development of models with high R2values (0.81–0.90), sensitivities (92%), and specificities (100%) for estimating microcystin concentrations above or below the Ohio Recreational Public Health Advisory level of 6 μg L−1 was demonstrated for one site; these statistics may change as more data are collected in subsequent years. This study showed that models could be developed for estimates of exceeding a microcystin threshold concentration at a recreational freshwater lake site, with potential to expand their use to provide relevant public health information to water resource managers and the public for both recreational and drinking waters.

Uncertainty of mass discharge estimation from contaminated sites at screening level

DEFF Research Database (Denmark)

Thomsen, Nanna Isbak; Troldborg, M.; McKnight, Ursula S.

Contaminated sites threaten groundwater resources worldwide. The number of contaminated sites is large and there are too few economic resources available to ensure a thorough investigation and remediation of them all. Risk assessment must already be done at a screening level in order to ensure...... consider possible source and hydrogeological descriptions, where each model is believed to be a realistic representation of the given site, based on the current level of information. Parameter uncertainty is quantified using Monte Carlo simulations. For each conceptual model we calculate a transient mass...

A natural analogue for high-level waste in tuff: Chemical analysis and modeling of the Valles site

International Nuclear Information System (INIS)

Stockman, H.W.; Krumhansl, J.L.; Ho, C.K.; Kovach, L.; McConnell, V.S.

1995-01-01

The contact between an obsidian flow and a steep-walled tuff canyon was examined as an analogue for a high-level waste repository. The analogue site is located in the Valles Caldera in New Mexico, where a massive obsidian flow filled a paleocanyon in the Battleship Rock Tuff. The obsidian flow provided a heat source, analogous to waste panels or an igneous intrusion in a repository, and caused evaporation and migration of water. The tuff and obsidian samples were analyzed for major and trace elements and mineralogy by INAA, XRF, x-ray diffraction, and scanning electron microscopy and electron microprobe. Samples were also analyzed for D/H and 39 Ar/ 40 Ar isotopic composition. Overall, the effects of the heating event seem to have been slight and limited to the tuff nearest the contact. There is some evidence of devitrification and migration of volatiles in the tuff within 10 m of the contact, but variations in major and trace element chemistry are small and difficult to distinguish from the natural (pre-heating) variability of the rocks

Department of Energy pretreatment of high-level and low-level wastes

International Nuclear Information System (INIS)

McGinnis, C.P.; Hunt, R.D.

1995-01-01

The remediation of the 1 x 10 8 gal of highly radioactive waste in the underground storage tanks (USTs) at five US Department of Energy (DOE) sites is one of DOE's greatest challenges. Therefore, the DOE Office of Environmental Management has created the Tank Focus Area (TFA) to manage an integrated technology development program that results in the safe and efficient remediation of UST waste. The TFA has divided its efforts into five areas, which are safety, characterization, retrieval/closure, pretreatment, and immobilization. All DOE pretreatment activities are integrated by the Pretreatment Technical Integration Manager of the TFA. For FY 1996, the 14 pretreatment tasks are divided into 3 systems: supernate separations, sludge treatment, and solid/liquid separation. The plans and recent results of these TFA tasks, which include two 25,000-gal demonstrations and two former TFA tasks on Cs removal, are presented. The pretreatment goals are to minimize the volume of high-level waste and the radioactivity in low-level waste

High-level radioactive waste management in the United States. Background and status: 1996

International Nuclear Information System (INIS)

Dyer, J.R.

1996-01-01

The US high-level radioactive waste disposal program is investigating a site at Yucca Mountain, Nevada, to determine whether or not it is a suitable location for the development of a deep mined geologic repository. At this time, the US program is investigating a single site, although in the past, the program involved successive screening and comparison of alternate locations. The United States civilian reactor programs do not reprocess spent fuel; the high-level waste repository will be designed for the emplacement or spent fuel and a limited amount of vitrified high-level wastes from previous reprocessing in the US. The legislation enabling the US program also contains provisions for a Monitored Retrievable Storage facility, which could provide temporary storage of spent fuel accepted for disposal, and improve the flexibility of the repository development schedule

Importance of geologic characterization of potential low-level radioactive waste disposal sites

Science.gov (United States)

Weibel, C.P.; Berg, R.C.

1991-01-01

Using the example of the Geff Alternative Site in Wayne County, Illinois, for the disposal of low-level radioactive waste, this paper demonstrates, from a policy and public opinion perspective, the importance of accurately determining site stratigraphy. Complete and accurate characterization of geologic materials and determination of site stratigraphy at potential low-level waste disposal sites provides the frame-work for subsequent hydrologic and geochemical investigations. Proper geologic characterization is critical to determine the long-term site stability and the extent of interactions of groundwater between the site and its surroundings. Failure to adequately characterize site stratigraphy can lead to the incorrect evaluation of the geology of a site, which in turn may result in a lack of public confidence. A potential problem of lack of public confidence was alleviated as a result of the resolution and proper definition of the Geff Alternative Site stratigraphy. The integrity of the investigation was not questioned and public perception was not compromised. ?? 1991 Springer-Verlag New York Inc.

Reproduction of European eel jeopardised by high levels of dioxins and dioxin-like PCBs?

Science.gov (United States)

Geeraerts, C; Focant, J-F; Eppe, G; De Pauw, E; Belpaire, C

2011-09-01

Dioxins, furans and dioxin-like polychlorinated biphenyls (PCBs) were analysed in muscle tissue from yellow phased European eel (Anguilla anguilla) from 38 sites in Belgium. Dioxin concentrations in eel vary considerably between sampling locations, indicating that yellow eel is a good indicator of local pollution levels. Measured levels of dioxin-like PCBs are much higher than those of the dioxins and furans. In the majority of the sites, eel has levels considered to be detrimental for their reproduction. Field levels of dioxin and dioxin-like PCBs are therefore suggested as an additional causal factor contributing to the decline of the European eel. 42% of the sampling sites show especially dioxin-like PCB levels exceeding the European consumption level (with a factor 3 on average). Human consumption of eel, especially in these highly contaminated sites, seems unjustified. Copyright © 2011 Elsevier B.V. All rights reserved.

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

Energy Technology Data Exchange (ETDEWEB)

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

1996-03-01

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

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

International Nuclear Information System (INIS)

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

1996-03-01

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

Siting a low-level waste facility in California: A success story

International Nuclear Information System (INIS)

Romano, S.A.; Gaynor, R.K.

1988-01-01

US Ecology is the state of California's designee to site, develop, and operate a low-level radioactive waste disposal facility. The facility will meet the state's responsibilities under the Low-Level Radioactive Waste Policy Act as amended. By January 1988, US Ecology narrowed its efforts to two candidate sites. Strong local community support has been expressed for both sites. US Ecology will select a single proposed site for licensing in 1988 and anticipates receiving waste in late 1900 or early 1991. This schedule places California well ahead of the milestones identified in federal law. The success to date in California can be attributed in large part to the open process used to involve citizens' advisory committees (CACs) and the general public at critical stages of the projects

Canadian experiences in characterizing two low-level and intermediate-level radioactive waste management sites

International Nuclear Information System (INIS)

Heystee, R.J.; Rao, P.K.M.

1984-02-01

Low-level waste (LLW) and intermediate-level reactor waste (ILW) arise in Canada from the operation of nuclear power reactors for the generation of electricity and from the operation of reactors for nuclear research and development as well as for the production of separated radioisotopes. The majority of this waste is currently being safely managed at two sites in the Province of Ontario: (1) Chalk River Nuclear Laboratories, and (2) Ontario Hydro's Bruce Nuclear Power Development Radioactive Waste Operations Site 2. Although these storage facilities can safely manage the waste for a long period of time, there are advantages in disposal of the LLW and ILW. The design of the disposal facilities and the assessment of long-term performance will require that the hydrologic and geologic data be gathered for a potential disposal site. Past site characterization programs at the two aforementioned waste storage sites have produced information which will be useful to future disposal studies in similar geologic materials. The assessment of long-term performance will require that predictions be made regarding the potential subsurface migration of radionuclides. However there still remain many uncertainties regarding the chemical and physical processes which affect radionuclide mobility and concentrations, in particular hydrodynamic dispersion, geochemical reactions, and transport through fractured media. These uncertainties have to be borne in mind when conducting the performance assessments and adequate conservatism must be included to account for the uncertainties. (author)

Geohydrologic aspects for siting and design of low-level radioactive-waste disposal

Science.gov (United States)

Bedinger, M.S.

1989-01-01

The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard as a result of radioactive decay. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by ground water. The unsaturated zone generally is preferred for isolating the waste. Low-level radioactive waste may need to be isolated for 300 to 500 years. Maintenance and monitoring of the repository site are required by Federal regulations for only the first 100 years. Therefore, geohydrology of the repository site needs to provide natural isolation of the waste for the hazardous period following maintenance of the site. Engineering design of the repository needs to be compatible with the natural geohydrologic conditions at the site. Studies at existing commercial and Federal waste-disposal sites provide information on the problems encountered and the basis for establishing siting guidelines for improved isolation of radioactive waste, engineering design of repository structures, and surveillance needs to assess the effectiveness of the repositories and to provide early warning of problems that may require remedial action.Climate directly affects the hydrology of a site and probably is the most important single factor that affects the suitability of a site for shallow-land burial of low-level radioactive waste. Humid and subhumid regions are not well suited for shallow isolation of low-level radioactive waste in the unsaturated zone; arid regions with zero to small infiltration from precipitation, great depths to the water table, and long flow paths to natural discharge areas are naturally well suited to isolation of the waste. The unsaturated zone is preferred for isolation of low-level radioactive waste. The guiding rationale is to minimize contact of water with the waste and to

Site characterization in connection with the low level defense waste management site in Area 5 of the Nevada Test Site, Nye County, Nevada. Final report

International Nuclear Information System (INIS)

Case, C.; Davis, J.; French, R.; Raker, S.

1984-09-01

The Site Characterization Report for the Defense Low Level Waste Management Site (RWMS) in Area 5 of the Nevada Test Site deals with the FY80-FY84 DRI activities. The areas that have been studied include geology, hydrology, unsaturated flow, soil and soil water chemistry, flood hazard, and economics-demographics. During this time the site characterization effort focussed on the following items as requested by NVO: geological and hydrological limitations to greater depth disposal of radioactive waste; potential for tectonic, seismic or volcanic activity (extent and frequency which these processes significantly affect the ability of the disposal operation to meet performance objectives); the possibility of groundwater intrusion into the waste zone, and its significance; topography of the RWMS with significance to drainage and flood potential (100-year flood plain, coastal high-hazard area or wetland); upstream drainage which may require modification to avoid erosion; population growth and future development; and the presence or absence of economically significant natural resources which, if exploited, would result in failure to meet performance objectives. The items mentioned above are dealt with in the description of activities and results in the body of the report. Extensive references, 32 figures, 20 tables

Levels of particulate matter in rural, urban and industrial sites in Spain

Energy Technology Data Exchange (ETDEWEB)

Querol, X.; Alastuey, A.; Rodriguez, S.; Viana, M.M. [Instituto de Ciencias de la Tierra del CSIC, C/Luis Sole y Sabaris s/n, 08028 Barcelona (Spain); Artinano, B.; Salvador, P. [Centro de Investigaciones Energeticas, Mediambientales y Tecnologicas, CIEMAT Avda. Complutense 22, 28040 Madrid (Spain); Mantilla, E. [Centro de Estudios Ambientales del Mediterraneo, CEAM. Parque tecnologico, C-4, sector oeste, 46980 Paterna, Valencia (Spain); Santos, S. Garcia do; Patier, R. Fernandez [Area de Contaminacion Atmosferica, Instituto de Salud Carlos III, Ctra. Majadahonda-Pozuelo, km n. 2, 28220 Majadahonda, Madrid (Spain); De La Rosa, J.; De la Campa, A. Sanchez [Departamento de Geologia, Universidad de Huelva, Campus Universitario de la Rabida, La Rabida, 21819 Huelva (Spain); Menendez, M.; Gil, J.J. [Departamento Mineralogia y Petrologia. Universidad del Pais Vasco, Aptdo. 644, 48080 Bilbao (Spain)

2004-12-01

This paper summarises the results of a series of studies on the interpretation of time series of levels of total suspended particles (TSP) and particulate matter (PM, <10 {mu}m) in six regions of Spain in the period 1996-2000. In addition to the local pollution events, high PM10 episodes are recorded during African dust outbreaks, regional atmospheric recirculation events (mainly in spring to autumn), and to a lesser extent, under the influence of European and Mediterranean long range transported air masses. The lowest PM10 levels are usually recorded under Atlantic air mass advective conditions. All these regional and large-scale processes account for the relatively high PM10 levels recorded in regional background stations in Spain. Thus, the PM10 levels recorded at EMEP (Cooperative Program for Monitoring and Evaluation of the Long Range Transmission of Air Pollutants in Europe) regional background stations between March 2001 and March 2002 are very close to the annual limit value proposed for 2010 by the EU Air Quality Directive 1999/30/CE. Chemical data obtained for the different monitoring stations during 2001 show a high mineral load in PM10 for most of the study sites in Spain. Furthermore, a high marine aerosol load is evidenced in the Canary Islands. These mineral and marine loads are lower when considering PM2.5, but a relatively high proportion (8-21%) of mineral dust is still present.

High-level waste melter alternatives assessment report

Energy Technology Data Exchange (ETDEWEB)

Calmus, R.B.

1995-02-01

This document describes the Tank Waste Remediation System (TWRS) High-Level Waste (HLW) Program`s (hereafter referred to as HLW Program) Melter Candidate Assessment Activity performed in fiscal year (FY) 1994. The mission of the TWRS Program is to store, treat, and immobilize highly radioactive Hanford Site waste (current and future tank waste and encapsulated strontium and cesium isotopic sources) in an environmentally sound, safe, and cost-effective manner. The goal of the HLW Program is to immobilize the HLW fraction of pretreated tank waste into a vitrified product suitable for interim onsite storage and eventual offsite disposal at a geologic repository. Preparation of the encapsulated strontium and cesium isotopic sources for final disposal is also included in the HLW Program. As a result of trade studies performed in 1992 and 1993, processes planned for pretreatment of tank wastes were modified substantially because of increasing estimates of the quantity of high-level and transuranic tank waste remaining after pretreatment. This resulted in substantial increases in needed vitrification plant capacity compared to the capacity of original Hanford Waste Vitrification Plant (HWVP). The required capacity has not been finalized, but is expected to be four to eight times that of the HWVP design. The increased capacity requirements for the HLW vitrification plant`s melter prompted the assessment of candidate high-capacity HLW melter technologies to determine the most viable candidates and the required development and testing (D and T) focus required to select the Hanford Site HLW vitrification plant melter system. An assessment process was developed in early 1994. This document describes the assessment team, roles of team members, the phased assessment process and results, resulting recommendations, and the implementation strategy.

High-level waste melter alternatives assessment report

International Nuclear Information System (INIS)

Calmus, R.B.

1995-02-01

This document describes the Tank Waste Remediation System (TWRS) High-Level Waste (HLW) Program's (hereafter referred to as HLW Program) Melter Candidate Assessment Activity performed in fiscal year (FY) 1994. The mission of the TWRS Program is to store, treat, and immobilize highly radioactive Hanford Site waste (current and future tank waste and encapsulated strontium and cesium isotopic sources) in an environmentally sound, safe, and cost-effective manner. The goal of the HLW Program is to immobilize the HLW fraction of pretreated tank waste into a vitrified product suitable for interim onsite storage and eventual offsite disposal at a geologic repository. Preparation of the encapsulated strontium and cesium isotopic sources for final disposal is also included in the HLW Program. As a result of trade studies performed in 1992 and 1993, processes planned for pretreatment of tank wastes were modified substantially because of increasing estimates of the quantity of high-level and transuranic tank waste remaining after pretreatment. This resulted in substantial increases in needed vitrification plant capacity compared to the capacity of original Hanford Waste Vitrification Plant (HWVP). The required capacity has not been finalized, but is expected to be four to eight times that of the HWVP design. The increased capacity requirements for the HLW vitrification plant's melter prompted the assessment of candidate high-capacity HLW melter technologies to determine the most viable candidates and the required development and testing (D and T) focus required to select the Hanford Site HLW vitrification plant melter system. An assessment process was developed in early 1994. This document describes the assessment team, roles of team members, the phased assessment process and results, resulting recommendations, and the implementation strategy

Strategic program for deep geological disposal of high level radioactive waste in China

International Nuclear Information System (INIS)

Wang Ju

2004-01-01

A strategic program for deep geological disposal of high level radioactive waste in China is proposed in this paper. A '3-step technical strategy': site selection and site characterization-site specific underground research laboratory-final repository, is proposed for the development of China's high level radioactive waste repository. The activities related with site selection and site characterization for the repository can be combined with those for the underground research laboratory. The goal of the strategy is to build China's repository around 2040, while the activities can be divided into 4 phases: 1) site selection and site characterization; 2) site confirmation and construction of underground research laboratory, 3) in-situ experiment and disposal demonstration, and 4) construction of repository. The targets and tasks for each phase are proposed. The logistic relationship among the activities is discussed. It is pointed out that the site selection and site characterization provide the basis for the program, the fundamental study and underground research laboratory study are the key support, the performance assessment plays a guiding role, while the construction of a qualified repository is the final goal. The site selection can be divided into 3 stages: comparison among pre-selected areas, comparison among pre-selected sites and confirmation of the final site. According to this strategy, the final site for China's underground research laboratory and repository will be confirmed in 2015, where the construction of an underground laboratory will be started. In 2025 the underground laboratory will have been constructed, while in around 2040, the construction of a final repository is to be completed

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

International Nuclear Information System (INIS)

Radulesscu, G.; Tang, J.S.

2000-01-01

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M andO [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M andO 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M andQ 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M andO 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable canisters. The intended use of this

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

Energy Technology Data Exchange (ETDEWEB)

G. Radulesscu; J.S. Tang

2000-06-07

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M&O 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M&Q 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M&O 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable

Future directions of defense programs high-level waste technology programs

International Nuclear Information System (INIS)

Chee, T.C.; Shupe, M.W.; Turner, D.A.; Campbell, M.H.

1987-01-01

The Department of Energy has been managing high-level waste from the production of nuclear materials for defense activities over the last forty years. An objective for the Defense Waste and Transportation Management program is to develop technology which ensures the safe, permanent disposal of all defense radioactive wastes. Technology programs are underway to address the long-term strategy for permanent disposal of high-level waste generated at each Department of Energy site. Technology is being developed for assessing the hazards, environmental impacts, and costs of each long-term disposal alternative for selection and implementation. This paper addresses key technology development areas, and consideration of recent regulatory requirements associated with the long-term management of defense radioactive high-level waste

On-Site Renewable Energy and Green Buildings: A System-Level Analysis.

Science.gov (United States)

Al-Ghamdi, Sami G; Bilec, Melissa M

2016-05-03

Adopting a green building rating system (GBRSs) that strongly considers use of renewable energy can have important environmental consequences, particularly in developing countries. In this paper, we studied on-site renewable energy and GBRSs at the system level to explore potential benefits and challenges. While we have focused on GBRSs, the findings can offer additional insight for renewable incentives across sectors. An energy model was built for 25 sites to compute the potential solar and wind power production on-site and available within the building footprint and regional climate. A life-cycle approach and cost analysis were then completed to analyze the environmental and economic impacts. Environmental impacts of renewable energy varied dramatically between sites, in some cases, the environmental benefits were limited despite the significant economic burden of those renewable systems on-site and vice versa. Our recommendation for GBRSs, and broader policies and regulations, is to require buildings with higher environmental impacts to achieve higher levels of energy performance and on-site renewable energy utilization, instead of fixed percentages.

Pre-disposal storage, transport and handling of vitrified high level waste

International Nuclear Information System (INIS)

Kempe, T.F.; Martin, A.

1981-05-01

The objectives of the study were to review non site-specific engineering features of the storage, transport and handling of vitrified high level radioactive waste prior to its transfer into an underground repository, and to identify those features which require validation or development. Section headings are: introduction (historical and technical background); characteristics and arisings of vitrified high level waste; overpacks (additional containment barrier, corrosion resistant); interim storage of HLW; transport of HLW; handling; conclusions and recommendations. (U.K.)

Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings

Science.gov (United States)

Bedinger, Marion S.; Stevens, Peter R.

1990-01-01

In the United States, low-level radioactive waste is disposed by shallow-land burial. Low-level radioactive waste generated by non-Federal facilities has been buried at six commercially operated sites; low-level radioactive waste generated by Federal facilities has been buried at eight major and several minor Federally operated sites (fig. 1). Generally, low-level radioactive waste is somewhat imprecisely defined as waste that does not fit the definition of high-level radioactive waste and does not exceed 100 nCi/g in the concentration of transuranic elements. Most low-level radioactive waste generated by non-Federal facilities is generated at nuclear powerplants; the remainder is generated primarily at research laboratories, hospitals, industrial facilities, and universities. On the basis of half lives and concentrations of radionuclides in low-level radioactive waste, the hazard associated with burial of such waste generally lasts for about 500 years. Studies made at several of the commercially and Federally operated low-level radioactive-waste repository sites indicate that some of these sites have not provided containment of waste nor the expected protection of the environment.

Geohydrologic problems at low-level radioactive waste disposal sites in the United States of America

International Nuclear Information System (INIS)

Fischer, J.N.; Robertson, J.B.

1984-01-01

Several commercial and US Department of Energy low-level radioactive waste disposal sites in the USA have not adequately contained the waste products. Studies of these sites indicate a number of causes for the problems, including water accumulation in filled trenches, breaches of trench cap integrity, erosion, high water table, hydrogeological complexity, flooding, complex leachate chemistry, and rapid radionuclide migration in groundwater. These problems can be avoided through the application of practical, comprehensive, and common sense earth-science guidelines discussed in this paper. (author)

Character and levels of radioactive contamination of underground waters at Semipalatinsk test site

Energy Technology Data Exchange (ETDEWEB)

Subbotin, S.; Lukashenko, S.; Turchenko, Y. [Institute of radiation safety and ecology (Kazakhstan)

2014-07-01

According to the data of RK government commission, 470 explosions have been set off at the Semipalatinsk Test Site (STS), inclusive of 26 surface, 90 in the air and 354 underground nuclear explosions (UNE), 103 of those have been conducted in tunnels and 251 - in boreholes. Underground nuclear explosions have been conducted at STS in horizontal mines, called - 'tunnels' ('Degelen' test site) and vertical mines called 'boreholes' ('Balapan' and 'Sary-Uzen' test sites). Gopher cavities of boreholes and tunnels are in different geotechnical conditions, that eventually specify migration of radioactive products with underground waters. Central cavities of UNE in holes are located significantly below the level of distribution of underground water. High temperature remains for a long time due to presence of overlying rock mass. High temperatures contribute to formation of thermal convection. When reaching the cavity, the water heat up, dissolve chemical elements and radionuclides and return with them to the water bearing formation. In the major part of 'Balapan' site for underground water of regional basin is characterized by low concentrations of radionuclides. High concentrations of {sup 137}Cs in underground water have been found only in immediate vicinity to 'warfare' boreholes. Formation of radiation situation in the 'Balapan' test site area is also affected by local area of underground water discharge. It is located in the valley of Shagan creek, where the concentration of {sup 3}H reaches 700 kBq/l. Enter of underground water contaminated with tritium into surface water well continue. In this case it is expected that tritium concentration in discharge zone can significantly change, because this migration process depends on hydro geological factors and the amount of atmospheric precipitation. Central cavities of nuclear explosions, made in tunnels, are above the level of underground

Independent Assessment of the Savannah River Site High-Level Waste Salt Disposition Alternatives Evaluation

International Nuclear Information System (INIS)

Case, J. T.; Renfro, M. L.

1998-01-01

This report presents the results of the Independent Project Evaluation (IPE) Team assessment of the Westinghouse Savannah River Company High-Level Waste Salt Disposition Systems Engineering (SE) Team's deliberations, evaluations, and selections. The Westinghouse Savannah River Company concluded in early 1998 that production goals and safety requirements for processing SRS HLW salt to remove Cs-137 could not be met in the existing In-Tank Precipitation Facility as currently configured for precipitation of cesium tetraphenylborate. The SE Team was chartered to evaluate and recommend an alternative(s) for processing the existing HLW salt to remove Cs-137. To replace the In-Tank Precipitation process, the Savannah River Site HLW Salt Disposition SE Team down-selected (October 1998) 140 candidate separation technologies to two alternatives: Small-Tank Tetraphenylborate (TPB) Precipitation (primary alternative) and Crystalline Silicotitanate (CST) Nonelutable Ion Exchange (backup alternative). The IPE Team, commissioned by the Department of Energy, concurs that both alternatives are technically feasible and should meet all salt disposition requirements. But the IPE Team judges that the SE Team's qualitative criteria and judgments used in their down-selection to a primary and a backup alternative do not clearly discriminate between the two alternatives. To properly choose between Small-Tank TPB and CST Ion Exchange for the primary alternative, the IPE Team suggests the following path forward: Complete all essential R and D activities for both alternatives and formulate an appropriate set of quantitative decision criteria that will be rigorously applied at the end of the R and D activities. Concurrent conceptual design activities should be limited to common elements of the alternatives

ENTRIA 2014. Memorandum on the disposal of high-level radioactive residuals

International Nuclear Information System (INIS)

Roehlig, Klaus-Juergen; Walther, Clemens; Bach, Friedrich-Wilhelm

2014-01-01

The memorandum on the disposal of high-level radioactive residuals covers the following issues: description of the problem: a ''wicked problem'', risks and NIMBY, the site selection law, international boundary conditions; disposal strategy and types of facilities: safety and reversibility, long-term surface storage, deep storage; risk and safety; procedural justice and the site selection process; social innovations and the requirement of long-term institutions; conclusion - central stress fields.

Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, vertical emplacement mode: Volume 1

International Nuclear Information System (INIS)

1987-12-01

This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs

Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, vertical emplacement mode: Volume 1

Energy Technology Data Exchange (ETDEWEB)

1987-12-01

This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs.

Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, horizontal emplacment mode: Volume 1

International Nuclear Information System (INIS)

1987-12-01

This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packaging, and other surface facility operations are described. Operations in the shafts and underground are described, including waste hoisting, transfer, and horizontal emplacement. This report specifically addresses the horizontal emplacement mode, the passive alternate design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs

National high-level waste systems analysis

International Nuclear Information System (INIS)

Kristofferson, K.; O'Holleran, T.P.

1996-01-01

Previously, no mechanism existed that provided a systematic, interrelated view or national perspective of all high-level waste treatment and storage systems that the US Department of Energy manages. The impacts of budgetary constraints and repository availability on storage and treatment must be assessed against existing and pending negotiated milestones for their impact on the overall HLW system. This assessment can give DOE a complex-wide view of the availability of waste treatment and help project the time required to prepare HLW for disposal. Facilities, throughputs, schedules, and milestones were modeled to ascertain the treatment and storage systems resource requirements at the Hanford Site, Savannah River Site, Idaho National Engineering Laboratory, and West Valley Demonstration Project. The impacts of various treatment system availabilities on schedule and throughput were compared to repository readiness to determine the prudent application of resources. To assess the various impacts, the model was exercised against a number of plausible scenarios as discussed in this paper

Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects. Annual report, October 1984-September 1985. Volume 4

International Nuclear Information System (INIS)

Meyer, R.E.; Arnold, W.D.; Blencoe, J.G.; Jacobs, G.K.; Kelmers, A.D.; Seeley, F.G.; Whatley, S.K.

1986-05-01

Information pertaining to the potential geochemical behavior of radionuclides at candidate sites for a high-level radioactive waste repository, which is being developed by projects within the Department of Energy (DOE), is being evaluated by Oak Ridge National Laboratory for the Nuclear Regulatory Commission (NRC). During this report period, emphasis was placed on the evaluation of information pertinent to the Hanford site in southeastern Washington. Results on the sorption/solubility behavior of technetium, neptunium, and uranium in the basalt/water geochemical system are summarized and compared to the results of DOE. Also, summaries of results are reported from two geochemical modeling studies: (1) an evaluation of the information developed by DOE on the native copper deposits of Michigan as a natural analog for the emplacement of copper canisters in a repository in basalt, and (2) calculation of the solubility and speciation of radionuclides for representative groundwaters from the Yucca Mountain site in Nevada

Use of DOE site selection criteria for screening low-level waste disposal sites on the Oak Ridge Reservation

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.; Stinton, L.H.

1983-09-01

The proposed Department of Energy (DOE) site selection criteria were applied to the Oak Ridge Reservation, and the application was evaluated to determine the criteria's usefulness in the selection of a low-level waste disposal site. The application of the criteria required the development of a methodology to provide a framework for evaluation. The methodology is composed of site screening and site characterization stages. The site screening stage relies on reconnaissance data to identify a preferred site capable of satisfying the site selection criteria. The site characterization stage relies on a detailed site investigation to determine site acceptability. The site selection criteria were applied to the DOE Oak Ridge Reservation through the site screening stage. Results of this application were similar to those of a previous siting study on the Oak Ridge Reservation. The DOE site selection criteria when coupled with the methodology that was developed were easily applied and would be adaptable to any region of interest

Corrosion and failure processes in high-level waste tanks

International Nuclear Information System (INIS)

Mahidhara, R.K.; Elleman, T.S.; Murty, K.L.

1992-11-01

A large amount of radioactive waste has been stored safely at the Savannah River and Hanford sites over the past 46 years. The aim of this report is to review the experimental corrosion studies at Savannah River and Hanford with the intention of identifying the types and rates of corrosion encountered and indicate how these data contribute to tank failure predictions. The compositions of the High-Level Wastes, mild steels used in the construction of the waste tanks and degradation-modes particularly stress corrosion cracking and pitting are discussed. Current concerns at the Hanford Site are highlighted

US program for the immobilization of high-level nuclear wastes

International Nuclear Information System (INIS)

Crandall, J.L.

1979-01-01

A program has been developed for long-term management of high-level nuclear waste. The Savannah River Operations Office of the US Department of Energy is acting as the lead office for this program with technical advice from the E.I. du Pont de Nemours and Company. The purpose of the long-term program is to immobilize the DOE high-level waste in forms that act as highly efficient barriers against radionuclide release to the disposal site and to provide technology for similar treatment of commercial high-level waste in case reprocessing of commercial nuclear fuels is ever resumed. Descriptions of existing DOE and commercial wastes, program strategy, program expenditures, development of waste forms, evaluation and selection of waste forms, regulatory aspects of waste form selection, project schedules, and cost estimates for immobilization facilities are discussed

Ground-level airborne particulate matter near important Portuguese Cultural Heritage sites in high polluted (Lisbon) and low polluted (Evora) urban environments

Science.gov (United States)

Schiavon, N.; Wagner, F.; Candeias, A.; Kandler, K.; Tobias, L.; Mirao, J.

2012-04-01

As part of a wider project on aerosol composition in the Southwestern part of the Iberian peninsula, an intensive field monitoring/sampling/analytical campaign has been conducted in August and December 2011 to assess indoor and outdoor atmospheric aerosol optical and microphysical parameters (Nephelometry), number/mass/size distribution (TEOM, MAAP, OPS) and single particle minero-chemical composition on filter collected samples (VP-SEM+EDS, XRD) at several sheltered and unsheltered locations close to important Cultural Heritage monuments in Evora and Lisbon, Portugal. Sites investigated included the Igreja do S. Francisco in Evora, the Cristo Rei sanctuary, Jeronimos Monastery, and Lisbon Castle in Lisbon. At Cristo Rei measurements at sea level, around 100m and around 180m were carried out in order to determine the vertical profile of the particle size distribution. Measurements were taken at different times of day reflecting changes in atmospheric mixing and air pollution levels. Measurements were also performed near an air quality monitoring station at Avenida de Libertade (the busiest traffic artery in Lisbon city center) during traffic peak hour. One of the aims of the campaign was to determine differences in airborne particulate matter compositions and concentrations between an urban coastal high pollution (Lisbon) and a low pollution (Evora) environments and how these could affect the nature of decay patterns and processes in the building materials of the monuments under investigation. Preliminary results indicate significant differences in particle properties between the 2 cities as well as between indoor and outdoor locations. One interesting result was the detection of considerable amounts of particle of oceanic origin (such as sodium chloride) in the Evora site even at 130 km away from the coast. Despite its relatively unpolluted location, single particle analysis by SEM+EDS at the Evora site reveals the presence of significant numbers of particle of

Highly Dense Isolated Metal Atom Catalytic Sites

DEFF Research Database (Denmark)

Chen, Yaxin; Kasama, Takeshi; Huang, Zhiwei

2015-01-01

-ray diffraction. A combination of electron microscopy images with X-ray absorption spectra demonstrated that the silver atoms were anchored on five-fold oxygen-terminated cavities on the surface of the support to form highly dense isolated metal active sites, leading to excellent reactivity in catalytic oxidation......Atomically dispersed noble-metal catalysts with highly dense active sites are promising materials with which to maximise metal efficiency and to enhance catalytic performance; however, their fabrication remains challenging because metal atoms are prone to sintering, especially at a high metal...... loading. A dynamic process of formation of isolated metal atom catalytic sites on the surface of the support, which was achieved starting from silver nanoparticles by using a thermal surface-mediated diffusion method, was observed directly by using in situ electron microscopy and in situ synchrotron X...

Development of high-level waste solidification technology 1

Energy Technology Data Exchange (ETDEWEB)

Kim, Joon Hyung; Kim, Hwan Young; Kim, In Tae [and others

1999-02-01

Spent nuclear fuel contains useful nuclides as valuable resource materials for energy, heat and catalyst. High-level wastes (HLW) are expected to be generated from the R and D activities and reuse processes. It is necessary to develop vitrification or advanced solidification technologies for the safe long-term management of high level wastes. As a first step to establish HLW vitrification technology, characterization of HLWs that would arise at KAERI site, glass melting experiments with a lab-scale high frequency induction melter, and fabrication and property evaluation of base-glass made of used HEPA filter media and additives were performed. Basic study on the fabrication and characterization of candidate ceramic waste form (Synroc) was also carried out. These HLW solidification technologies would be directly useful for carrying out the R and Ds on the nuclear fuel cycle and waste management. (author). 70 refs., 29 tabs., 35 figs.

Atmospheric Dispersion Simulation for Level 3 PSA at Ulchin Nuclear Site using a PUFF model

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Jun; Han, Seok-Jung; Jeong, Hyojoon; Jang, Seung-Cheol [KAERI, Daejeon (Korea, Republic of)

2015-05-15

Air dispersion prediction is a key in the level 3 PSA to predict radiation releases into the environment for preparing an effective strategy for an evacuation as a basis of the emergency preparedness. To predict the atmospheric dispersion accurately, the specific conditions of the radiation release location should be considered. There are various level 3 PSA tools and MACSS2 is one of the widely used level 3 PSA tools in many countries including Korea. Due to the characteristics of environmental conditions in Korea, it should be demonstrated that environmental conditions of Korea nuclear sites can be appropriately illustrated by the tool. In Korea, because all nuclear power plants are located on coasts, sea and land breezes might be a significant factor. The objectives of this work is to simulate the atmospheric dispersion for Ulchin nuclear site in Korea using a PUFF model and to generate the data which can be used for the comparison with that of PLUME model. A nuclear site has own atmospheric dispersion characteristics. Especially in Korea, nuclear sites are located at coasts and it is expected that see and land breeze effects are relatively high. In this work, the atmospheric dispersion at Ulchin nuclear site was simulated to evaluate the effect of see and land breezes in four seasons. In the simulation results, it was observed that the wind direction change with time has a large effect on atmospheric dispersion. If the result of a PLUME model is more conservative than most severe case of a PUFF model, then the PLUME model could be used for Korea nuclear sites in terms of safety assessment.

Identification of sites for the low-level waste disposal development and demonstration program

International Nuclear Information System (INIS)

Ketelle, R.H.; Lee, D.W.

1988-04-01

This report presents the results of site selection studies for potential low-level radioactive waste disposal sites on the Oak Ridge Reservation (ORR). Summaries of the site selection procedures used and results of previous site selection studies on the ORR are included. This report includes recommendations of sites for demonstration of shallow land burial using engineered trench designs and demonstration of above-grade disposal using design concepts similar to those used in tumulus disposal. The site selection study, like its predecessor (ORNL/TM-9717, Use of DOE Site Selection Criteria for Screening Low-Level Waste Disposal Sites on the Oak Ridge Reservation), involved application of exclusionary site screening criteria to the region of interest to eliminate unacceptable areas from consideration. Also like the previous study, the region of interest for this study was limited to the Oak Ridge Department of Energy Reservation. Reconnaissance-level environmental data were used in the study, and field inspections of candidate sites were made to verify the available reconnaissance data. Five candidate sites, all underlain by Knox dolomite residuum and bedrock, were identified for possible development of shallow land burial facilities. Of the five candidate sites, the West Chestnut site was judged to be best suited for deployment of the shallow land burial technology. Three candidate sites, all underlain by the Conasauga Group in Bear Creek Valley, were identified for possible development of above-grade disposal technologies. Of the three sites identified, the Central Bear Creek Valley site lying between State Route 95 and Gum Hollow Road was ranked most favorable for deployment of the above-grade disposal technology

Key scientific challenges in geological disposal of high level radioactive waste

International Nuclear Information System (INIS)

Wang Ju

2007-01-01

The geological disposal of high radioactive waste is a challenging task facing the scientific and technical world. This paper introduces the latest progress of high level radioactive disposal programs in the latest progress of high level radioactive disposal programs in the world, and discusses the following key scientific challenges: (1) precise prediction of the evolution of a repository site; (2) characteristics of deep geological environment; (3) behaviour of deep rock mass, groundwater and engineering material under coupled con-ditions (intermediate to high temperature, geostress, hydraulic, chemical, biological and radiation process, etc); (4) geo-chemical behaviour of transuranic radionuclides with low concentration and its migration with groundwater; and (5) safety assessment of disposal system. Several large-scale research projects and several hot topics related with high-level waste disposal are also introduced. (authors)

Strategies for high-level radioactive waste management: the U.S. experience

International Nuclear Information System (INIS)

Cotton, T.A.

1984-01-01

Technology exists or is under development for the safe, retrievable storage of spent fuel from commercial nuclear reactors and high-level waste from reprocessing that fuel, for many decades, and no insuperable scientific obstacles to permanent disposal of spent fuel or high-level waste in geologic repositories have been identified. However, there are significant institutional obstacles to developing such repositories: strong local opposition to siting and the requirement for a sustained commitment of money and skilled manpower over a period of decades. These create strong incentives to defer the political and economic costs of developing disposal facilities by using less expensive interim storage; yet continued deferral may affect the acceptability of nuclear power. Thus the principal strategic policy issue in high-level waste management is how rapidly to develop disposal facilities. Some countries plan decades of storage before choosing a repository site or a disposal technology, while the United States has enacted a law requiring operation of a geologic repository by 1998. This paper discusses waste management strategic issues and major provisions of the U.S. law, emphasizing those measures dealing with the institutional obstacles to developing geologic repositories. (author)

Use of compensation and incentives in siting low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Smith, T.P.; Jaffe, M.

1984-09-01

In discussing the use of compensation and incentives in siting low-level radioactive waste disposal facilities, chapters are devoted to: compensation and incentives in disposal facility siting (definitions and effects of compensation and incentives and siting decisions involving the use of compensation and incentives); the impacts of regional and state low-level radioactive waste facilities; the legal framework of compensation; and recommendations regarding the use of compensation

Overview of high-level waste management accomplishments

International Nuclear Information System (INIS)

Lawroski, H.; Berreth, J.R.; Freeby, W.A.

1980-01-01

Storage of power reactor spent fuel is necessary at present because of the lack of reprocessing operations particularly in the U.S. By considering the above solidification and storage scenario, there is more than reasonable assurance that acceptable, stable, low heat generation rate, solidified waste can be produced, and safely disposed. The public perception of no waste disposal solutions is being exploited by detractors of nuclear power application. The inability to even point to one overall system demonstration lends credibility to the negative assertions. By delaying the gathering of on-line information to qualify repository sites, and to implement a demonstration, the actions of the nuclear power detractors are self serving in that they can continue to point out there is no demonstration of satisfactory high-level waste disposal. By maintaining the liquid and solidified high-level waste in secure above ground storage until acceptable decay heat generation rates are achieved, by producing a compatible, high integrity, solid waste form, by providing a second or even third barrier as a compound container and by inserting the enclosed waste form in a qualified repository with spacing to assure moderately low temperature disposal conditions, there appears to be no technical reason for not progressing further with the disposal of high-level wastes and needed implementation of the complete nuclear power fuel cycle

Research on high level radioactive waste repository seismic design criteria

International Nuclear Information System (INIS)

Jing Xu

2012-01-01

Review seismic hazard analysis principle and method in site suitable assessment process of Yucca Mountain Project, and seismic design criteria and seismic design basis in primary design process. Demonstrated spatial character of seismic hazard by calculated regional seismic hazard map. Contrasted different level seismic design basis to show their differences and relation. Discussed seismic design criteria for preclosure phrase of high level waste repository and preference goal under beyond design basis ground motion. (author)

Economics model for new low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

1983-12-01

This report describes LLWECON, an interactive computer mode for evaluating financial factors involved in low-level radioactive waste disposal. The logic by which LLWECON calculates the final generator price (price per cubic foot the disposal site operator charges waste generators) is detailed. Required user input and hypothetical examples, covering sites with different capacities, and both public and private-sector development, are included

Evaluating biological transport of radionuclides at low-level waste burial sites

International Nuclear Information System (INIS)

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

1983-08-01

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

Radon levels after restoration of the U-mine disposal site

International Nuclear Information System (INIS)

Krizman, M.J.; Rojc, J.; Jovanovic, P.

2010-01-01

After cessation of the underground mining of uranium ore and production of uranium concentrate at Zirovski Vrh (Slovenia) in the period 1985-1990, two permanent surface disposal sites remained, namely, tailings pile and mine waste rock pile. Both disposal sites were of equal size of 4 hectares and were significant sources of radon. Their final restoration was designed in compliance with the condition of dose constraint for the public and authorized limits for radon exhalation from the remediated piles. In the late summer of 2008, a restoration of the mine waste pile was finished. Radon releases were reduced significantly by constructing an effective radon barrier of well compacted clay material and a thick complex protective cover layer constructed over it. Radon exhalation rate from the mine waste area was lowered from primary level of 0.7 Bq/m 2 ·s to natural levels (0.01 Bq/m 2 ·s), and consequently, ambient radon levels also decreased on the site and nearby environment. The average radon contribution from the remaining U-mine sources was estimated on the basis of the environmental measurements of radon concentrations; they dropped from initial 7-9 Bq/m 3 to approximately 3 Bq/m 3 . Further reduction of outdoor radon concentrations is expected after 2010, since the restoration of another disposal site will have been completed by the end of this year. Public exposure due to industrial radon after the first phase of restoration satisfactorily meets the dose constraint level of 0.3 mSv/y, since it decreased to less than 0.1 mSv/y. (authors)

Development of new low level radioactive waste disposal sites: A progress report

International Nuclear Information System (INIS)

Anderson, Robert T.; Antonucci, George J.; Ryan, Michael T.

1992-01-01

The status of the development of three new low level radioactive waste disposal facilities for the Central Midwest (Illinois), Southeastern (North Carolina) and Appalachian (Pennsylvania) compacts is presented. These three sites will dispose of about 50-65 percent of the commercial low-level waste (LLW) generated in the U.S. annually. Chem-Nuclear, as developer and proposed operator of all three sites has used a common approach to site development. This approach has been based on their twenty-plus years of operating experience and a standard technical approach. The technology employed is an above-grade, multiple engineered barrier design. The paper also contrasts actual progress at each site with a generalized project schedule. Areas of schedule delays are noted along with the steps being taken to accelerate schedule. Finally, we note that continued progress and timely start-up of operations of these new sites is critical on a national basis. This is due to the possibility of near-term closure of the existing LLW disposal sites. (author)

Geological evaluation of spent fuel storage and low-intermediate level radwaste disposal in the site of NPP candidate

International Nuclear Information System (INIS)

Sucipta; Yatim, S.; Martono, H.; Pudyo, A.

1997-01-01

Based on the consideration of techno-economy and environmental safety, the radioactive waste treatment installation (RWI), interim storage of spen fuel (ISSF) and low-intermediate level disposal shall be sited in the surrounding of NPP area. The land suitability of NPP's site candidate at Muria Peninsula as spent fuel storage and low-intermediate level radwaste disposal need to be studied. Site selection was conducted by overlay method and scoring method, and based on safety criteria which include geological and environmental aspects. Land evaluation by overlay method has given result a potential site which have highest suitable land at surrounding of borehole L-15 about 17.5 hectares. Land evaluation by scoring method has given result two land suitability classes, i.e. moderate suitability class (includes 14 borehole) and high suitability class, include borehole L-2, L-14 and L-15 (author)

A geotechnical evaluation of potentially acceptable sites for a high-level nuclear waste repository near the Red Lake Indian Reservation

International Nuclear Information System (INIS)

1986-01-01

The scope and work which served as the basis for this report included the following major activities; (1) A review and summary of the screening methodologies utilized by DOE for the selection of proposed nuclear waste repository sites, including a description of the inherent weakness in those methodologies. (2) A description of the geologic and hydrologic features of the rock bodies selected by DOE and an identification of those features which could result in hazardous conditions as a result of the location of a high-level nuclear waste repository. (3) An assessment of potential environmental impacts of the repository and discussion of endanged species in the proposed repository project areas. This report is organized in three major sections in relationship to the scope of work. A list of references is also included at the end of this report. 37 refs., 2 figs

Separation processes for the pretreatment of high-level nuclear wastes at the Savannah River site - 59291

International Nuclear Information System (INIS)

Hobbs, David; Peters, Thomas; Taylor-Pashow, Kathryn; Fondeur, Fernando; Nash, Charles; Fink, Samuel; Herman, David; Marra, Jim

2012-01-01

Document available in abstract form only. Full text of publication follows: Separation methods for the pretreatment of the high-level nuclear wastes (HLW) at the Savannah River Site (SRS) include the Caustic Side Solvent Extraction (CSSX) process for cesium and adsorption/ion exchange for the removal of cesium, strontium and alpha-emitting actinides. The CSSX process uses a calixarene extractant in combination with phase modifiers in a hydrocarbon diluent. Monosodium titanate (MST), a hydrous metal oxide, is the baseline material for the removal of strontium and alpha-emitting radionuclides (principally Pu-238, Pu-239, Pu-240 and Np-237). Two pretreatment facilities, the Modular Caustic Side Solvent Extraction Unit (MCU) and the Actinide Removal Process (ARP) facility began radioactive operations at SRS in 2008. Together these facilities can treat approximately 4 million liters of waste per year. The same separation processes are also planned for the much larger Salt Waste Processing Facility (SWPF). The SWPF, which has a design throughput of about 27 million liters per year, is under construction and scheduled to begin radioactive operations in 2014. Current R and D activities for the CSSX process are focused on implementing a new solvent system and stripping flowsheet that offers enhanced extraction and stripping of cesium. This next generation solvent system features a different calixarene extractant, uses caustic instead of nitric acid

Glass optimization for vitrification of Hanford Site low-level tank waste

International Nuclear Information System (INIS)

Feng, X.; Hrma, P.R.; Westsik, J.H. Jr.

1996-03-01

The radioactive defense wastes stored in 177 underground single-shell tanks (SST) and double-shell tanks (DST) at the Hanford Site will be separated into low-level and high-level fractions. One technology activity underway at PNNL is the development of glass formulations for the immobilization of the low-level tank wastes. A glass formulation strategy has been developed that describes development approaches to optimize glass compositions prior to the projected LLW vitrification facility start-up in 2005. Implementation of this strategy requires testing of glass formulations spanning a number of waste loadings, compositions, and additives over the range of expected waste compositions. The resulting glasses will then be characterized and compared to processing and performance specifications yet to be developed. This report documents the glass formulation work conducted at PNL in fiscal years 1994 and 1995 including glass formulation optimization, minor component impacts evaluation, Phase 1 and Phase 2 melter vendor glass development, liquidus temperature and crystallization kinetics determination. This report also summarizes relevant work at PNNL on high-iron glasses for Hanford tank wastes conducted through the Mixed Waste Integrated Program and work at Savannah River Technology Center to optimize glass formulations using a Plackett-Burnam experimental design

Hydrologic and geologic aspects of low-level radioactive-waste site management

International Nuclear Information System (INIS)

Cutshall, N.H.; Vaughan, N.D.; Haase, C.S.; Olsen, C.R.; Huff, D.D.

1982-01-01

Hydrologic and geologic site characterization is a critical phase in development of shallow land-burial sites for low-level radioactive-waste disposal, especially in humid environments. Structural features such as folds, faults, and bedding and textural features such as formation permeability, porosity, and mineralogy all affect the water balance and water movement and, in turn, radionuclide migration. Where these features vary over short distance scales, detailed mapping is required in order to enable accurate model predictions of site performance and to provide the basis for proper design and planning of site-disposal operations

Remediation and production of low-sludge high-level waste glasses

International Nuclear Information System (INIS)

Ramsey, W.G.; Brown, K.G.; Beam, D.C.

1994-01-01

High-level radioactive sludge will constitute 24-28 oxide weight percent of the high-level waste glass produced at the Savannah River Site. A recent melter campaign using non-radioactive, simulated feed was performed with a sludge content considerably lower than 24 percent. The resulting glass was processed and shown to have acceptable durability. However, the durability was lower than predicted by the durability algorithm. Additional melter runs were performed to demonstrate that low sludge feed could be remediated by simply adding sludge oxides. The Product Composition Control System, a computer code developed to predict the proper feed composition for production of high-level waste glass, was utilized to determine the necessary chemical additions. The methodology used to calculate the needed feed additives, the effects of sludge oxides on glass production, and the resulting glass durability are discussed

Study of the navigation methods applicable to monitoring in sites with high level of radiation

International Nuclear Information System (INIS)

Segovia de los Rios, J.A.; Rivero G, T.; Garduno G, M.; Zapata, R.

2004-01-01

In places in which high radiation levels exist is desirable to have a system that allows the realization of mensurations without the necessity of the exhibition of human resources. It is in fact in these types of situations where a robot system, or automated, in a sense but wide, it is directly applicable. So that a monitoring system, based on a mobile robot, for example, be autonomous, it is necessary to develop and to implement functional and efficient sailing algorithms that allow its use with the minimum of human intervention. Several methods exist to achieve this objective, some of them already proven and others in roads of experimentation. The present work presents some in the sailing ways but used, and specifically, the one that intends for a system of detection of flights in a place with high temperatures and high radiation levels. (Author)

High and uneven levels of 45S rDNA site-number variation across wild populations of a diploid plant genus (Anacyclus, Asteraceae).

Science.gov (United States)

Rosato, Marcela; Álvarez, Inés; Nieto Feliner, Gonzalo; Rosselló, Josep A

2017-01-01

The nuclear genome harbours hundreds to several thousand copies of ribosomal DNA. Despite their essential role in cellular ribogenesis few studies have addressed intrapopulation, interpopulation and interspecific levels of rDNA variability in wild plants. Some studies have assessed the extent of rDNA variation at the sequence and copy-number level with large sampling in several species. However, comparable studies on rDNA site number variation in plants, assessed with extensive hierarchical sampling at several levels (individuals, populations, species) are lacking. In exploring the possible causes for ribosomal loci dynamism, we have used the diploid genus Anacyclus (Asteraceae) as a suitable system to examine the evolution of ribosomal loci. To this end, the number and chromosomal position of 45S rDNA sites have been determined in 196 individuals from 47 populations in all Anacyclus species using FISH. The 45S rDNA site-number has been assessed in a significant sample of seed plants, which usually exhibit rather consistent features, except for polyploid plants. In contrast, the level of rDNA site-number variation detected in Anacyclus is outstanding in the context of angiosperms particularly regarding populations of the same species. The number of 45S rDNA sites ranged from four to 11, accounting for 14 karyological ribosomal phenotypes. Our results are not even across species and geographical areas, and show that there is no clear association between the number of 45S rDNA loci and the life cycle in Anacyclus. A single rDNA phenotype was detected in several species, but a more complex pattern that included intra-specific and intra-population polymorphisms was recorded in A. homogamos, A. clavatus and A. valentinus, three weedy species showing large and overlapping distribution ranges. It is likely that part of the cytogenetic changes and inferred dynamism found in these species have been triggered by genomic rearrangements resulting from contemporary

Coastline Mapping and Cultural Review to Predict Sea Level Rise Impact on Hawaiian Archeological Sites

Science.gov (United States)

Clinton, J.

2017-12-01

Much of Hawaii's history is recorded in archeological sites. Researchers and cultural practitioners have been studying and reconstructing significant archeological sites for generations. Climate change, and more specifically, sea level rise may threaten these sites. Our research records current sea levels and then projects possible consequences to these cultural monuments due to sea level rise. In this mixed methods study, research scientists, cultural practitioners, and secondary students use plane-table mapping techniques to create maps of coastlines and historic sites. Students compare historical records to these maps, analyze current sea level rise trends, and calculate future sea levels. They also gather data through interviews with community experts and kupuna (elders). If climate change continues at projected rates, some historic sites will be in danger of negative impact due to sea level rise. Knowing projected sea levels at specific sites allows for preventative action and contributes to raised awareness of the impacts of climate change to the Hawaiian Islands. Students will share results with the community and governmental agencies in hopes of inspiring action to minimize climate change. It will take collaboration between scientists and cultural communities to inspire future action on climate change.

Experiences from two local processes of debate and referenda on the issue of siting high level nuclear waste

International Nuclear Information System (INIS)

Drottz Sjoberg, B.M.

1998-01-01

Full text of publication follows: the paper summarizes results from two interview studies conducted in the communities of Storuman (1995) and Malaa (1997) in northern Sweden regarding whether to continue investigations of the areas for siting of a deep level repository for high level nuclear waste. Active, local participants in the work and discussions preceding each local referendum on the issue were asked to reflect on reasons and considerations related to their opinions, as well as the overall outcome for achieving a deeper understanding of the local processes. The first referendum (1995) yielded a strongly voiced rejection of continuing local investigations (72%), whereas the second (1997) referendum resulted in a marginally negative response (54%). A comparison of the results of the interview studies showed e.g. that the decision processes differed across communities, regarding both time interval and content, and that the local strategies and tactics related to the campaigns preceding the referenda differed. Among the similarities were the types of questions which remained unclear, often related to a long term perspective, e.g. risks and uncertainties regarding material reliability, access to and future safety of the repository, concern for future generations, national and international long-term decision procedures, and roles of responsibility. The discussion focuses on considerations around the issue of local vs. centralized political decisions and the tool provided by the referendum, and touches upon some issues which appeared rather paradoxical. (author)

Final report, Task 4: options for on-site management of Nuclear Fuel Services, Inc. high level waste

International Nuclear Information System (INIS)

1978-01-01

Two on-site management options for handling the NFS high-level waste were analyzed: in-tank cement solidification and perpetual tank storage of the liquid waste. The cost of converting the 8D4 plus 8D2 waste to a cementitious solid, including mixing, grout preparation, and transfer to tank 8D1 would require $3,651,000; the cost of cooling the solidified solid for 15 years, plus the cost of filling the rest of the tank space and annulus with grout, plus the cost of minimum surveillance are $10,002,000. Modification of tank 8D2 would be required; prior to transfer of the waste, tank 8D1 would also be modified for cooling of the grout mass. Estimated costs of perpetual tank storage (replacing the existing neutralized waste tank after 10 years, then transferring contents at 50-y intervals for 1000 y, with replacement of ventilation system and auxiliaries at 30-y intervals) would require a sinking fund of $11,039,000. The acidic 8D4 waste would be transferred at 50-y intervals. The sinking fund requirements are sensitive to the difference between the interest rate and the escalation rate, and also to the time assumed from present to the first tank replacement

Management and disposition of off-site laboratory-generated mixed/low level waste

International Nuclear Information System (INIS)

Fisher, D.L.

1993-10-01

The Fernald Environmental Management Project (FEMP) is the first Department of Energy (DOE) site to take back mixed and low level waste generated at commercial laboratories from chemical analyses and treatability studies on samples taken from the site. This paper discusses the steps addressed and the issues resolved in order to initiate the task of taking back mixed/low level waste. Such issues included regulatory, waste management and contractual issues

Synthetic hydrogeological study on Beishan preselected area for high-level radioactive waste repository in China

International Nuclear Information System (INIS)

Guo Yonghai; Su Rui; Ji Ruili; Wang Hailong; Liu Shufen; Zong Zihua; Dong Jiannan; Zhang Ming

2014-01-01

On the basis of large scale field hydrogeological investigation, synthetic hydrogeological studies related to groundwater system characteristics, permeability of rock bodies, groundwater dynamic, hydrogeochemistry, isotopic hydrology, CFC's of groundwater and groundwater flow field simulation were carried out for Beishan area, Gansu province. According to analysis on a large amount of hydrogeological data, the characteristics of groundwater circulation, groundwater hydrodynamics and hydrgeochemistry were described and the suitability of Beishan area as the potential area of high-level radioactive waste disposal was evaluated in the paper. Through this study, the hydrogeological study and evaluation methods in the siting of China's high level radioactive waste repository were set up. Furthermore, the important hydrogeological scientific evidence was provided for optimal site filtration of China's high-level radioactive waste repository in Beishan area. (authors)

The siting dilemma: Low-level radioactive waste disposal in the United States

International Nuclear Information System (INIS)

English, M.R.

1991-01-01

The 1980 Low-Level Radioactive Waste Policy Act ushered in a new era in low-level waste disposal; one with vastly increased state responsibilities. By a 1985 amendment, states were given until January 1993 to fulfill their mandate. In this dissertation, their progress is reviewed. The focus then turns to one particularly intractable problem: that of finding technically and socially acceptable sites for new disposal facilities. Many lament the difficulty of siting facilities that are intended to benefit the public at large but are often locally unwanted. Many label local opposition as purely self-interested; as simply a function of the NIMBY (Not In My Backyard) syndrome. Here, it is argued that epithets such as NIMBY are unhelpful. Instead, to lay the groundwork for widely acceptable solutions to siting conflicts, deeper understanding is needed of differing values on issues concerning authority, trust, risk, and justice. This dissertation provides a theoretical and practical analysis of those issues as they pertain to siting low-level waste disposal facilities and, by extension, other locally unwanted facilities

Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

International Nuclear Information System (INIS)

Wodrich, D.D.

1996-01-01

This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

Canadian high-level radioactive waste management system issues

International Nuclear Information System (INIS)

Allan, C.J.; Gray, B.R.

1992-01-01

In Canada responsibility for the management of radioactive wastes rests with the producer of those wastes. This fundamental principle applies to such diverse wastes as uranium mine and mill tailings, low-level wastes from universities and hospitals, wastes produced at nuclear research establishments, and wastes produced at nuclear generating stations. The federal government has accepted responsibility for historical wastes for which the original producer can no longer be held accountable. Management of radioactive wastes is subject to the regulatory control of the Atomic Energy Control Board, the federal agency responsible for regulating the nuclear industry. In this paper the authors summarize the current situation concerning the management of high level (used nuclear fuel) wastes. In 1981 the two governments also announced that selection of a disposal site would not proceed, and responsibility for site selection and operation would not be assigned until the Concept for used fuel disposal had been reviewed and assessed. Thus the concept assessment is generic rather than site specific. The Concept that has been developed has been designed to conform with safety and performance criteria established by the Atomic Energy Control Board. It is based on burial deep in plutonic rock of the Canadian Shield, using a multi-barrier approach with a series of engineered and natural barriers: these include the waste form, container, buffer and backfill, and the host rock

Use of compensation and incentives in siting low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

1985-04-01

This report assumes that local opposition is a critical issue in siting low-level radioactive waste disposal facilities. Although it recognizes the importance of local health and safety concerns, this report only addresses the economic issues facing local officials in the siting process. Finding ways to overcome local opposition through economic compensation and incentives is a basic step in the waste facility siting process. The report argues that the use of these compensation and incentive mechanisms can help achieve greater local acceptance of waste facilities and also help ease the economic burdens that many communities bear when they agree to host a low-level waste disposal facility. The growing national need for low-level radioactive waste disposal facilities requires that state and local planning agencies develop creative new procedures for siting facilities, procedures that are sensitive to local perceptions and effects

Pilot scale processing of simulated Savannah River Site high level radioactive waste

International Nuclear Information System (INIS)

Hutson, N.D.; Zamecnik, J.R.; Ritter, J.A.; Carter, J.T.

1991-01-01

The Savannah River Laboratory operates the Integrated DWPF Melter System (IDMS), which is a pilot-scale test facility used in support of the start-up and operation of the US Department of Energy's Defense Waste Processing Facility (DWPF). Specifically, the IDMS is used in the evaluation of the DWPF melter and its associated feed preparation and offgass treatment systems. This article provides a general overview of some of the test work which has been conducted in the IDMS facility. The chemistry associated with the chemical treatment of the sludge (via formic acid adjustment) is discussed. Operating experiences with simulated sludge containing high levels of nitrite, mercury, and noble metals are summarized

In-situ nitrite analysis in high level waste tanks

International Nuclear Information System (INIS)

O'Rourke, P.E.; Prather, W.S.; Livingston, R.R.

1992-01-01

The Savannah River Site produces special nuclear materials used in the defense of the United States. Most of the processes at SRS are primarily chemical separations and purifications. In-situ chemical analyses help improve the safety, efficiency and quality of these operations. One area where in situ fiberoptic spectroscopy can have a great impact is the management of high level radioactive waste. High level radioactive waste at SRS is stored in more than 50 large waste tanks. The waste exists as a slurry of nitrate salts and metal hydroxides at pH's higher than 10. Sodium Nitrite is added to the tanks as a corrosion inhibitor. In-situ fiberoptic probes are being developed to measure the nitrate, nitrite and hydroxide concentrations in both liquid and solid fractions. Nitrite levels can be measured between 0.01M and 1M in a 1mm pathlength optical cell

Exposure to unusually high indoor radon levels

International Nuclear Information System (INIS)

Rasheed, F.N.

1993-01-01

Unusually high indoor radon concentrations were reported in a small village in western Tyrol, Austria. The authors have measured the seasonal course of indoor radon concentrations in 390 houses of this village. 71% of houses in winter and 33% in summer, showed radon values on the ground floor above the Austrian action level of 400 Bq/cm 3 . This proportion results in an unusually high indoor radon exposure of the population. The radon source was an 8,700-year-old rock slide of granite gneiss, the largest of the alpine crystalline rocks. It has a strong emanating power because its rocks are heavily fractured and show a slightly increased uranium content. Previous reports show increased lung cancer mortality, myeloid leukemia, kidney cancer, melanoma, and prostate cancer resulting from indoor radon exposure. However, many studies fail to provide accurate information on indoor radon concentrations, classifying them merely as low, intermediate, and high, or they record only minor increases in indoor radon concentrations. Mortality data for 1970-91 were used to calculate age and sex standardized mortality rates (SMR) for 51 sites of carcinoma. The total population of Tyrol were controls. A significantly higher risk was recorded for lung cancer. The high SMR for lung cancer in female subjects is especially striking. Because the numbers were low for the other cancer sites, these were combined in one group to calculate the SMR. No significant increase in SMR was found for this group

High-level verification

CERN Document Server

Lerner, Sorin; Kundu, Sudipta

2011-01-01

Given the growing size and heterogeneity of Systems on Chip (SOC), the design process from initial specification to chip fabrication has become increasingly complex. This growing complexity provides incentive for designers to use high-level languages such as C, SystemC, and SystemVerilog for system-level design. While a major goal of these high-level languages is to enable verification at a higher level of abstraction, allowing early exploration of system-level designs, the focus so far for validation purposes has been on traditional testing techniques such as random testing and scenario-based

Building arrangement and site layout design guides for on site low level radioactive waste storage facilities

International Nuclear Information System (INIS)

McMullen, J.W.; Feehan, M.J.

1986-01-01

Many papers have been written by AE's and utilities describing their onsite storage facilities, why they are needed, NRC regulations, and disposal site requirements. This paper discusses a typical storage facility and address the design considerations and operational aspects that are generally overlooked when designing and siting a low level radioactive waste storage facility. Some topics to be addressed are: 1. Container flexibility; 2. Modular expansion capabilities; 3. DOT regulations; 4. Meterological requirements; 5. OSHA; 6. Fire protection; 7. Floods; 8. ALARA

Storage of High Level Nuclear Waste in Germany

Directory of Open Access Journals (Sweden)

Dietmar P. F. Möller

2007-01-01

Full Text Available Nuclear energy is very often used to generate electricity. But first the energy must be released from atoms what can be done in two ways: nuclear fusion and nuclear fission. Nuclear power plants use nuclear fission to produce electrical energy. The electrical energy generated in nuclear power plants does not produce polluting combustion gases but a renewable energy, an important fact that could play a key role helping to reduce global greenhouse gas emissions and tackling global warming especially as the electricity energy demand rises in the years ahead. This could be assumed as an ideal win-win situation, but the reverse site of the medal is that the production of high-level nuclear waste outweighs this advantage. Hence the paper attempt to highlight the possible state-of-art concepts for the safe and sustaining storage of high-level nuclear waste in Germany.

The disposal of high level radioactive wastes. Proposed solutions and uses in Brazil

International Nuclear Information System (INIS)

Toledo, J.F.A.

1992-06-01

The characteristics of high level radioactive waste produced in nuclear plants similar to that used in Brazil is presented. Subsequently it is described the international experience, and the way to apply such knowledge to the Brazilian situation, defining the magnitude of the problem, applying a methodology to select sites, and choosing areas for the location of a repository. Once such areas are defined, it is presented the behaviour of rock mass, similar to those found in the brazilian territory, based on the requirements for a high radioactive waste repository site. Finally, two Projects are presented for countries with lithologies similar to that of Brazil. The first one is choosing sites for a high radioactive waste repository program, and the second is an investigation of rock mass responses program. (author)

Suggestions on R and D work of high-level radioactive waste disposal in China

International Nuclear Information System (INIS)

Xu Guoqing

2012-01-01

The difference between repository and generic underground facilities is described. Some differences and similarities of site selection between the low and medium radioactive waste disposal, nuclear power station and high-level radioactive waste repository are also discussed here. We trend to extremely emphasize the safety of high-level radioactive waste disposal because of high toxicity, long half-life and long safety disposal period of this kind of radioactive wastes; because radioactive waste in the repository is of high specific activities and buried in depth, it would be difficult to meddle with its safety. In case of repository system being destroyed, the author considers that in the stages of regional and area site selection, the first task is to investigate regional tectonic stability. Some problems about disposal options and others are also discussed in this paper. (author)

Status of the high-level nuclear waste disposal program in Japan

International Nuclear Information System (INIS)

Uematsu, K.

1985-01-01

The Japan Atomic Energy Commission (JAEC) initiated a high-level radioactive waste disposal program in 1976. Since then, the Advisory Committee on Radioactive Waste Management of JAEC has revised the program twice. The latest revision was issued in 1984. The committee recommended a four-phase program and the last phase calls for the beginning of emplacement of the high-level nuclear waste into a selected repository in the Year 2000. The first phase is already completed, and the second phase of this decade calls for the selection of a candidate disposal site and the conducting of the RandD of waste disposal in an underground research laboratory and in a hot test facility. This paper covers the current status of the high-level nuclear waste disposal program in Japan

Glomeromycota communities survive extreme levels of metal toxicity in an orphan mining site.

Science.gov (United States)

Sánchez-Castro, I; Gianinazzi-Pearson, V; Cleyet-Marel, J C; Baudoin, E; van Tuinen, D

2017-11-15

Abandoned tailing basins and waste heaps of orphan mining sites are of great concern since extreme metal contamination makes soil improper for any human activity and is a permanent threat for nearby surroundings. Although spontaneous revegetation can occur, the process is slow or unsuccessful and rhizostabilisation strategies to reduce dispersal of contaminated dust represent an option to rehabilitate such sites. This requires selection of plants tolerant to such conditions, and optimization of their fitness and growth. Arbuscular mycorrhizal fungi (AMF) can enhance metal tolerance in moderately polluted soils, but their ability to survive extreme levels of metal contamination has not been reported. This question was addressed in the tailing basin and nearby waste heaps of an orphan mining site in southern France, reaching in the tailing basin exceptionally high contents of zinc (ppm: 97,333 total) and lead (ppm: 31,333 total). In order to contribute to a better understanding of AMF ecology under severe abiotic stress and to identify AMF associated with plants growing under such conditions, that may be considered in future revegetation and rhizostabilisation of highly polluted areas, nine plant species were sampled at different growing seasons and AMF root colonization was determined. Glomeromycota diversity was monitored in mycorrhizal roots by sequencing of the ribosomal LSU. This first survey of AMF in such highly contaminated soils revealed the presence of several AMF ribotypes, belonging mainly to the Glomerales, with some examples from the Paraglomerales and Diversisporales. AMF diversity and root colonization in the tailing basin were lower than in the less-contaminated waste heaps. A Paraglomus species previously identified in a polish mining site was common in roots of different plants. Presence of active AMF in such an environment is an outstanding finding, which should be clearly considered for the design of efficient rhizostabilisation processes

Environmental-pathways analysis for evaluation of a low-level waste disposal site

International Nuclear Information System (INIS)

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

1983-01-01

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

Environmental pathways analysis for evaluation of a low-level waste disposal site

International Nuclear Information System (INIS)

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

1984-01-01

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

High-level waste program integration within the DOE complex

International Nuclear Information System (INIS)

Valentine, J.H.; Malone, K.; Schaus, P.S.

1998-03-01

Eleven major Department of Energy (DOE) site contractors were chartered by the Assistant Secretary to use a systems engineering approach to develop and evaluate technically defensible cost savings opportunities across the complex. Known as the complex-wide Environmental Management Integration (EMI), this process evaluated all the major DOE waste streams including high level waste (HLW). Across the DOE complex, this waste stream has the highest life cycle cost and is scheduled to take until at least 2035 before all HLW is processed for disposal. Technical contract experts from the four DOE sites that manage high level waste participated in the integration analysis: Hanford, Savannah River Site (SRS), Idaho National Engineering and Environmental Laboratory (INEEL), and West Valley Demonstration Project (WVDP). In addition, subject matter experts from the Yucca Mountain Project and the Tanks Focus Area participated in the analysis. Also, departmental representatives from the US Department of Energy Headquarters (DOE-HQ) monitored the analysis and results. Workouts were held throughout the year to develop recommendations to achieve a complex-wide integrated program. From this effort, the HLW Environmental Management (EM) Team identified a set of programmatic and technical opportunities that could result in potential cost savings and avoidance in excess of $18 billion and an accelerated completion of the HLW mission by seven years. The cost savings, schedule improvements, and volume reduction are attributed to a multifaceted HLW treatment disposal strategy which involves waste pretreatment, standardized waste matrices, risk-based retrieval, early development and deployment of a shipping system for glass canisters, and reasonable, low cost tank closure

Selection of candidate canister materials for high-level nuclear waste containment in a tuff repository

International Nuclear Information System (INIS)

McCright, R.D.; Weiss, H.; Juhas, M.C.; Logan, R.W.

1983-11-01

A repository located at Yucca Mountain at the Nevada Test Site is a potential site for permanent geological disposal of high-level nuclear waste. The repository can be located in a horizon in welded tuff, a volcanic rock, which is above the static water level at this site. The environmental conditions in this unsaturated zone are expected to be air and water vapor dominated for much of the containment period. Type 304L stainless steel is the reference material for fabricating canisters to contain the solid high-level wastes. Alternative stainless alloys are considered because of possible susceptibility of 304L to localized and stress forms of corrosion. For the reprocessed glass wastes, the canisters serve as the recipient for pouring the glass with the result that a sensitized microstructure may develop because of the times at elevated temperatures. Corrosion testing of the reference and alternative materials has begun in tuff-conditioned water and steam environments. 21 references, 8 figures, 8 tables

Siting of a low-level radioactive waste management facility - environmental assessment experiences of the Canadian siting task force

International Nuclear Information System (INIS)

Gorber, D.M.; Story, V.A.

1995-01-01

After public opposition to the plans for a low-level radioactive waste facility at one of two candidate areas at Port Hope, Canada the Environmental Assessment process was postponed, and an independent Siting Process Task Force was set-up to assess the most suitable technologies for LLRW disposal, the areas with the best potential in the province to use these technologies, and the most promising approaches to site selection. The Task Force recommended a five-phased siting process known as the 'Co-operative Siting Process', which was based on the voluntary participation of local communities and a collaborative, joint-planning style of decision making. An independent Siting Task Force was to be established to ensure that the principles of the recommended process was upheld. This siting process is still underway, and problems and successes that have been encountered are summarized in this contribution

China's deep geological disposal program for high level radioactive waste, background and status 1998

International Nuclear Information System (INIS)

Ju Wang; Xu Guoqing; Guo Yonghai

2001-01-01

This paper presents the background and progress made in the study of China's high level radioactive waste, including site screening, site evaluation, the study on radionuclide migration, bentonite, natural analogue studies, and performance assessment, etc. The study on Beishan area, the potential area for China's geological repository, is also presented in this paper. (author)

Non-radiological air quality modeling for the high-level waste tank closure environmental impact statement

International Nuclear Information System (INIS)

Hunter, C.H.

2000-01-01

Dispersion modeling of potential non-radiological air emissions associated with the proposed closure of high-level waste (HLW) tanks at the Savannah River Site has been completed, as requested (TtNUS, 1999). Estimated maximum ground-level concentrations of applicable regulated air pollutants at the site boundary and at the distance to the co-located onsite worker (640 meters) are summarized. In all cases, the calculated concentrations were much less than regulatory standards

Environmental plutonium levels near the Nevada Test Site

International Nuclear Information System (INIS)

Bliss, W.A.; Jakubowski, F.M.

1977-01-01

The Environmental Monitoring and Support Laboratory-Las Vegas is engaged in a study to define the distribution of plutonium in the environment surrounding the Nevada Test Site (NTS). Extensive soil sampling has been conducted around the NTS, both to define areal distribution and to investigate local concentrating effects by natural phenomena. Additionally, air filters used in the off-NTS air surveillance network as well as those collected in special studies have been analyzed for plutonium to better define ambient levels and to investigate the possibility of resuspension. Results of these, as well as other studies related to defining the ambient plutonium levels around the NTS, are given in this report

The Michigan high-level radioactive waste program: Final technical progress report

International Nuclear Information System (INIS)

1987-01-01

This report comprises the state of Michigan's final technical report on the location of a proposed high-level radioactive waste disposal site. Included are a list of Michigan's efforts to review the DOE proposal and a detailed report on the application of geographic information systems analysis techniques to the review process

Efficient handling of high-level radioactive cell waste in a vitrification facility analytical laboratory

International Nuclear Information System (INIS)

Roberts, D.W.; Collins, K.J.

1998-01-01

The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, South Carolina, is the world''s largest and the United State''s first high level waste vitrification facility. For the past 1.5 years, DWPF has been vitrifying high level radioactive liquid waste left over from the Cold War. The vitrification process involves the stabilization of high level radioactive liquid waste into borosilicate glass. The glass is contained in stainless steel canisters. DWPF has filled more than 200 canisters 3.05 meters (10 feet) long and 0.61 meters (2 foot) diameter. Since operations began at DWPF in March of 1996, high level radioactive solid waste continues to be generated due to operating the facility''s analytical laboratory. The waste is referred to as cell waste and is routinely removed from the analytical laboratories. Through facility design, engineering controls, and administrative controls, DWPF has established efficient methods of handling the high level waste generated in its laboratory facility. These methods have resulted in the prevention of undue radiation exposure, wasted man-hours, expenses due to waste disposal, and the spread of contamination. This level of efficiency was not reached overnight, but it involved the collaboration of Radiological Control Operations and Laboratory personnel working together to devise methods that best benefited the facility. This paper discusses the methods that have been incorporated at DWPF for the handling of cell waste. The objective of this paper is to provide insight to good radiological and safety practices that were incorporated to handle high level radioactive waste in a laboratory setting

Application of the Spanish methodological approach for biosphere assessment to a generic high-level waste disposal site

International Nuclear Information System (INIS)

Agueero, A.; Pinedo, P.; Simon, I.; Cancio, D.; Moraleda, M.; Trueba, C.; Perez-Sanchez, D.

2008-01-01

A methodological approach which includes conceptual developments, methodological aspects and software tools have been developed in the Spanish context, based on the BIOMASS 'Reference Biospheres Methodology'. The biosphere assessments have to be undertaken with the aim of demonstrating compliance with principles and regulations established to limit the possible radiological impact of radioactive waste disposals on human health and on the environment, and to ensure that future generations will not be exposed to higher radiation levels than those that would be acceptable today. The biosphere in the context of high-level waste disposal is defined as the collection of various radionuclide transfer pathways that may result in releases into the surface environment, transport within and between the biosphere receptors, exposure of humans and biota, and the doses/risks associated with such exposures. The assessments need to take into account the complexity of the biosphere, the nature of the radionuclides released and the long timescales considered. It is also necessary to make assumptions related to the habits and lifestyle of the exposed population, human activities in the long term and possible modifications of the biosphere. A summary on the Spanish methodological approach for biosphere assessment are presented here as well as its application in a Spanish generic case study. A reference scenario has been developed based on current conditions at a site located in Central-West Spain, to indicate the potential impact to the actual population. In addition, environmental change has been considered qualitatively through the use of interaction matrices and transition diagrams. Unit source terms of 36 Cl, 79 Se, 99 Tc, 129 I, 135 Cs, 226 Ra, 231 Pa, 238 U, 237 Np and 239 Pu have been taken. Two exposure groups of infants and adults have been chosen for dose calculations. Results are presented and their robustness is evaluated through the use of uncertainty and sensitivity

Application of the Spanish methodological approach for biosphere assessment to a generic high-level waste disposal site.

Science.gov (United States)

Agüero, A; Pinedo, P; Simón, I; Cancio, D; Moraleda, M; Trueba, C; Pérez-Sánchez, D

2008-09-15

A methodological approach which includes conceptual developments, methodological aspects and software tools have been developed in the Spanish context, based on the BIOMASS "Reference Biospheres Methodology". The biosphere assessments have to be undertaken with the aim of demonstrating compliance with principles and regulations established to limit the possible radiological impact of radioactive waste disposals on human health and on the environment, and to ensure that future generations will not be exposed to higher radiation levels than those that would be acceptable today. The biosphere in the context of high-level waste disposal is defined as the collection of various radionuclide transfer pathways that may result in releases into the surface environment, transport within and between the biosphere receptors, exposure of humans and biota, and the doses/risks associated with such exposures. The assessments need to take into account the complexity of the biosphere, the nature of the radionuclides released and the long timescales considered. It is also necessary to make assumptions related to the habits and lifestyle of the exposed population, human activities in the long term and possible modifications of the biosphere. A summary on the Spanish methodological approach for biosphere assessment are presented here as well as its application in a Spanish generic case study. A reference scenario has been developed based on current conditions at a site located in Central-West Spain, to indicate the potential impact to the actual population. In addition, environmental change has been considered qualitatively through the use of interaction matrices and transition diagrams. Unit source terms of (36)Cl, (79)Se, (99)Tc, (129)I, (135)Cs, (226)Ra, (231)Pa, (238)U, (237)Np and (239)Pu have been taken. Two exposure groups of infants and adults have been chosen for dose calculations. Results are presented and their robustness is evaluated through the use of uncertainty and

Disposal of low-level radioactive waste at the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Sauls, V.W. [Dept. of Energy, Aiken, SC (United States). Savannah River Field Office

1993-03-01

An important objective of the Savannah River Site`s low-level radioactive waste management program is to isolate the waste from the environment both now and well into the future. A key element in achieving this is the disposal of low-level radioactive waste in sealed concrete vaults. Historically the Site has disposed of low-level radioactive waste via shallow land burial. In 1987, it was decided that better isolation from the environment was required. At that time several options for achieving this isolation were studied and below grade concrete vaults were chosen as the best method. This paper discusses the performance objectives for the vaults, the current design of the vaults and plans for the design of future vaults, the cost to construct the vaults, and the performance assessment on the vaults. Construction of the first set of vaults is essentially complete and readiness reviews before the start of waste receipt are being performed. Startup is to begin late in calendar year 1992 and continue through early CY 1993. The performance assessment is under way and the first draft is to be completed in early 1993.

Willow yield is highly dependent on clone and site

DEFF Research Database (Denmark)

Ugilt Larsen, Søren; Jørgensen, Uffe; Lærke, Poul Erik

2014-01-01

Use of high-yielding genotypes is one of the means to achieve high yield and profitability in willow (Salix spp.) short rotation coppice. This study investigated the performance of eight willow clones (Inger, Klara, Linnea, Resolution, Stina, Terra Nova, Tora, Tordis) on five Danish sites......, differing considerably in soil type, climatic conditions and management. Compared to the best clone, the yield was up to 36 % lower for other clones across sites and up to 51 % lower within sites. Tordis was superior to other clones with dry matter yields between 5.2 and 10.2 Mg ha−1 year−1 during the first...... 3-year harvest rotation, and it consistently ranked as the highest yielding clone on four of the five sites and not significantly lower than the highest yielding clone on the fifth site. The ranking of the other clones was more dependent on site with significant interaction between clone and site...

Long-term high-level waste technology. Composite quarterly technical report, October-December 1979

International Nuclear Information System (INIS)

Cornman, W.R.

1980-06-01

This document summarizes work for the immobilization of high-level radioactive wastes from the chemical reprocessing of nuclear reactor fuels. The progress is reported in two main areas: site technology, and alternative waste form development

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

International Nuclear Information System (INIS)

2010-01-01

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Programs

2010-10-04

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

New treatment facility for low level process effluents at the Savannah River site

International Nuclear Information System (INIS)

Ebra, M.A.; Bibler, J.P.; Johnston, B.S.; Kilpatrick, L.L.; Poy, F.L.; Wallace, R.M.

1987-01-01

A new facility, the F/H Effluent Treatment Facility (F/H ETF) is under construction at the Savannah River site. It will decontaminate process effluents containing low levels of radionuclides and hazardous chemicals prior to discharge to a surface stream. These effluents, which are currently discharged to seepage basins, originate in the chemical separations and high-level radioactive waste processing areas, known as F-Area and H-Area. The new facility will allow closure of the basins in order to meet the provisions of the Resource Conservation and Recovery Act by November 1988. A high degree of reliability is expected from this design as a result of extensive process development work that has been conducted at the Savannah River Laboratory. This work has included both bench scale testing of individual unit operations and pilot scale testing of an integrated facility, 150 to 285 L/min (40 to 75 gpm), that contains the major operations

Low-level radioactive waste facility siting in the Rocky Mountain compact region

International Nuclear Information System (INIS)

Whitman, M.

1983-09-01

The puprose of the Rocky Mountain Low-Level Radioactive Waste Compact is to develop a regional management system for low-level waste (LLW) generated in the six states eligible for membership: Arizona, Colorado, Nevada, New Mexico, Utah and Wyoming. Under the terms of the compact, any party state generating at least 20% of the region's waste becomes responsible for hosting a regional LLW management facility. However, the compact prescribes no system which the host state must follow to develop a facility, but rather calls on the state to fulfill its responsibility through reliance on its own laws and regulations. Few of the Rocky Mountain compact states have legislation dealing specifically with LLW facility siting. Authority for LLW facility siting is usually obtained from radiation control statutes and solid or hazardous waste statutes. A state-by-state analysis of the siting authorities of each of the Rock Mountain compact states as they pertain to LLW disposal facility siting is presented. Siting authority for LLW disposal facilities in the Rocky Mountain compact region runs from no authority, as in Wyoming, to general statutory authority for which regulations would have to be promulgated, as in Arizona and Nevada, to more detailed siting laws, as in Colorado and New Mexico. Barring an amendment to, or different interpretation of, the Utah Hazardous Waste Facility Siting Act, none of the Rocky Mountain States' LLW facility siting authorities preempt local veto authorities

High-level nuclear waste disposal

International Nuclear Information System (INIS)

Burkholder, H.C.

1985-01-01

The meeting was timely because many countries had begun their site selection processes and their engineering designs were becoming well-defined. The technology of nuclear waste disposal was maturing, and the institutional issues arising from the implementation of that technology were being confronted. Accordingly, the program was structured to consider both the technical and institutional aspects of the subject. The meeting started with a review of the status of the disposal programs in eight countries and three international nuclear waste management organizations. These invited presentations allowed listeners to understand the similarities and differences among the various national approaches to solving this very international problem. Then seven invited presentations describing nuclear waste disposal from different perspectives were made. These included: legal and judicial, electric utility, state governor, ethical, and technical perspectives. These invited presentations uncovered several issues that may need to be resolved before high-level nuclear wastes can be emplaced in a geologic repository in the United States. Finally, there were sixty-six contributed technical presentations organized in ten sessions around six general topics: site characterization and selection, repository design and in-situ testing, package design and testing, disposal system performance, disposal and storage system cost, and disposal in the overall waste management system context. These contributed presentations provided listeners with the results of recent applied RandD in each of the subject areas

Overview of Low-Level Waste Disposal Operations at the Nevada Test Site

International Nuclear Information System (INIS)

2007-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Environmental Management Program is charged with the responsibility to carry out the disposal of on-site and off-site generated low-level radioactive waste at the Nevada Test Site. Core elements of this mission are ensuring that disposal take place in a manner that is safe and cost-effective while protecting workers, the public, and the environment. This paper focuses on giving an overview of the Nevada Test Site facilities regarding currant design of disposal. In addition, technical attributes of the facilities established through the site characterization process will be further described. An update on current waste disposal volumes and capabilities will also be provided. This discussion leads to anticipated volume projections and disposal site requirements as the Nevada Test Site disposal operations look towards the future

Radon levels at the rehabilitated Nabarlek mine site

International Nuclear Information System (INIS)

Tims, S.; Ryan, B.; Martin, P.

1998-01-01

Full text: A high sensitivity radon monitor has now been in continuous operation at the Nabarlek mine site for several months. The pit area can be viewed as a single, extended radon source, which can be used to assess the validity of radon dispersal predictions. The data have been recorded simultaneously with a variety of meteorological parameters, with a view to using correlations between the data sets as a guide for the improvement of dispersion model inputs. The sensitivity of radon concentration to selected parameters will be discussed, as will the future of the study which aims to make additional simultaneous radon measurements at selected locations around the mine site

Study of site layout in the Rokkasho site

International Nuclear Information System (INIS)

Sato, Kazuyoshi; Tamura, Kousaku; Yagenji, Akira; Sekiya, Shigeki; Takahashi, Hideo; Neyatani, Yuzuru; Uehara, Masaharu; Motohashi, Keiichi; Hashimoto, Masayoshi; Ogino, Shunji; Nagamatsu, Nobuhide

2006-03-01

The Final Design Report (FDR) of the International Thermonuclear Experimental Reactor (ITER) was published on July 2001 as a summary of the Engineering Design Activity (EDA). After the EDA, site dependent design has been investigated for the invitation of ITER toward Rokkasho Site (Iyasakadai area) in Aomori prefecture. This report describes the results of site layout of major buildings and structures of ITER in the Rokkasho-Site. The data of the ground near the site and the results of site dependent design in Japan were applied to this study. Through this study, the most appropriate site layout has been constructed with satisfaction of following conditions. (1) Bedrock level at the tokamak complex building is relatively high and it can be reduced the cost of excavation and foundation work. (2) Total amount of excavation soil for site preparation is minimized and the flexibility of the layout is ensured with flat ground level. (3) Accessibility of human and equipments, reduction of noise and vibration to the environment can be obtained. Total length of ducts and piping between buildings in site is minimized. (author)

Soil characterization methods for unsaturated low-level waste sites

International Nuclear Information System (INIS)

Wierenga, P.J.; Young, M.H.; Hills, R.G.

1993-01-01

To support a license application for the disposal of low-level radioactive waste (LLW), applicants must characterize the unsaturated zone and demonstrate that waste will not migrate from the facility boundary. This document provides a strategy for developing this characterization plan. It describes principles of contaminant flow and transport, site characterization and monitoring strategies, and data management. It also discusses methods and practices that are currently used to monitor properties and conditions in the soil profile, how these properties influence water and waste migration, and why they are important to the license application. The methods part of the document is divided into sections on laboratory and field-based properties, then further subdivided into the description of methods for determining 18 physical, flow, and transport properties. Because of the availability of detailed procedures in many texts and journal articles, the reader is often directed for details to the available literature. References are made to experiments performed at the Las Cruces Trench site, New Mexico, that support LLW site characterization activities. A major contribution from the Las Cruces study is the experience gained in handling data sets for site characterization and the subsequent use of these data sets in modeling studies

Thermal analysis of Yucca Mountain commercial high-level waste packages

International Nuclear Information System (INIS)

Altenhofen, M.K.; Eslinger, P.W.

1992-10-01

The thermal performance of commercial high-level waste packages was evaluated on a preliminary basis for the candidate Yucca Mountain repository site. The purpose of this study is to provide an estimate for waste package component temperatures as a function of isolation time in tuff. Several recommendations are made concerning the additional information and modeling needed to evaluate the thermal performance of the Yucca Mountain repository system

Nuclear waste. DOE's program to prepare high-level radioactive waste for final disposal

International Nuclear Information System (INIS)

Bannerman, Carl J.; Owens, Ronald M.; Dowd, Leonard L.; Herndobler, Christopher S.; Purvine, Nancy R.; Stenersen, Stanley G.

1989-11-01

In summary, as of December 1988, the four sites collectively stored about 95 million gallons of high-level waste in underground tanks and bins. Approximately 57 million gallons are stored at Hanford, 34 million gallons at Savannah River, 3 million gallons at INEL, and 6 million gallons at West Valley. The waste is in several forms, including liquid, sludge, and dry granular materials, that make it unsuitable for permanent storage in its current state at these locations. Leaks from the tanks, designed for temporary storage, can pose an environmental hazard to surrounding land and water for thousands of years. DOE expects that when its waste processes at Savannah River, West Valley, and Hanford become operational, the high-level radioactive waste stored at these sites will be blended with other materials to immobilize it by forming a glass-like substance. The glass form will minimize the risk of environmental damage and make the waste more acceptable for permanent disposal in a geologic repository. At INEL, DOE is still considering various other immobilization and permanent disposal approaches. In July 1989, DOE estimated that it would cost about $13 billion (in fiscal year 1988 dollars) to retrieve, process, immobilize, and store the high-level waste until it can be moved to a permanent disposal site: about $5.3 billion is expected to be spent at Savannah River, $0.9 billion at West Valley, $2.8 billion at Hanford, and $4.0 billion at INEL. DOE has started construction at Savannah River and West Valley for facilities that will be used to transform the waste into glass (a process known as vitrification). These sites have each encountered schedule delays, and one has encountered a significant cost increase over earlier estimates. More specifically, the Savannah River facility is scheduled to begin high-level waste vitrification in 1992; the West Valley project, based on a January 1989 estimate, is scheduled to begin high-level waste vitrification in 1996, about 8

Nondestructive examination of DOE high-level waste storage tanks

International Nuclear Information System (INIS)

Bush, S.; Bandyopadhyay, K.; Kassir, M.; Mather, B.; Shewmon, P.; Streicher, M.; Thompson, B.; van Rooyen, D.; Weeks, J.

1995-01-01

A number of DOE sites have buried tanks containing high-level waste. Tanks of particular interest am double-shell inside concrete cylinders. A program has been developed for the inservice inspection of the primary tank containing high-level waste (HLW), for testing of transfer lines and for the inspection of the concrete containment where possible. Emphasis is placed on the ultrasonic examination of selected areas of the primary tank, coupled with a leak-detection system capable of detecting small leaks through the wall of the primary tank. The NDE program is modelled after ASME Section XI in many respects, particularly with respects to the sampling protocol. Selected testing of concrete is planned to determine if there has been any significant degradation. The most probable failure mechanisms are corrosion-related so that the examination program gives major emphasis to possible locations for corrosion attack

Geological factors of disposal site selection for low-and intermediate-level solid radwastes in China

International Nuclear Information System (INIS)

Chen Zhangru

1993-01-01

For disposal of low- and intermediate-level solid radioactive wastes, shallow-ground disposal can provide adequate isolation of waste from human for a fairly long period of time. The objective of disposal site selection is to ensure that the natural properties of the site together with the engineered barrier site shall provide adequate isolation of radionuclides from the human beings and environment, so the whole disposal system can keep the radiological impact within an acceptable level. Since the early 1980's, complying with the national standards and the expert's conception as well as the related IAEA Criteria, geological selection of disposal sites for low-and intermediate-level solid radwastes has been carried out in East China, South China, Northwest China and Southwest China separately. Finally, 5 candidate sites were recommended to the CNNC

Evaluation of a high-level waste radiological maintenance facility

International Nuclear Information System (INIS)

Collins, K.J.

1998-01-01

The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation''s first and world''s largest high level waste vitrification facility. DWPF began, operations in March 1996 to process radioactive waste, consisting of a matrixed predominantly 137 Cs precipitate and a predominately 90 Sr and alpha emitting sludge, into boro-silicate glass for long term storage. Presently, DWPF is processing only sludge waste and is preparing to process a combination of sludge and precipitate waste. During precipitate operations, canister dose rates are expected to exceed 10 Sv hr -1 (1000 rem hr -1 ). In sludge-only operations, canister contact gamma dose rates are approximately 15 mSv hr -1 (1500 mrem hr -1 ). Transferable contamination levels have been greater than 10 mSv hr -1 (100 cm 2 ) -1 for beta-gamma emitters and into the millions of Bq (100 cm 2 ) -1 for the alpha emitting radionuclides. This paper presents an evaluation of the radiological maintenance areas and their ability to support radiological work

Site descriptions for preliminary radiological assessments of low-level waste repositories

International Nuclear Information System (INIS)

Burgess, W.E.; Jones, C.H.; Sumerling, T.J.; Ashton, J.

1988-07-01

The environmental contexts of four sites, previously under investigation by UK Nirex Ltd. as potential locations for low-level waste disposal facilities, are described. Information on geographical setting, climate, surface hydrology, land use, agriculture, fisheries, geology and hydrogeology is presented. The geological and hydrogeological data are interpreted with the support of deterministic modelling of groundwater conditions. The routes by which radionuclides may migrate from the site are identified and reduced to 1D statistical descriptions suitable for use in probabilistic risk assessments. Additional data required to improve the assessment of the performance of the site are identified. (author)

Siting low-level radioactive waste in Pennsylvania: socio-political problems and the search for solutions

International Nuclear Information System (INIS)

Bord, R.J.

1987-01-01

By January 1, 1996 the State of Pennsylvania must take title to and possession of all low-level radioactive waste generated within its borders and pay any damages resulting from failure to provide disposal. While ten years appears to be a comfortable time frame within which to develop a disposal facility, the path to an operating site will undoubtedly be difficult and costly in both time and money. Public opposition to waste in general and to radioactive materials in particular makes the 1996 deadline problematic. The not in my back yard battle cry highlights the conflict characterizing attempts to site any kind of hazardous material. Nuclear power plants, medical facilities, manufacturing industries, and research institutes have a high stake in successful siting. Three issues must be addressed to provide a better understanding of the dilemma facing the State: first, an overview of the development of the present legal situation is necessary to understand the mandate facing Pennsylvania; second, the nature of public intransigence and their perception of the situation sheds light on approaches which may enhance cooperation; finally, probable paths to a LLRW site which are now being discussed in draft legislation provide an assessment of how the State hopes to meet the siting challenge. A discussion of general siting difficulties will conclude the paper

Technical development for geological disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Asano, Hidekazu; Sugino, Hiroyuki; Kawakami, Susumu; Yamanaka, Yumiko

1997-01-01

Technical developments for geological disposal of high-level radioactive wastes materials research and design technique for engineered barriers (overpack and buffer material) were studied to evaluate more reliable disposal systems for high-level radioactive wastes. A lifetime prediction model for the maximum corrosion depth of carbon steel was developed. A preferable alloys evaluation method for crevice corrosion was established for titanium. Swelling pressure and water permeability of bentonite as a buffer material was measured, and coupled hydro-thermo-mechanical analysis code for bentonite was also studied. The CIP (cold isostatic pressing) method for monolithically formed buffer material was tested. A concept study on operation equipment for the disposal site was performed. Activities of microorganisms involved in underground performance were investigated. (author)

Siting high-level nuclear waste repositories: A progress report for Rhode Island

International Nuclear Information System (INIS)

Frohlich, R.K.; Vild, B.F.

1986-03-01

In this booklet, we will not try to argue the pros and cons of nuclear power or weapons production. We will focus instead on the issue of nuclear waste disposal. With the passage of the Nuclear Waste Policy Act (NWPA) of 1982, the US Congress and the President charged federal and state regulators with the responsibility of settling that issue by the end of this century - with extensive public involvement. This booklet, now in its second printing, is designed to explain the nature of ''high-level'' nuclear waste, the essential criteria for its safe and permanent disposal, and Rhode Island's participation in the federal repository program. It has been funded from a USDOE grant derived from a utility-financed Nuclear Waste Fund established under the NWPA. 17 refs., 10 figs., 2 tabs

High-level waste description, inventory and hazard

International Nuclear Information System (INIS)

Crandall, J.; Hennelly, E.J.; McElroy, J.L.

1983-01-01

High-level nuclear waste (HLW), including its origin, is described and the current differences in definitions discussed. Quantities of defense and commercial radioactive HLW, both volume and curie content, are given. Current waste handling, which is interimin nature, is described for the several sites. The HLW hazard is defined by the times during which various radionuclides are the dominant contributors. The hazard is also compared to that of the ore. Using ICRP-2, which is the legal reference in the US, the hazard of the waste reduces to a level equal to the ore in about 300 years. The disposal plans are summarized and it is shown that regulatory requirements will probably govern disposal operations in such a conservative manner that the risk (product of hazard times probability of release) may well be lower than for any other wastes in existence or perhaps lower than those for any other human endeavor

Secrets of successful siting legislation for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Pasternak, A.D.

1988-01-01

California's users of radioactive materials, working together through the California Radioactive Materials Management Forum (Cal Rad), have played a role in fostering development of our state's low-level radioactive waste disposal facility. One of Cal Rad's contributions was to develop and sponsor California's siting legislation in 1983. In this paper, the elements of the state's LLRW siting law, California Senate Bill 342 (Chapter 1177, Statutes a 1983), and their relationship to a successful siting program are described

United States regulations for institutional controls at high-level waste repositories

International Nuclear Information System (INIS)

Piccone, Josephine

2015-01-01

The United States regulations for disposal of spent nuclear fuel and high-level radioactive waste are found at Title 10 of the Code of Federal Regulations (10 CFR) Parts 60 and 63, which cover deep geologic disposal at a generic site and at Yucca Mountain, Nevada, respectively. As an independent regulator, the US Nuclear Regulatory Commission (NRC) is responsible for licensing and oversight of a high-level waste repository in the United States. The licensing approach for disposal has discreet decisions, made by the NRC, that include approval of construction authorisation, approval to receive and possess high-level radioactive waste, and approval for permanent closure. For construction authorisation approval, the applicant must provide a description of the programme to be used to maintain the records. The NRC will have an active oversight role during the construction and operation period, which can be on the order of 100 years for the facility before permanent closure. The oversight activities are part of the active institutional controls, and serve as a means of conveying knowledge for that initial period, given that this will likely involve multiple generations of workers for both the implementer and the regulator. Additionally, the NRC provides requirements for the physical protection of stored spent nuclear fuel and high-level radioactive waste at 10 CFR Chap. 73.51. For permanent closure approval, the applicant must provide a detailed description of the measures to be employed-such as land use controls, construction of monuments, and preservation of records. The NRC's regulatory role in any licensing action is to apply the applicable regulations and guidance, and to review applications for proposed actions to determine if compliance with regulations has been achieved. The burden of proof is on the applicant or licensee to show that the proposed action is safe, to demonstrate that regulations are met, and to ensure continued compliance with the regulations

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

International Nuclear Information System (INIS)

2010-01-01

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles (mi)) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan

On area-specific underground research laboratory for geological disposal of high-level radioactive waste in China

Directory of Open Access Journals (Sweden)

Ju Wang

2014-04-01

Full Text Available Underground research laboratories (URLs, including “generic URLs” and “site-specific URLs”, are underground facilities in which characterisation, testing, technology development, and/or demonstration activities are carried out in support of the development of geological repositories for high-level radioactive waste (HLW disposal. In addition to the generic URL and site-specific URL, a concept of “area-specific URL”, or the third type of URL, is proposed in this paper. It is referred to as the facility that is built at a site within an area that is considered as a potential area for HLW repository or built at a place near the future repository site, and may be regarded as a precursor to the development of a repository at the site. It acts as a “generic URL”, but also acts as a “site-specific URL” to some extent. Considering the current situation in China, the most suitable option is to build an “area-specific URL” in Beishan area, the first priority region for China's high-level waste repository. With this strategy, the goal to build China's URL by 2020 may be achieved, but the time left is limited.

Derivation of beryllium guidelines for use in establishing cleanup levels at the Peek Street and Sacandaga sites, New York

International Nuclear Information System (INIS)

Hartmann, H.M.; Avci, H.I.; Ditmars, J.D.

1992-02-01

Guideline levels are derived for beryllium in soil and on indoor surfaces at the Peek Street and Sacandaga sites in the state of New York. On the basis of highly conservative assumptions, the soil beryllium concentration that corresponds to a 10 - 4 carcinogenic risk level is estimated to be 13 mg/kg at both sites. Calculations indicate that the proposed US Department of Energy guideline of 2 μg/ft 2 for beryllium in dust on indoor surfaces would be sufficiently protective of human health. For occupational protection of workers during cleanup operations, Office of Safety and Health Administration standards for beryllium are referenced and restated

Water-Level Data Analysis for the Saturated Zone Site-Scale Flow and Transport Model

International Nuclear Information System (INIS)

Tucci, P.

2001-01-01

This Analysis/Model Report (AMR) documents an updated analysis of water-level data performed to provide the saturated-zone, site-scale flow and transport model (CRWMS M and O 2000) with the configuration of the potentiometric surface, target water-level data, and hydraulic gradients for model calibration. The previous analysis was presented in ANL-NBS-HS-000034, Rev 00 ICN 01, Water-Level Data Analysis for the Saturated Zone Site-Scale Flow and Transport Model (USGS 2001). This analysis is designed to use updated water-level data as the basis for estimating water-level altitudes and the potentiometric surface in the SZ site-scale flow and transport model domain. The objectives of this revision are to develop computer files containing (1) water-level data within the model area (DTN: GS010908312332.002), (2) a table of known vertical head differences (DTN: GS0109083 12332.003), and (3) a potentiometric-surface map (DTN: GS010608312332.001) using an alternate concept from that presented in ANL-NBS-HS-000034, Rev 00 ICN 01 for the area north of Yucca Mountain. The updated water-level data include data obtained from the Nye County Early Warning Drilling Program (EWDP) and data from borehole USW WT-24. In addition to being utilized by the SZ site-scale flow and transport model, the water-level data and potentiometric-surface map contained within this report will be available to other government agencies and water users for ground-water management purposes. The potentiometric surface defines an upper boundary of the site-scale flow model, as well as provides information useful to estimation of the magnitude and direction of lateral ground-water flow within the flow system. Therefore, the analysis documented in this revision is important to SZ flow and transport calculations in support of total system performance assessment

Stabilization and isolation of low-level liquid waste disposal sites

International Nuclear Information System (INIS)

Phillips, S.J.; Gilbert, T.W.

1987-01-01

Rockwell Hanford Operations is developing and testing equipment for stabilization and isolation of low-level radioactive liquid waste disposal sites. Stabilization and isolation are accomplished by a dynamic consolidation and particulate grout injection system. System equipment components include: a mobile grout plant for transport, mixing, and pumping of particulate grout; a vibratory hammer/extractor for consolidation of waste, backfill, and for emplacement of the injector; dynamic consolidation/injector probe for introducing grout into fill material; and an open-void surface injector that uses surface or subsurface mechanical or pneumatic packers and displacement gas filtration for introducing grout into disposal structure access piping. Treatment of a liquid-waste disposal site yields a physically stable, cementitious monolith. Additional testing and modification of this equipment for other applications to liquid waste disposal sites is in progress

High-level waste issues and resolutions document

International Nuclear Information System (INIS)

1994-05-01

The High-Level Waste (HLW) Issues and Resolutions Document recognizes US Department of Energy (DOE) complex-wide HLW issues and offers potential corrective actions for resolving these issues. Westinghouse Management and Operations (M ampersand O) Contractors are effectively managing HLW for the Department of Energy at four sites: Idaho National Engineering Laboratory (INEL), Savannah River Site (SRS), West Valley Demonstration Project (WVDP), and Hanford Reservation. Each site is at varying stages of processing HLW into a more manageable form. This HLW Issues and Resolutions Document identifies five primary issues that must be resolved in order to reach the long-term objective of HLW repository disposal. As the current M ampersand O contractor at DOE's most difficult waste problem sites, Westinghouse recognizes that they have the responsibility to help solve some of the complexes' HLW problems in a cost effective manner by encouraging the M ampersand Os to work together by sharing expertise, eliminating duplicate efforts, and sharing best practices. Pending an action plan, Westinghouse M ampersand Os will take the initiative on those corrective actions identified as the responsibility of an M ampersand O. This document captures issues important to the management of HLW. The proposed resolutions contained within this document set the framework for the M ampersand Os and DOE work cooperatively to develop an action plan to solve some of the major complex-wide problems. Dialogue will continue between the M ampersand Os, DOE, and other regulatory agencies to work jointly toward the goal of storing, treating, and immobilizing HLW for disposal in an environmentally sound, safe, and cost effective manner

Status of the French nuclear high level waste disposal

International Nuclear Information System (INIS)

Sombret, C.

1985-09-01

French research on high level waste processing has led to the development of industrial vitrification facilities. Borosilicate glass is still being investigated for its long-term storage properties, since it is itself a component of the containment system. The other constituents of this system, the engineered barriers, are also being actively investigated. The geological barrier is now being assessed using a methodology applicable to various types of geological formations, and final site qualification should be possible before the end of 1992

1983 state-by-state assessment of low-level radioactive wastes shipped to commercial disposal sites

International Nuclear Information System (INIS)

1984-12-01

The 1983 report uses the volume of low-level waste reported as received at each commercial disposal site as the national baseline figure. A volume of 76,702 m 3 of radioactive waste containing 505,340 Ci of activity was reported disposed at the commercial sites in 1983. The distribution of these waste volumes by disposal site is tabulated. Typical radionuclides in low-level wastes by sector are given. Predominant waste forms associated with low-level waste by sector are tabulated. Sometimes the amount of waste reported by power facilities is equal to or exceeds the state volume reported from commercial disposal site operators. Discrepancies may be a result of waste volumes being credited to the home state of the waste broker instead of the actual state location of the generator. Additionally, waste volumes may have been in transit from the generator to the disposal site at year's end. The Low-Level Waste Management Program felt a responsibility to report information accurately from the various sources, so did not alter the figures to make them balance

Techno-economical Analysis of High Level Waste Storage and Disposal Options

International Nuclear Information System (INIS)

Bace, M.; Trontl, K.; Vrankic, K.

2002-01-01

Global warming and instability of gas and oil prices are redefining the role of nuclear energy in electrical energy production. A production of high-level radioactive waste (HLW), during the nuclear power plant operation and a danger of high level waste mitigation to the environment are considered by the public as a main obstacle of accepting the nuclear option. As economical and technical aspects of the back end of fuel cycle will affect the nuclear energy acceptance the techno-economical analysis of different methods for high level waste storage and disposal has to be performed. The aim of this paper is to present technical and economical characteristics of different HLW storage and disposal technologies. The final choice of a particular HLW management method is closely connected to the selection of a fuel cycle type: open or closed. Wet and dry temporary storage has been analyzed including different types of spent fuel pool capacity increase methods, different pool location (at reactor site and away from reactor site) as well as casks and vault system of dry storage. Since deep geological deposition is the only disposal method with a realistic potential, we focused our attention on that disposal technology. Special attention has been given to the new idea of international and regional disposal location. The analysis showed that a coexistence of different storage methods and deep geological deposition is expected in the future, regardless of the fuel cycle type. (author)

Parameters for characterizing sites for disposal of low-level radioactive waste

International Nuclear Information System (INIS)

Lutton, R.J.; Malone, P.G.; Meade, R.B.; Patrick, D.M.

1982-05-01

Sixty-seven site parameters and parameter groups are identified as important characteristics of sites for disposal of low-level radioactive waste and require detailed evaluation. Several of the most important parameters are needed for hydrological analysis while others are needed for facility design, construction, and operation. Still others are needed for baseline and detection stages of monitoring. It is recommended that all parameters be evaluated by technically qualified personnel. Appropriate tests and documentation methods are discussed in a second report, which will follow. However, site-specific testing or elaborate field measurement will not always be necessary, i.e., where indicated to be unnecessary on a technical basis. Much of this report, Appendices A through G, is directed to explaining the importances of parameters and to establishing site-specific limitations

Characterization of radionuclude behavior in low-level waste sites

International Nuclear Information System (INIS)

Toste, A.P.; Kirby, L.J.; Robertson, D.E.; Abel, K.H.; Perkins, R.W.

1982-10-01

Our laboratory is investigating the subsurface migration of radionuclides in groundwater at the Maxey Flats, Kentucky, shallow land-burial site and at a low-level aqueous waste disposal facility. At Maxey Flats, radionuclide and tracer data indicate groundwater communication between a waste trench and an adjacent experimental study area. Areal distributions of radionuclides in surface soil confirm that contamination at Maxey Flats has been largely contained on site. Of the radionuclides detected in the surface soil, only 3 H and 60 Co concentrations appear to be derived from waste. Plutonium exists in the anoxic subsurface waters at Maxey Flats as a reduced, anionic complex; some of the plutonium appears to be complexed with EDTA, whereas organic acids seem to be associated with 137 Cs and 90 Sr. At the aqueous waste disposal site, 3 H and mainly anionic species of certain radionuclides, including 60 Co, 106 Ru, 99 Tc, 131 I, and traces of 238 239 240 Pu, appear to migrate from a trench through soil adjacent to the trench. Radionuclides in the particulate and cationic forms appear to be efficiently retained by the soil. In general, observations indicate that the physicochemical form of the radionuclides mediates their subsurface migration in groundwater at both waste disposal sites

Multimedia approach to estimating target cleanup levels for soils at hazardous waste sites

International Nuclear Information System (INIS)

Hwang, S.T.

1990-04-01

Contaminated soils at hazardous and nuclear waste sites pose a potential threat to human health via transport through environmental media and subsequent human intake. To minimize health risks, it is necessary to identify those risks and ensure that appropriate actions are taken to protect public health. The regulatory process may typically include identification of target cleanup levels and evaluation of the effectiveness of remedial alternatives and the corresponding reduction in risks at a site. The US Environmental Protection Agency (EPA) recommends that exposure assessments be combined with toxicity information to quantify the health risk posed by a specific site. This recommendation then forms the basis for establishing target cleanup levels. An exposure assessment must first identify the chemical concentration in a specific medium (soil, water, air, or food), estimate the exposure potential based on human intake from that media, and then combined with health criteria to estimate the upperbound health risks for noncarcinogens and carcinogens. Estimation of target cleanup levels involves the use of these same principles but can occur in reverse order. The procedure starts from establishing a permissible health effect level and ends with an estimated target cleanup level through an exposure assessment process. 17 refs

Cover technology demonstration for low-level radioactive sites

International Nuclear Information System (INIS)

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

1988-01-01

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

Permitting plan for the high-level waste interim storage

International Nuclear Information System (INIS)

Deffenbaugh, M.L.

1997-01-01

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

Energy Technology Data Exchange (ETDEWEB)

Collard, L.B.

2000-09-26

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds.

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Collard, L.B.

2000-01-01

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds

Topical report on release scenario analysis of long-term management of high-level defense waste at the Hanford Site

International Nuclear Information System (INIS)

Wallace, R.W.; Landstrom, D.K.; Blair, S.C.; Howes, B.W.; Robkin, M.A.; Benson, G.L.; Reisenauer, A.E.; Walters, W.H.; Zimmerman, M.G.

1980-11-01

Potential release scenarios for the defense high-level waste (HLW) on the Hanford Site are presented. Presented in this report are the three components necessary for evaluating the various alternatives under consideration for long-term management of Hanford defense HLW: identification of scenarios and events which might directly or indirectly disrupt radionuclide containment barriers; geotransport calculations of waste migration through the site media; and consequence (dose) analyses based on groundwater and air pathways calculations. The scenarios described in this report provide the necessary parameters for radionuclide transport and consequence analysis. Scenarios are categorized as either bounding or nonbounding. Bounding scenarios consider worst case or what if situations where an actual and significant release of waste material to the environment would happen if the scenario were to occur. Bounding scenarios include both near-term and long-term scenarios. Near-term scenarios are events which occur at 100 years from 1990. Long term scenarios are potential events considered to occur at 1000 and 10,000 years from 1990. Nonbounding scenarios consider events which result in insignificant releases or no release at all to the environment. Three release mechanisms are described in this report: (1) direct exposure of waste to the biosphere by a defined sequence of events (scenario) such as human intrusion by drilling; (2) radionuclides contacting an unconfined aquifer through downward percolation of groundwater or a rising water table; and (3) cataclysmic or explosive release of radionuclides by such mechanisms as meteorite impact, fire and explosion, criticality, or seismic events. Scenarios in this report present ways in which these release mechanisms could occur at a waste management facility. The scenarios are applied to the two in-tank waste management alternatives: in-situ disposal and continued present action

Technology needs for selecting and evaluating high-level waste repository sites in crystalline rock

International Nuclear Information System (INIS)

1988-12-01

This report describes properties and processes that govern the performance of the geological barrier in a nuclear waste isolation system in crystalline rock and the state-of-the-art in the understanding of these properties and processes. Areas and topics that require further research and development as well as technology needs for investigating and selecting repository sites are presented. Experiences from the Swedish site selection program are discussed, and a general investigation strategy is presented for an area characterization phase of an exploratory program in crystalline rocks. 255 refs., 65 figs., 10 tabs

Water-Level Data Analysis for the Saturated Zone Site-Scale Flow and Transport Model

International Nuclear Information System (INIS)

K. Rehfeldt

2004-01-01

This report is an updated analysis of water-level data performed to provide the ''Saturated Zone Site-Scale Flow Model'' (BSC 2004 [DIRS 170037]) (referred to as the saturated zone (SZ) site-scale flow model or site-scale SZ flow model in this report) with the configuration of the potentiometric surface, target water-level data, and hydraulic gradients for calibration of groundwater flow models. This report also contains an expanded discussion of uncertainty in the potentiometric-surface map. The analysis of the potentiometric data presented in Revision 00 of this report (USGS 2001 [DIRS 154625]) provides the configuration of the potentiometric surface, target heads, and hydraulic gradients for the calibration of the SZ site-scale flow model (BSC 2004 [DIRS 170037]). Revision 01 of this report (USGS 2004 [DIRS 168473]) used updated water-level data for selected wells through the year 2000 as the basis for estimating water-level altitudes and the potentiometric surface in the SZ site-scale flow and transport model domain based on an alternative interpretation of perched water conditions. That revision developed computer files containing: Water-level data within the model area (DTN: GS010908312332.002); A table of known vertical head differences (DTN: GS010908312332.003); and A potentiometric-surface map (DTN: GS010608312332.001) using an alternative concept from that presented by USGS (2001 [DIRS 154625]) for the area north of Yucca Mountain. The updated water-level data presented in USGS (2004 [DIRS 168473]) include data obtained from the Nye County Early Warning Drilling Program (EWDP) Phases I and II and data from Borehole USW WT-24. This document is based on Revision 01 (USGS 2004 [DIRS 168473]) and expands the discussion of uncertainty in the potentiometric-surface map. This uncertainty assessment includes an analysis of the impact of more recent water-level data and the impact of adding data from the EWDP Phases III and IV wells. In addition to being utilized

Low level radioactive waste disposal/treatment technology overview: Savannah River site

International Nuclear Information System (INIS)

Sturm, H.F. Jr.

1987-01-01

The Savannah River Site will begin operation of several low-level waste disposal/treatment facilities during the next five years, including a new low-level solid waste disposal facility, a low-level liquid effluent treatment facility, and a low-level liquid waste solidification process. Closure of a radioactive hazardous waste burial ground will also be completed. Technical efforts directed toward waste volume reduction include compaction, incineration, waste avoidance, and clean waste segregation. This paper summarizes new technology being developed and implemented. 11 refs., 1 fig

Hydrogeologic factors in the selection of shallow land burial sites for the disposal of low-level radioactive waste

Science.gov (United States)

Fischer, John N.

1986-01-01

In the United States, low-level radioactive waste is disposed of by shallow land burial. Commercial low-level radioactive waste has been buried at six sites, and low-level radioactive waste generated by the Federal Government has been buried at nine major and several minor sites. Several existing low-level radioactive waste sites have not provided expected protection of the environment. These shortcomings are related, at least in part, to an inadequate understanding of site hydrogeology at the time the sites were selected. To better understand the natural systems and the effect of hydrogeologic factors on long-term site performance, the U.S. Geological Survey has conducted investigations at five of the six commercial low-level radioactive waste sites and at three Federal sites. These studies, combined with those of other Federal and State agencies, have identified and confirmed important hydrogeologic factors in the effective disposal of low-level radioactive waste by shallow land burial. These factors include precipitation, surface drainage, topography, site stability, geology, thickness of the host soil-rock horizon, soil and sediment permeability, soil and water chemistry, and depth to the water table.

Design and operation of off-gas cleaning systems at high level liquid waste conditioning facilities

International Nuclear Information System (INIS)

1988-01-01

The immobilization of high level liquid wastes from the reprocessing of irradiated nuclear fuels is of great interest and serious efforts are being undertaken to find a satisfactory technical solution. Volatilization of fission product elements during immobilization poses the potential for the release of radioactive substances to the environment and necessitates effective off-gas cleaning systems. This report describes typical off-gas cleaning systems used in the most advanced high level liquid waste immobilization plants and considers most of the equipment and components which can be used for the efficient retention of the aerosols and volatile contaminants. In the case of a nuclear facility consisting of several different facilities, release limits are generally prescribed for the nuclear facility as a whole. Since high level liquid waste conditioning (calcination, vitrification, etc.) facilities are usually located at fuel reprocessing sites (where the majority of the high level liquid wastes originates), the off-gas cleaning system should be designed so that the airborne radioactivity discharge of the whole site, including the emission of the waste conditioning facility, can be kept below the permitted limits. This report deals with the sources and composition of different kinds of high level liquid wastes and describes briefly the main high level liquid waste solidification processes examining the sources and characteristics of the off-gas contaminants to be retained by the off-gas cleaning system. The equipment and components of typical off-gas systems used in the most advanced (large pilot or industrial scale) high level liquid waste solidification plants are described. Safety considerations for the design and safe operation of the off-gas systems are discussed. 60 refs, 31 figs, 17 tabs

Carbon stocks and fluxes in the high latitudes: using site-level data to evaluate Earth system models

Directory of Open Access Journals (Sweden)

S. E. Chadburn

2017-11-01

Full Text Available It is important that climate models can accurately simulate the terrestrial carbon cycle in the Arctic due to the large and potentially labile carbon stocks found in permafrost-affected environments, which can lead to a positive climate feedback, along with the possibility of future carbon sinks from northward expansion of vegetation under climate warming. Here we evaluate the simulation of tundra carbon stocks and fluxes in three land surface schemes that each form part of major Earth system models (JSBACH, Germany; JULES, UK; ORCHIDEE, France. We use a site-level approach in which comprehensive, high-frequency datasets allow us to disentangle the importance of different processes. The models have improved physical permafrost processes and there is a reasonable correspondence between the simulated and measured physical variables, including soil temperature, soil moisture and snow. We show that if the models simulate the correct leaf area index (LAI, the standard C3 photosynthesis schemes produce the correct order of magnitude of carbon fluxes. Therefore, simulating the correct LAI is one of the first priorities. LAI depends quite strongly on climatic variables alone, as we see by the fact that the dynamic vegetation model can simulate most of the differences in LAI between sites, based almost entirely on climate inputs. However, we also identify an influence from nutrient limitation as the LAI becomes too large at some of the more nutrient-limited sites. We conclude that including moss as well as vascular plants is of primary importance to the carbon budget, as moss contributes a large fraction to the seasonal CO2 flux in nutrient-limited conditions. Moss photosynthetic activity can be strongly influenced by the moisture content of moss, and the carbon uptake can be significantly different from vascular plants with a similar LAI. The soil carbon stocks depend strongly on the rate of input of carbon from the vegetation to the soil, and our

Carbon stocks and fluxes in the high latitudes: using site-level data to evaluate Earth system models

Science.gov (United States)

Chadburn, Sarah E.; Krinner, Gerhard; Porada, Philipp; Bartsch, Annett; Beer, Christian; Belelli Marchesini, Luca; Boike, Julia; Ekici, Altug; Elberling, Bo; Friborg, Thomas; Hugelius, Gustaf; Johansson, Margareta; Kuhry, Peter; Kutzbach, Lars; Langer, Moritz; Lund, Magnus; Parmentier, Frans-Jan W.; Peng, Shushi; Van Huissteden, Ko; Wang, Tao; Westermann, Sebastian; Zhu, Dan; Burke, Eleanor J.

2017-11-01

It is important that climate models can accurately simulate the terrestrial carbon cycle in the Arctic due to the large and potentially labile carbon stocks found in permafrost-affected environments, which can lead to a positive climate feedback, along with the possibility of future carbon sinks from northward expansion of vegetation under climate warming. Here we evaluate the simulation of tundra carbon stocks and fluxes in three land surface schemes that each form part of major Earth system models (JSBACH, Germany; JULES, UK; ORCHIDEE, France). We use a site-level approach in which comprehensive, high-frequency datasets allow us to disentangle the importance of different processes. The models have improved physical permafrost processes and there is a reasonable correspondence between the simulated and measured physical variables, including soil temperature, soil moisture and snow. We show that if the models simulate the correct leaf area index (LAI), the standard C3 photosynthesis schemes produce the correct order of magnitude of carbon fluxes. Therefore, simulating the correct LAI is one of the first priorities. LAI depends quite strongly on climatic variables alone, as we see by the fact that the dynamic vegetation model can simulate most of the differences in LAI between sites, based almost entirely on climate inputs. However, we also identify an influence from nutrient limitation as the LAI becomes too large at some of the more nutrient-limited sites. We conclude that including moss as well as vascular plants is of primary importance to the carbon budget, as moss contributes a large fraction to the seasonal CO2 flux in nutrient-limited conditions. Moss photosynthetic activity can be strongly influenced by the moisture content of moss, and the carbon uptake can be significantly different from vascular plants with a similar LAI. The soil carbon stocks depend strongly on the rate of input of carbon from the vegetation to the soil, and our analysis suggests that

High-level radioactive-waste-disposal investigations in Texas

International Nuclear Information System (INIS)

Smith, R.D.

1983-01-01

The Texas Energy and Natural Resources Advisory Council (TENRAC) was designated in 1980 to coordinate the interaction between the State of Texas and the federal government relating to the high-level radioactive waste disposal issue. This report was prepared to summarize the many aspects of that issue with particular emphasis on the activities in Texas. The report is intended to provide a comprehensive introduction for individuals with little or no previous exposure to the issue and to provide a broader perspective for those individuals who have addressed specific aspects of the issue but have not had the opportunity to study it in a broader context. Following the introduction, contents of this report are as follows: (1) general status of major repository siting investigations in the US; (2) detailed review of Texas studies; (3) possible facilities to be sited in Texas; (4) current Texas policy; (5) federal regulations; and (6) federal legislation. 9 figures, 2 tables

Characterization of organics in leachates from low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Francis, A.J.; Iden, C.R.; Nine, B.; Chang, C.

1979-01-01

Low-level radioactive wastes generated by the nuclear industry, universities, research institutions, and hospitals are disposed of in shallow-land trenches and pits. In 1962 the first commercial disposal site was opened in Beatty, Nevada. Since then, the industry has grown to include three private companies operating six disposal areas located in sparsely populated areas: at Maxey Flats (Morehead), Kentucky; Beatty, Nevada; Sheffield, Illinois; Barnwell, South Carolina; West Valley, New York; and Richland, Washington. Although the facilities are operated by private industry, they are located on public land and are subject to federal and state regulation. Although inventories of the radioactive materials buried in the disposal sites are available, no specific records are kept on the kinds and quantities of organic wastes buried. In general, the organic wastes consist of contaminated paper, packing materials, clothing, plastics, ion-exchange resins, scintillation vials, solvents, chemicals, decontamination fluids, carcasses of experimental animals, and solidification agents. Radionuclides such as 14 C, 3 H, 90 Sr, 134 137 Cs, 60 Co, 241 Am, and 238 239 240 Pu have been identified in leachate samples collected from several trenches at Maxey Flats and West Valley. The purpose of this report is to identify some of the organic compounds present in high concentrations in trench leachates at the disposal sites in order to begin to evaluate their effect on radionuclide mobilization and contamination of the environment

Underground excavation methods for a high-level waste repository

International Nuclear Information System (INIS)

Peshel, J.; Gupta, D.; Nataraja, M.

1990-01-01

This paper reports on rock excavation methods for a High-Level Waste repository that should be selected to limit the potential for creating preferential pathways for groundwater to travel to the waste packages or for radionuclides to migrate to the accessible environment. The use of water and other foreign substances should be controlled so that the repository performance is not compromised. The excavated openings should remain stable so that operations can be carried out safely and the retrievability option maintained. As per the current conceptual designs presented by the Department of Energy, the exploratory shaft facility becomes a part of the repository if the Yucca Mountain site is found suitable for repository development. Therefore, the methods of constructing the underground openings should be compatible with the performance requirements for the repository. Also, the degree of damage to the rock surrounding the openings and the extent of the damage zone should not preclude adequate site characterization. The ESf construction and operation should be compatible with the site data gathering activities, such as geological, thermomechanical, hydrological and geochemical testing

Potential impacts of sea level rise on native plant communities and associated cultural sites in coastal areas of the main Hawaiian Islands

Science.gov (United States)

Jacobi, James D.; Warshauer, Frederick R.

2017-01-01

Hawaiian coastal vegetation is comprised of plant species that are adapted to growing in extremely harsh conditions (salt spray, wave wash, wind, and substrates with limited nutrients) found in this habitat zone. Prior to human colonization of Hawai‘i coastal vegetation extended as a continuous ring around each of the islands, broken only by stretches of recent lava flows or unstable cliff faces. However, since humans arrived in Hawai‘i many areas that originally supported native coastal plant communities have been highly altered or the native vegetation totally removed for agriculture, housing, or resort development, destroyed by fire, displaced by invasive plants, eaten by introduced mammals, or damaged by recreational use. This study was focused on identifying sites that still retain relatively intact and highly diverse native coastal plant communities throughout the main Hawaiian Islands that may be further impacted by projected sea level rise. Approximately 40 percent of Hawai‘i’s coastlines were found to still contain high quality native coastal plant communities. Most of these sites were located in areas where the coastal vegetation can still migrate inshore in response to rising sea level and associated inundation by waves. However, six sites with high-quality native coastal vegetation were found on low-lying offshore islets that will be totally inundated with a one meter increase in sea level and thirty sites were found to have some type of fixed barrier, such as a paved road or structure, which would restrict the plants from colonizing the adjacent inland areas. Many of these sites also have other cultural resources that are fixed in place and will definitely be impacted by rising sea level. The results of this study can help refine our understanding of Hawai‘i’s remaining native coastal vegetation and aid with the development of management and restoration strategies to ensure the long-term survival of these unique plant communities.

Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 3. Appendices M-V

International Nuclear Information System (INIS)

1986-03-01

The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)

Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 2. Appendices A-L

International Nuclear Information System (INIS)

1986-03-01

The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)

Managing the nation's high-level radioactive waste: key issues and recommendations

International Nuclear Information System (INIS)

1981-07-01

To date, no unified national plan has been adopted to develop and implement a comprehensive system of management and disposal of high-level radioactive waste in the United States. Growing public concern about this problem has resulted in a number of recent efforts to develop a national high-level waste management policy. The 96th Congress strove to resolve the central issues, but ultimately failed to pass legislation, partly because of disagreements about the appropriate role of states in the siting of repositories for military waste. Outside government, a number of organizations convened representatives of diverse groups concerned with national high-level radioactive waste management to seek agreement on the major elements of national policy. One such organization was RESOLVE, Center for Environmental Conflict Resolution, which in May 1981 was merged into The Conservation Foundation. RESOLVE convened Forum II, a series of discussions among representatives of environmental, industrial, governmental, and citizen interest groups, in 1981 specifically to address the issues blocking Congressional agreement on high-level waste policy. This report contains the recommendations which resulted from these deliberations. Reprocessing, interim storage, respository development, and licensing requirements are addressed. Federal, state, and public participation in decision making are also discussed

Michigan high-level radioactive waste program. Technical progress report for 1985

International Nuclear Information System (INIS)

1986-01-01

In 1985, five crystalline rock formations located in Michigan's Upper Peninsula were under consideration in the regional phase of the Department of Energy's (DOE) search for the site of the nation's second high-level radioactive waste repository. The Michigan Department of Public Health has been designated by the Governor as lead state agency in matters related to high-level radioactive waste (HLRW). Mr. Lee E. Jager, Chief of the Department's Bureau of Environmental and Occupational Health, has been designated as the state contact person in this matter, and the Bureau's Division of Radiological Health, Office of Radioactive Waste Management (ORWM), has been designated to provide staff support. Recognizing that adequate state involvement in the various aspects of the Federal high-level radioactive waste (HLRW) programs would require a range of expertise beyond the scope of any single state agency, Governor Blanchard established the High-Level Radioactive Waste Task Force in 1983. In support of the Task Force efforts concerning the implementation of its change, the Department negotiated and concluded an agreement with the DOE, under which federal funds are provided to support state HLRW activities. This report outlines state activities for the calendar year 1985, funded under that agreement

The nuclear physical method for high pressure steam manifold water level gauging and its error

International Nuclear Information System (INIS)

Li Nianzu; Li Beicheng; Jia Shengming

1993-10-01

A new method, which is non-contact on measured water level, for measuring high pressure steam manifold water level with nuclear detection technique is introduced. This method overcomes the inherent drawback of previous water level gauges based on other principles. This method can realize full range real time monitoring on the continuous water level of high pressure steam manifold from the start to full load of boiler, and the actual value of water level can be obtained. The measuring errors were analysed on site. Errors from practical operation in Tianjin Junliangcheng Power Plant and in laboratory are also presented

Selection Criteria of Sites Suitable for Low- Level Radioactive U-mining and Milling wastes Disposal at Al-Missikat-Al-Aradiya District, Eastern Desert, Egypt

International Nuclear Information System (INIS)

Abdel-Monem, A.A.; Rabei, S.I.; El-Kiki, M.F.; Guirguis, G.P.; Rabei, S.I.

1999-01-01

Uranium mining and milling tailings are U-depleted but contain 230 TH and 226 Ra. These low-level radioactive wastes are disposed of in the near surface environment. Hydro geologically, suitable sites for disposal of these wastes should be characterized by:1) deep water-level,2) minimal precipitation,3) minimal exposure to flooding and 4) circular- shaped basins. Al-Missikat-Al-Aradiya District with future potential of U-mining and milling operations, a geomorphologic analysis led to the selection of four sites (sub basins) having the geomorphologic characteristics:1)elongation and circularity ratio≡1, 2) high track drainage density (limited infiltration),3) high stream frequency (deep water-table) and 4) moderate to low bifurcation ratio. These sites are further characterized geologically and structurally

Research in the selection of very low level radioactive waste disposal site in southwest China

International Nuclear Information System (INIS)

Tuo, Xianguo; Long, Qiong; Zhong, Hongmei; Xu, Zhengqi; Mu, Keliang; Gao, Lan

2008-01-01

The ultimate goal of Chinese Radioactive Nuclear Waste Management and Disposal Security is that must use proper and optimized ways to manage radioactive waste and make sure human beings and the environment either at the present or in the future can be free from any unacceptable risks. According to the goal, this paper presents an overview of comprehensive site characterization work that comprises investigations of physical geography, climatology, geology and hydrogeology, as well as geological hazard on two candidate Very Low Level Radioactive Waste (VLLW) disposal sites (Site 1 and Site 2) which are both located in the south west of China. The results showed that there are many similarities in the regional extent of the two sites, but many distinct differences are found in terrain and topographic features, granule stratum, hydraulic gradient, and so on. On the whole, the two alternative sites are in line with the requirements for very low level radioactive waste disposal, and Site 1 is superior to Site 2. (author)

Estimating variation in stomatal frequency at intra-individual, intra-site, and inter-taxonomic levels in populations of the Leonardoxa africana (Fabaceae) complex over environmental gradients in Cameroon

Science.gov (United States)

Finsinger, Walter; Dos Santos, Thibaut; McKey, Doyle

2013-07-01

Variation of stomatal frequency (stomatal density and stomatal index) includes genetically-based, potentially-adaptive variation, and variation due to phenotypic plasticity, the degree of which may be fundamental to the ability to maintain high water-use efficiency and thus to deal with environmental change. We analysed stomatal frequency and morphology (pore length, pore width) in leaves from several individuals from nine populations of four sub-species of the Leonardoxa africana complex. The dataset represents a hierarchical sampling wherein factors are nested within each level (leaves in individuals, individuals in sites, etc.), allowing estimation of the contribution of different levels to overall variation, using variance-component analysis. SI showed significant variation among sites ("site" is largely confounded with "sub-species"), being highest in the sub-species localized in the highest-elevation site. However, most of the observed variance was accounted for at intra-site and intra-individual levels. This variance could reflect great phenotypic plasticity, presumably in response to highly local variation in micro-environmental conditions.

DELPHI expert panel evaluation of Hanford high level waste tank failure modes and release quantities

Energy Technology Data Exchange (ETDEWEB)

Dunford, G.L.; Han, F.C.

1996-09-30

The Failure Modes and Release Quantities of the Hanford High Level Waste Tanks due to postulated accident loads were established by a DELPHI Expert Panel consisting of both on-site and off-site experts in the field of Structure and Release. The Report presents the evaluation process, accident loads, tank structural failure conclusion reached by the panel during the two-day meeting.

Instrument reliability for high-level nuclear-waste-repository applications

International Nuclear Information System (INIS)

Rogue, F.; Binnall, E.P.; Armantrout, G.A.

1983-01-01

Reliable instrumentation will be needed to evaluate the characteristics of proposed high-level nuclear-wasted-repository sites and to monitor the performance of selected sites during the operational period and into repository closure. A study has been done to assess the reliability of instruments used in Department of Energy (DOE) waste repository related experiments and in other similar geological applications. The study included experiences with geotechnical, hydrological, geochemical, environmental, and radiological instrumentation and associated data acquisition equipment. Though this paper includes some findings on the reliability of instruments in each of these categories, the emphasis is on experiences with geotechnical instrumentation in hostile repository-type environments. We review the failure modes, rates, and mechanisms, along with manufacturers modifications and design changes to enhance and improve instrument performance; and include recommendations on areas where further improvements are needed

Current status of high level radioactive waste disposal in Japan and foreign countries

International Nuclear Information System (INIS)

Tanaka, Satoru; Tanabe, Hiromi; Inagaki, Yusuke; Ishida, Hisahiro; Kato, Osamu; Kurata, Mitsuyuki; Yamachika, Hidehiko

2002-01-01

At a time point of 2002, there is no country actually disposing high level radioactive wastes into grounds, but in most of countries legislative preparation and practicing agents are carried out and site selection is promoted together with energetic advancement of its R and Ds. As disposal methods of the high level radioactive wastes, various methods such as space disposal, oceanic bottom disposal, ice bed disposal, ground disposal, and so on have been examined. And, a processing technology called partitioning and transmutation technology separating long-lived radionuclides from liquid high level radioactive waste and transmutation into short-lived or harmless radionuclides has also been studied. Here was introduced their wrestling conditions in Japan and main foreign countries, as a special issue of the Current status of high level radioactive waste disposal in Japan and foreign countries'. The high level radioactive wastes (glassification solids or spent nuclear fuels) are wastes always formed by nuclear power generation and establishment of technologies is an important subject for nuclear fuel cycle. (G.K.)

Preliminary report on the hydrogeology of a low-level radioactive waste disposal site near Sheffield, Illinois

Science.gov (United States)

Foster, J.B.; Erickson, J.R.

1980-01-01

The Sheffield low-level radioactive-waste disposal site is located on 20 acres of rolling terrain about 3 miles southwest of Sheffield, Illinois. Twenty-one trenches were constructed and filled with radioactive waste from August 1967 through April 1978. Forty-three test wells were installed by the U.S. Geological Survey on and adjacent to the site. Continuous cores were collected from 36 wells to help in defining the subsurface geology. The wells have been used for water sample collection and to monitor water-level changes. A tunnel, 6.5 feet in diameter by 290 feet in length, was constructed beneath four burial trenches to provide access for collection of hydrologic and geologic data. Pennsylvanian shale and mudstone deposits are overlain by Pleistocene glacial deposits consisting of the Teneriffe Silt, Glasford Formation, Roxana Silt, Peoria Loess, Parkland Sand, Cahokia Alluvium, and Henry Formation. Three till units of the Glasford Formation, the Hulick Till Member, the Radnor Till Member, and Till A have been identified on the site. Stratigraphic position indicates that the Hulick Till Member and Till A are probably variations of the same till. A continuous pebbly sand deposit, classified as part of the Toulon Member, extends across the middle of the site and continues off site on the northeast and southwest corners. Because of its relatively high hydraulic conductivity, this deposit will be a controlling factor in shallow groundwater movement and in any radionuclide migration. Ground water at the site is derived through infiltration of precipitation and as underflow from adjacent highlands. Precipitation averages 35 inches per year, 1 or 2 inches of which probably recharge the ground water. Runoff is estimated to be 12 to 15 inches per year and evapotranspiration about 20 inches. The fluctuation of water levels has been about 2.5 feet in hilltop wells, 3.6 feet in sidehill wells, and 5.9 feet in valley wells. Hydraulic conductivity of the materials comprising

Cultural approach to the perception of risk. Analyzing concern about siting of a high-level nuclear waste facility in Finland

International Nuclear Information System (INIS)

Litmanen, T.

1996-01-01

The study of local residents' attitudes toward siting a high-level nuclear waste facility in Finland took place in three municipalities (Eurajoki, Kuhmo and Agnekoski), which are being considered possible host communities for the plant. The survey showed that the NIMBY phenomenon is a common reaction in two of the three municipalities, and in the third a polarization of opinions into two opposing camps is evident. The analysis of the data indicates that the opposition consist of people who have less education, less knowledge about the facility, lower incomes, and a lower occupational status. The social base of the proponents is the opposite. The persons most critical towards the possible siting can be found among women, older people, voters of the Greens, retired persons and farmers. People who welcome nuclear waste in their vicinity can be found among men, the middle-aged, voters of the Conservative Party and business owners. The study of the perception of possible negative impacts (health and safety, environmental, economic and social) showed that residents in Kuhmo and Adnekoski were more concerned about possible hazards than the residents of Eurajoki. According to the cultural approach, these findings must be contextualized. Eurajoka, which holds more favorable attitudes than Kuhmo and Agnekoski, hosts a nuclear power plant. In the two other communities the opposition is greater, because the residents are unfamiliar with nuclear technology. The thesis of the paper is that in order to understand different opinions about the facility, one must understand the cultural logic of risk perception. People evaluate the risk as individuals, but also as members of different reference groups and in the context of local, national and international circumstances

Seismic site-response characterization of high-velocity sites using advanced geophysical techniques: application to the NAGRA-Net

Science.gov (United States)

Poggi, V.; Burjanek, J.; Michel, C.; Fäh, D.

2017-08-01

The Swiss Seismological Service (SED) has recently finalised the installation of ten new seismological broadband stations in northern Switzerland. The project was led in cooperation with the National Cooperative for the Disposal of Radioactive Waste (Nagra) and Swissnuclear to monitor micro seismicity at potential locations of nuclear-waste repositories. To further improve the quality and usability of the seismic recordings, an extensive characterization of the sites surrounding the installation area was performed following a standardised investigation protocol. State-of-the-art geophysical techniques have been used, including advanced active and passive seismic methods. The results of all analyses converged to the definition of a set of best-representative 1-D velocity profiles for each site, which are the input for the computation of engineering soil proxies (traveltime averaged velocity and quarter-wavelength parameters) and numerical amplification models. Computed site response is then validated through comparison with empirical site amplification, which is currently available for any station connected to the Swiss seismic networks. With the goal of a high-sensitivity network, most of the NAGRA stations have been installed on stiff-soil sites of rather high seismic velocity. Seismic characterization of such sites has always been considered challenging, due to lack of relevant velocity contrast and the large wavelengths required to investigate the frequency range of engineering interest. We describe how ambient vibration techniques can successfully be applied in these particular conditions, providing practical recommendations for best practice in seismic site characterization of high-velocity sites.

Site selection criteria for shallow land burial of low-level radioactive waste

International Nuclear Information System (INIS)

Falconer, K.L.; Hull, L.C.; Mizell, S.A.

1982-01-01

Twelve site selection criteria are presented. These are: (1) site shall be of sufficient area and depth to accommodate the projected volume of waste and a three dimensional buffer zone; (2) site should allow waste to be buried either completely above or below the transition zone between the unsaturated and saturated zones; (3) site should be located where flooding will not jeopardize performance; (4) site should be located where erosion will not jeopardize performance; (5) site should be located in areas where hydrogeologic conditions allow reliable performance prediction; (6) site should be located where geologic hazards will not jeopardize performance; (7) site should be selected with considerations given to those characteristics of earth materials and water chemistry that favor increased residence times and/or attenuation of radionuclide concentrations within site boundaries; (8) site should be selected with consideration given to current and projected population distributions; (9) site should be selected with consideration given to current and projected land use and resource development; (10) site should be selected with consideration given to location of waste generation, access to all-weather highway and rail routes, and access utilities; (11) site should be selected consistent with federal laws and regulations; (12) site should not be located within areas that are protected from such use by federal laws and regulations. These criteria are considered preliminary and do not necessarily represent the position of the Department of Energy's Low-Level Waste Management Program

Water-Level Data Analysis for the Saturated Zone Site-Scale Flow and Transport Model

Energy Technology Data Exchange (ETDEWEB)

K. Rehfeldt

2004-10-08

This report is an updated analysis of water-level data performed to provide the ''Saturated Zone Site-Scale Flow Model'' (BSC 2004 [DIRS 170037]) (referred to as the saturated zone (SZ) site-scale flow model or site-scale SZ flow model in this report) with the configuration of the potentiometric surface, target water-level data, and hydraulic gradients for calibration of groundwater flow models. This report also contains an expanded discussion of uncertainty in the potentiometric-surface map. The analysis of the potentiometric data presented in Revision 00 of this report (USGS 2001 [DIRS 154625]) provides the configuration of the potentiometric surface, target heads, and hydraulic gradients for the calibration of the SZ site-scale flow model (BSC 2004 [DIRS 170037]). Revision 01 of this report (USGS 2004 [DIRS 168473]) used updated water-level data for selected wells through the year 2000 as the basis for estimating water-level altitudes and the potentiometric surface in the SZ site-scale flow and transport model domain based on an alternative interpretation of perched water conditions. That revision developed computer files containing: Water-level data within the model area (DTN: GS010908312332.002); A table of known vertical head differences (DTN: GS010908312332.003); and A potentiometric-surface map (DTN: GS010608312332.001) using an alternative concept from that presented by USGS (2001 [DIRS 154625]) for the area north of Yucca Mountain. The updated water-level data presented in USGS (2004 [DIRS 168473]) include data obtained from the Nye County Early Warning Drilling Program (EWDP) Phases I and II and data from Borehole USW WT-24. This document is based on Revision 01 (USGS 2004 [DIRS 168473]) and expands the discussion of uncertainty in the potentiometric-surface map. This uncertainty assessment includes an analysis of the impact of more recent water-level data and the impact of adding data from the EWDP Phases III and IV wells. In

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

Cotton, T.

1985-01-01

With the passage of the Nuclear Waste Policy Act of 1982 (NWPA), Congress for the first time established in law a comprehensive Federal policy for commercial high-level radioactive waste management, including interim storage and permanent disposal. NWPA provides sufficient authority for developing and operating a high-level radioactive waste management system based on disposal in mined geologic repositories. Authorization for other types of waste facilities will not be required unless major problems with geologic disposal are discovered, and studies to date have identified no insurmountable technical obstacles to developing geologic repositories. The NWPA requires the Department of Energy (DOE) to submit to Congress three key documents: (1) a Mission Plan, containing both a waste management plan with a schedule for transferring waste to Federal facilities and an implementation program for choosing sites and developing technologies to carry out that plan; (2) a monitored retrievable storage (MRS) proposal, to include a site-specific design for a long-term federal storage facility, an evaluation of whether such an MRS facility is needed and feasible, and an analysis of how an MRS facility would be integrated with the repository program if authorized by Congress; and (3) a study of alternative institutional mechanisms for financing and managing the radioactive waste system, including the option of establishing an independent waste management organization outside of DOE. The Mission Plan and the report on alternative institutional mechanisms were submitted to the 99th US Congress in 1985. The MRS proposal is to be submitted in early 1986. Each of these documents is discussed following an overview of the Nuclear Waste Policy Act of 1982

Regional-interstate site-review procedure: low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

1983-09-01

The attributes of the Southern States Energy Board (SSEB) enable it to view federal/state interface problem areas from a perspective that can be uniquely constructive. The board is sensitive to the interests of both federal and state levels of government since it is composed of member states with common regional interests and confirmed by federal legislative action. It has been most effective when exercising a leadership role in finding procedures and practices that use the resources of both levels of government that are mutually supportive and nonduplicative. SSEB began an NRC-funded effort in that direction related to nuclear power plant siting in June 1975, entitled Regional-Interstate Nuclear Facility Siting Procedure Demonstration Project. SSEB approached the problem by working with interested states to analyze various elements of the licensing process, in particular with NEPA review procedures for interstate coordination where potential impacts extend beyond a single state and where the facility serves an interstate or regional need. SSEB also served as a catalyst in the development of a region-wide nuclear facility siting procedure that could improve the effectiveness and timeliness of the regulatory process

Great Lakes Daily Ice Observations at NOAA Water Level Gauge Sites

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains daily visual ice observations taken yearly from 1 November to 30 April at NOAA/National Ocean Service water level gauge sites in the Great...

Technical status report on environmental aspects of long-term management of high-level defense waste at the Hanford Site

International Nuclear Information System (INIS)

1980-10-01

Since 1944, radioactive wastes have accumulated at the US Department of Energy's (DOE) 1500-km 2 Hanford Site in southeastern Washington, where nine nuclear reactors have produced nuclear materials for National defense. Today, only one production reactor is still operating, but a large inventory of radioactive high-level waste (HLW), the residue from processing the spent fuel to recover plutonium and uranium, remains stored in underground tanks and in metal capsules in water basins. So that this waste will pose no significant threat to the public health and safety, it must be isolated from the biosphere for thousands of years. This document contains an evaluation of environmental impacts of four alternative methods for long-term management of these HLW. The alternatives range from continuing the present action of storing the waste near the surface of the ground to retrieving the waste and disposing of it deep underground in a mined geologic repository. The alternatives are: near-term geologic disposal of stored waste; deferred geologic disposal of in-tank waste; in situ disposal of in-tank waste; and continued present action for stored waste. The environmental impacts of the four alternatives are small relative to that radiation received from natural sources or the available natural resources in the earth

Hanford Site Tank Waste Remediation System

International Nuclear Information System (INIS)

1993-05-01

The US Department of Energy's (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives

Problems related to final disposal of high-level radioactive waste in Russia

International Nuclear Information System (INIS)

Velichkin, Vasily I.

1999-01-01

According to this presentation, the radioactivity of the total amount of radioactive waste accumulated in Russia to date is 1.5*10 9 Ci and of spent fuel 4.5*10 9 Ci. A table is given that shows the source, type, volume activity and storage type under the responsibility of the different departments and enterprises. 99.9% of the wastes are accumulated at the enterprises of Minatom of the Russian Federation. Some companies inject their liquid wastes from ionisation sources and intermediate liquid waste from the nuclear power industry into deep-seated reliably isolated aquifers. The Mayak plant has released liquid low-level and intermediate wastes into artificial reservoirs and Lake Karachay. Liquid high-level wastes are always stored in special tanks at interim storage facilities. A large number of nuclear submarines are laid up in North-Western Russia and East Russia, with spent fuel still in place as the interim storages in these regions are filled up and there are no conditioning plants. Underground disposal is considered the best way of isolating radioactive waste for as long as it is hazardous to the environment. Two new technologies are discussed. One involves including long-lived isotopes in high-stable mineral matrices, the other uses selective separation from the bulk of wastes. The matrices should be disposed of deep in the Earth's crust, at least 2-3 km down. Liquid waste of caesium-strontium fraction must be transformed into glass-like form and stored underground at a depth of a few hundred metres. Short-lived low level and intermediate level wastes should be conditioned and then deposited in subsurface ferroconcrete repositories constructed in clays. Finally, the presentation discusses the selection of sites and conditions for radioactive waste disposal. Two sites are discussed, the Mayak plant and a possible site at Mining Chemical Combine in Krasnoyarsk-26

Geomicrobiology of High Level Nuclear Waste-Contaminated Vadose Sediments at the Hanford Site, Washington State

International Nuclear Information System (INIS)

Fredrickson, Jim K.; Zachara, John M.; Balkwill, David L.; Kennedy, David W.; Li, Shu-Mei W.; Kostandarithes, Heather M.; Daly, Michael J.; Romine, Margaret F.; Brockman, Fred J.

2004-01-01

Sediments from a high-level nuclear waste plume were collected as part of investigations to evaluate the potential fate and migration of contaminants in the subsurface. The plume originated from a leak that occurred in 1962 from a waste tank consisting of high concentrations of alkali, nitrate, aluminate, Cr(VI), 137Cs, and 99Tc. Investigations were initiated to determine the distribution of viable microorganisms in the vadose sediment samples, probe the phylogeny of cultivated and uncultivated members, and evaluate the ability of the cultivated organisms to survive acute doses of ionizing radiation. The populations of viable aerobic heterotrophic bacteria were generally low, from below detection to ∼104 7 CFU g-1 but viable microorganisms were recovered from 11 of 16 samples including several of the most radioactive ones (e.g., > 10 ?Ci/g 137Cs). The isolates from the contaminated sediments and clone libraries from sediment DNA extracts were dominated by members related to known Gram-positive bacteria. Gram-positive bacteria most closely related to Arthrobacter species were the most common isolates among all samples but other high G+C phyla were also represented including Rhodococcus and Nocardia. Two isolates from the second most radioactive sample (>20 ?Ci 137Cs g-1) were closely related to Deinococcus radiodurans and were able to survive acute doses of ionizing radiation approaching 20kGy. Many of the Gram-positive isolates were resistant to lower levels of gamma radiation. These results demonstrate that Gram-positive bacteria, predominantly high G+C phyla, are indigenous to Hanford vadose sediments and some are effective at surviving the extreme physical and chemical stress associated with radioactive waste

Thermo-aeraulics of high level waste storage facilities

International Nuclear Information System (INIS)

Lagrave, Herve; Gaillard, Jean-Philippe; Laurent, Franck; Ranc, Guillaume; Duret, Bernard

2006-01-01

This paper discusses the research undertaken in response to axis 3 of the 1991 radioactive waste management act, and possible solutions concerning the processes under consideration for conditioning and long-term interim storage of long-lived radioactive waste. The notion of 'long-term' is evaluated with respect to the usual operating lifetime of a basic nuclear installation, about 50 years. In this context, 'long-term' is defined on a secular time scale: the lifetime of the facility could be as long as 300 years. The waste package taken into account is characterized notably by its high thermal power release. Studies were carried out in dedicated facilities for vitrified waste and for spent UOX and MOX fuel. The latter are not considered as wastes, owing to the value of the reusable material they contain. Three primary objectives have guided the design of these long-term interim storage facilities: - ensure radionuclide containment at all times; - permit retrieval of the containers at any time; - minimize surveillance; - maintenance costs. The CEA has also investigated surface and subsurface facilities. It was decided to work on generic sites with a reasonable set of parameters values that should be applicable at most sites in France. All the studies and demonstrations to date lead to the conclusion that long-term interim storage is technically feasible. The paper addresses the following items: - Long-term interim storage concepts for high-level waste; - Design principles and options for the interim storage facilities; - General architecture; - Research topics, Storage facility ventilation, Dimensioning of the facility; - Thermo-aeraulics of a surface interim storage facility; - VALIDA surface loop, VALIDA single container test campaign, Continuation of the VALIDA program; - Thermo-aeraulics of a network of subsurface interim storage galleries; - SIGAL subsurface loop; - PROMETHEE subsurface loop; - Temperature behaviour of the concrete structures; - GALATEE

Thermo-aeraulics of high level waste storage facilities

Energy Technology Data Exchange (ETDEWEB)

Lagrave, Herve; Gaillard, Jean-Philippe; Laurent, Franck; Ranc, Guillaume [CEA/Valrho, B.P. 17171, F-30207 Bagnols-sur-Ceze (France); Duret, Bernard [CEA Grenoble, 17 rue des Martyrs, 38054 Grenoble cedex 9 (France)

2006-07-01

This paper discusses the research undertaken in response to axis 3 of the 1991 radioactive waste management act, and possible solutions concerning the processes under consideration for conditioning and long-term interim storage of long-lived radioactive waste. The notion of 'long-term' is evaluated with respect to the usual operating lifetime of a basic nuclear installation, about 50 years. In this context, 'long-term' is defined on a secular time scale: the lifetime of the facility could be as long as 300 years. The waste package taken into account is characterized notably by its high thermal power release. Studies were carried out in dedicated facilities for vitrified waste and for spent UOX and MOX fuel. The latter are not considered as wastes, owing to the value of the reusable material they contain. Three primary objectives have guided the design of these long-term interim storage facilities: - ensure radionuclide containment at all times; - permit retrieval of the containers at any time; - minimize surveillance; - maintenance costs. The CEA has also investigated surface and subsurface facilities. It was decided to work on generic sites with a reasonable set of parameters values that should be applicable at most sites in France. All the studies and demonstrations to date lead to the conclusion that long-term interim storage is technically feasible. The paper addresses the following items: - Long-term interim storage concepts for high-level waste; - Design principles and options for the interim storage facilities; - General architecture; - Research topics, Storage facility ventilation, Dimensioning of the facility; - Thermo-aeraulics of a surface interim storage facility; - VALIDA surface loop, VALIDA single container test campaign, Continuation of the VALIDA program; - Thermo-aeraulics of a network of subsurface interim storage galleries; - SIGAL subsurface loop; - PROMETHEE subsurface loop; - Temperature behaviour of the concrete

High-Level Waste Salt Disposition Systems Engineering Team Final Report, Volumes I, II, and III

International Nuclear Information System (INIS)

Piccolo, S.F.

1999-01-01

This report describes the process used and results obtained by the High Level Waste Salt Disposition Systems Engineering Team to select a primary and backup alternative salt disposition method for the Savannah River Site

Ground-water levels and precipitation data at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky, October 1988-September 2000

Science.gov (United States)

Zettwoch, Douglas D.

2002-01-01

The U.S. Geological Survey, in cooperation with the Kentucky Natural Resources and Environmental Protection Cabinet--Department for Environmental Protection--Division of Waste Management, has an ongoing program to monitor water levels at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky. Ground-water-level and precipitation data were collected from 112 wells and 1 rain gage at the Maxey Flats low-level radioactive waste disposal site during October 1988-September 2000. Data were collected on a semi-annual basis from 62 wells, continuously from 6 wells, and monthly or bimonthly from 44 wells (13 of which had continuous recorders installed for the period October 1998-September 2000). One tipping-bucket rain gage was used to collect data at the Maxey Flats site for the period October 1988-September 2000.

Non-Thermal Treatment of Hanford Site Low-Level Mixed Waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

DOE proposes to transport contact-handled LLMW from the Hanford Site to the Allied Technology Group (ATG) Mixed Waste Facility (MWF) in Richland, Washington, for non-thermal treatment and to return the treated waste to the Hanford Site for eventual land disposal. Over a 3-year period the waste would be staged to the ATG MWF, and treated waste would be returned to the Hanford Site. The ATG MWF would be located on an 18 hectare (ha) (45 acre [at]) ATG Site adjacent to ATG's licensed low-level waste processing facility at 2025 Battelle Boulevard. The ATG MWF is located approximately 0.8 kilometers (km) (0.5 miles [mi]) south of Horn Rapids Road and 1.6 km (1 mi) west of Stevens Drive. The property is located within the Horn Rapids triangle in northern Richland (Figure 2.1). The ATG MWF is to be located on the existing ATG Site, near the DOE Hanford Site, in an industrial area in the City of Richland. The effects of siting, construction, and overall operation of the MWF have been evaluated in a separate State Environmental Policy Act (SEPA) EIS (City of Richland 1998). The proposed action includes transporting the LLMW from the Hanford Site to the ATG Facility, non-thermal treatment of the LLMW at the ATG MWF, and transporting the waste from ATG back to the Hanford Site. Impacts fi-om waste treatment operations would be bounded by the ATG SEPA EIS, which included an evaluation of the impacts associated with operating the non-thermal portion of the MWF at maximum design capacity (8,500 metric tons per year) (City of Richland 1998). Up to 50 employees would be required for non-thermal treatment portion of the MWF. This includes 40 employees that would perform waste treatment operations and 10 support staff. Similar numbers were projected for the thermal treatment portion of the MWF (City of Richland 1998).

Siting low-level radioactive waste disposal facilities: The public policy dilemma

International Nuclear Information System (INIS)

English, M.R.

1993-01-01

The book's focus is on one overwhelming problems facing the compacts and states: figuring out where low-level waste disposal sites should be located. The author discusses the central issues underlying this dilemma - authority, trust, risk, justice - and the roles each plays in determining whether the siting processes are regarded as legitimate. The structure of the book provides a mix of narrative, fact and philosophy and adds to the body of well researched information saying that is is not only right but more efficient to develop and implement a just process

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Spent fuel, high-level radioactive waste, or reactor... RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Siting Evaluation Factors § 72.108 Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation. The...

High Mercury Wet Deposition at a "Clean Air" Site in Puerto Rico.

Science.gov (United States)

Shanley, James B; Engle, Mark A; Scholl, Martha; Krabbenhoft, David P; Brunette, Robert; Olson, Mark L; Conroy, Mary E

2015-10-20

Atmospheric mercury deposition measurements are rare in tropical latitudes. Here we report on seven years (April 2005 to April 2012, with gaps) of wet Hg deposition measurements at a tropical wet forest in the Luquillo Mountains, northeastern Puerto Rico, U.S. Despite receiving unpolluted air off the Atlantic Ocean from northeasterly trade winds, during two complete years the site averaged 27.9 μg m(-2) yr(-1) wet Hg deposition, or about 30% more than Florida and the Gulf Coast, the highest deposition areas within the U.S. These high Hg deposition rates are driven in part by high rainfall, which averaged 2855 mm yr(-1). The volume-weighted mean Hg concentration was 9.8 ng L(-1), and was highest during summer and lowest during the winter dry season. Rainout of Hg (decreasing concentration with increasing rainfall depth) was minimal. The high Hg deposition was not supported by gaseous oxidized mercury (GOM) at ground level, which remained near global background concentrations (<10 pg m(-3)). Rather, a strong positive correlation between Hg concentrations and the maximum height of rain detected within clouds (echo tops) suggests that droplets in high convective cloud tops scavenge GOM from above the mixing layer. The high wet Hg deposition at this "clean air" site suggests that other tropical areas may be hotspots for Hg deposition as well.

Conceptual design report for regional low-level waste interim storage site

International Nuclear Information System (INIS)

Bird, M.V.; Thompson, J.D.

1981-08-01

An interim storage site design concept was developed for receiving 100,000 ft 3 low-level waste per year, in the form of solidified wastes in 55-gallon drums with a dose rate of < 200 mrem per hour at contact

QA in the characterization of a low-level waste disposal site

International Nuclear Information System (INIS)

Jacobi, L.R. Jr.

1989-01-01

This paper discusses the implementation of the quality assurance program for the site characterization phase of the Texas low-level radioactive waste disposal facility. The author's thought on implementation of a program with a comparison to the California plan are presented

High-level language computer architecture

CERN Document Server

Chu, Yaohan

1975-01-01

High-Level Language Computer Architecture offers a tutorial on high-level language computer architecture, including von Neumann architecture and syntax-oriented architecture as well as direct and indirect execution architecture. Design concepts of Japanese-language data processing systems are discussed, along with the architecture of stack machines and the SYMBOL computer system. The conceptual design of a direct high-level language processor is also described.Comprised of seven chapters, this book first presents a classification of high-level language computer architecture according to the pr

Other-than-high-level waste

International Nuclear Information System (INIS)

Bray, G.R.

1976-01-01

The main emphasis of the work in the area of partitioning transuranic elements from waste has been in the area of high-level liquid waste. But there are ''other-than-high-level wastes'' generated by the back end of the nuclear fuel cycle that are both large in volume and contaminated with significant quantities of transuranic elements. The combined volume of these other wastes is approximately 50 times that of the solidified high-level waste. These other wastes also contain up to 75% of the transuranic elements associated with waste generated by the back end of the fuel cycle. Therefore, any detailed evaluation of partitioning as a viable waste management option must address both high-level wastes and ''other-than-high-level wastes.''

Correlation between gamma radiation levels and soil radium concentrations at the Edgemont uranium mill site

International Nuclear Information System (INIS)

Wallace, R.G.; Reed, R.P.; Polehn, J.L.; Wilson, G.T.

1985-01-01

The Tennessee Valley Authority's uranium mill in Edgemont, South Dakota, is being decommissioned. Approximately 4 million tons of contaminated tailings, building equipment, and contaminated soil and debris on the mill site will be removed to the disposal site located approximately 3 kilometers to the southeast. To minimize recontamination of cleaned areas, tailings removal will progress from the northwest corner to the southeast corner of the mill site. As specific areas are cleaned, surveys will be conducted to determine if the concentrations of radium-226 in soil are within the limits outlined in 40 CFR, Part 192. Conformance with the criteria will be demonstrated by a gamma survey of the area employing the differential, or delta-measurement, technique. This technique involves fitting the detector with a base and a receptacle for a removable high-density filter. By making measurements with and without the filter in place, a gamma radiation level proportional to the radium-226 concentration in soil can be determined. This paper describes the results obtained in the development of the correlation between the gamma survey measurements and the soil radium concentrations

Correlation between gamma radiation levels and soil radium concentrations at the Edgemont uranium mill site

International Nuclear Information System (INIS)

Wallace, R.G.; Reed, R.P.; Polehn, J.L.; Wilson, G.T.

1986-01-01

The Tennessee Valley Authority's uranium mill in Edgemont, South Dakota is being decommissioned. Approximately 4 million tons of contaminated tailings, building equipment, and contaminated soil and debris on the mill site will be removed to the disposal site located approximately 3 kilometers to the southeast. To minimize recontamination of cleaned areas, tailings removal will progress from the northwest corner to the southeast corner of the mill site. As specific areas are cleaned, surveys will be conducted to determine if the concentrations of radium-226 in soil are within the limits outlined in 40 CFR, Part 192. Conformance with the criteria will be demonstrated by a gamma survey of the area employing the differential, or delta-measurement, technique. This technique involves fitting the detector with a base and a receptacle for a removable high-density filter. By making measurements with and without the filter in place, a gamma radiation level proportional to the radium-226 concentration in soil can be determined. This paper describes the results obtained in the development of the correlation between the gamma survey measurements and the soil radium concentrations

Unsaturated flow and transport through fractured rock related to high-level waste repositories

International Nuclear Information System (INIS)

Evans, D.D.; Rasmussen, T.C.

1991-01-01

Research results are summarized for a US Nuclear Regulatory Commission contract with the University of Arizona focusing on field and laboratory methods for characterizing unsaturated fluid flow and solute transport related to high-level radioactive waste repositories. Characterization activities are presented for the Apache Leap Tuff field site. The field site is located in unsaturated, fractured tuff in central Arizona. Hydraulic, pneumatic, and thermal characteristics of the tuff are summarized, along with methodologies employed to monitor and sample hydrologic and geochemical processes at the field site. Thermohydrologic experiments are reported which provide laboratory and field data related to the effects conditions and flow and transport in unsaturated, fractured rock. 29 refs., 17 figs., 21 tabs

Is Yucca Mountain a long-term solution for disposing of US spent nuclear fuel and high-level radioactive waste?

Science.gov (United States)

Thorne, M C

2012-06-01

On 26 January 2012, the Blue Ribbon Commission on America's Nuclear Future released a report addressing, amongst other matters, options for the managing and disposal of high-level waste and spent fuel. The Blue Ribbon Commission was not chartered as a siting commission. Accordingly, it did not evaluate Yucca Mountain or any other location as a potential site for the storage or disposal of spent nuclear fuel and high-level waste. Nevertheless, if the Commission's recommendations are followed, it is clear that any future proposals to develop a repository at Yucca Mountain would require an extended period of consultation with local communities, tribes and the State of Nevada. Furthermore, there would be a need to develop generally applicable regulations for disposal of spent fuel and high-level radioactive waste, so that the Yucca Mountain site could be properly compared with alternative sites that would be expected to be identified in the initial phase of the site-selection process. Based on what is now known of the conditions existing at Yucca Mountain and the large number of safety, environmental and legal issues that have been raised in relation to the DOE Licence Application, it is suggested that it would be imprudent to include Yucca Mountain in a list of candidate sites for future evaluation in a consent-based process for site selection. Even if there were a desire at the local, tribal and state levels to act as hosts for such a repository, there would be enormous difficulties in attempting to develop an adequate post-closure safety case for such a facility, and in showing why this unsaturated environment should be preferred over other geological contexts that exist in the USA and that are more akin to those being studied and developed in other countries.

Hydrogeological characteristics of Beishan preselected area, Gansu province for China's high-level radioactive waste repository

International Nuclear Information System (INIS)

Guo Yonghai; Yang Tianxiao; Liu Shufen

2001-01-01

Groundwater is the major carrier for radionuclide migration in the high-level radioactive waste disposal. For this reason the hydrogeological study is one of the main contents in repository siting. According to the field investigation which has been carried out during the last few years and some data from the previous study, the author describes the general hydrogeological situation and groundwater circulation, as well as chemical characteristics of groundwater in Beishan preselected area, Gansu province. The research shows that main hydrogeological characteristics of the Beishan area is water-bearing character, low permeability and slow water movement while the major chemical feature of groundwater is high mineralization. This recognition will provide an important basis for repository siting in the site area

Vitrification of low level and mixed (radioactive and hazardous) wastes: Lessons learned from high level waste vitrification

International Nuclear Information System (INIS)

Jantzen, C.M.

1994-01-01

Borosilicate glasses will be used in the USA and in Europe immobilize radioactive high level liquid wastes (HLLW) for ultimate geologic disposal. Simultaneously, tehnologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to immobilize low-level and mixed (radioactive and hazardous) wastes (LLMW) in durable glass formulations for permanent disposal or long-term storage. Vitrification of LLMW achieves large volume reductions (86--97 %) which minimize the associated long-term storage costs. Vitrification of LLMW also ensures that mixed wastes are stabilized to the highest level reasonably possible, e.g. equivalent to HLLW, in order to meet both current and future regulatory waste disposal specifications The tehnologies being developed for vitrification of LLMW rely heavily on the technologies developed for HLLW and the lessons learned about process and product control

Information needs for characterization of high-level waste repository sites in six geologic media. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-05-01

Volume II contains appendices for the following: (1) remote sensing and surface mapping techniques; (2) subsurface mapping methods for site characterization; (3) gravity technique; (4) audio-frequency magnetotelluric technique; (5) seismic refraction technique; (6) direct-current electrical resistivity method; (7) magnetic technique; (8) seismic reflection technique; (9) seismic crosshole method; (10) mechanical downhole seismic velocity survey method; (11) borehole geophysical logging techniques; (12) drilling and coring methods for precharacterization studies; (13) subsurface drilling methods for site characterization; (14) geomechanical/thermomechanical techniques for precharacterization studies; (15)geomechanical/thermal techniques for site characterization studies; (16) exploratory geochemical techniques for precharacterization studies; (17) geochemical techniques for site characterization; (18) hydrologic techniques for precharacterization studies; (19) hydrologic techniques for site characterization; and (20) seismological techniques.

Information needs for characterization of high-level waste repository sites in six geologic media. Volume 2. Appendices

International Nuclear Information System (INIS)

1985-05-01

Volume II contains appendices for the following: (1) remote sensing and surface mapping techniques; (2) subsurface mapping methods for site characterization; (3) gravity technique; (4) audio-frequency magnetotelluric technique; (5) seismic refraction technique; (6) direct-current electrical resistivity method; (7) magnetic technique; (8) seismic reflection technique; (9) seismic crosshole method; (10) mechanical downhole seismic velocity survey method; (11) borehole geophysical logging techniques; (12) drilling and coring methods for precharacterization studies; (13) subsurface drilling methods for site characterization; (14) geomechanical/thermomechanical techniques for precharacterization studies; (15)geomechanical/thermal techniques for site characterization studies; (16) exploratory geochemical techniques for precharacterization studies; (17) geochemical techniques for site characterization; (18) hydrologic techniques for precharacterization studies; (19) hydrologic techniques for site characterization; and (20) seismological techniques

Statewide screening for low-level radioactive waste shallow land burial sites

International Nuclear Information System (INIS)

Staub, W.P.; Cannon, J.B.; Stratton, L.E.

1984-01-01

A methodology was developed for statewide low-level waste site screening based on NRC site selection criteria. The methodology and criteria were tested in Tennessee to determine their effectiveness in narrowing the choice of sites for more intensive localized site screening. The statewide screening methodology entailed two steps. The first step was to select one or more physiographic provinces wherein sites meeting the criteria were most likely to be found. The second step was to select one or more suitable outcrop bands from within the most favorable physiographic provinces. These selections were based entirely on examination of existing literature and maps at scales no larger than 1:250,000. The statewide screening project identified only one suitable physiographic province (the Mississippi Embayment region) and one favorable outcrop band (the Coon Creek Formation) within a three county area of western Tennessee. Ground water monitoring and predictability proved to be the most difficult criterion to meet. This criterion alone eliminated other outcrop bands in the Mississippi Embayment as well as the Eastern Highland Rim and Western Highland Rim physiographic provinces. Other provinces failed to meet several screening criteria. 3 references, 3 figures, 1 table

High performance gamma measurements of equipment retrieved from Hanford high-level nuclear waste tanks

International Nuclear Information System (INIS)

Troyer, G.L.

1997-01-01

The cleanup of high level defense nuclear waste at the Hanford site presents several progressive challenges. Among these is the removal and disposal of various components from buried active waste tanks to allow new equipment insertion or hazards mitigation. A unique automated retrieval system at the tank provides for retrieval, high pressure washing, inventory measurement, and containment for disposal. Key to the inventory measurement is a three detector HPGe high performance gamma spectroscopy system capable of recovering data at up to 90% saturation (200,000 counts per second). Data recovery is based on a unique embedded electronic pulser and specialized software to report the inventory. Each of the detectors have different shielding specified through Monte Carlo simulation with the MCNP program. This shielding provides performance over a dynamic range of eight orders of magnitude. System description, calibration issues and operational experiences are discussed

High performance gamma measurements of equipment retrieved from Hanford high-level nuclear waste tanks

Energy Technology Data Exchange (ETDEWEB)

Troyer, G.L.

1997-03-17

The cleanup of high level defense nuclear waste at the Hanford site presents several progressive challenges. Among these is the removal and disposal of various components from buried active waste tanks to allow new equipment insertion or hazards mitigation. A unique automated retrieval system at the tank provides for retrieval, high pressure washing, inventory measurement, and containment for disposal. Key to the inventory measurement is a three detector HPGe high performance gamma spectroscopy system capable of recovering data at up to 90% saturation (200,000 counts per second). Data recovery is based on a unique embedded electronic pulser and specialized software to report the inventory. Each of the detectors have different shielding specified through Monte Carlo simulation with the MCNP program. This shielding provides performance over a dynamic range of eight orders of magnitude. System description, calibration issues and operational experiences are discussed.

Site selection experience for a new low-level radioactive waste storage/disposal facility at the Savannah River Plant

International Nuclear Information System (INIS)

Towler, O.A.; Cook, J.R.; Helton, B.D.

1985-10-01

Preliminary performance criteria and site selection guides specific to the Savannah River Plant, were developed for a new low-level radioactive waste storage/disposal facility. These site selection guides were applied to seventeen potential sites identified at SRP. The potential site were ranked based on how well they met a set of characteristics considered important in site selection for a low-level radioactive waste disposal facility. The characteristics were given a weighting factor representing its relative importance in meeting site performance criteria. A candidate site was selected and will be the subject of a site characterization program

Second report: development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

1977-11-01

Results are presented of mining and geotechnical studies provided to the University in support of the development of site suitability criteria. The work involved literature research, further evaluation of geotechnical and mining site suitability factors, further development of specific geotechnical descriptions and coefficients relating to uncertainties, additional documentation of descriptors and coefficients developed for the Cycle II model, and geotechnical and mining guidance to the overall LLL site suitability work. Work results are summarized in sections on general site suitability, geotechnical data base, descriptors and coefficients, uncertainty considerations, natural resources, hydrology, geology, and documentation

Siting Criteria for Low and Intermediate Level Radioactive Waste Disposal in Egypt (Proposal approach)

International Nuclear Information System (INIS)

Abdellatif, M.M.

2012-01-01

The objective of radioactive waste disposal is to isolate waste from the surrounding media so that it does not result in undue radiation exposure to humans and the environment. The required degree of isolation can be obtained by implementing various disposal methods and suitable criteria. Near surface disposal method has been practiced for some decades, with a wide variation in sites, types and amounts of wastes, and facility designs employed. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components or barriers: the site, the disposal facility and the waste form. The site selection process for low-level and intermediate level radioactive waste disposal facility addressed a wide range of public health, safety, environmental, social and economic factors. Establishing site criteria is the first step in the sitting process to identify a site that is capable of protecting public health, safety and the environment. This paper is concerning a proposal approach for the primary criteria for near surface disposal facility that could be applicable in Egypt.

PLUTONIUM/HIGH-LEVEL VITRIFIED WASTE BDBE DOSE CALCULATION

Energy Technology Data Exchange (ETDEWEB)

D.C. Richardson

2003-03-19

In accordance with the Nuclear Waste Policy Amendments Act of 1987, Yucca Mountain was designated as the site to be investigated as a potential repository for the disposal of high-level radioactive waste. The Yucca Mountain site is an undeveloped area located on the southwestern edge of the Nevada Test Site (NTS), about 100 miles northwest of Las Vegas. The site currently lacks rail service or an existing right-of-way. If the Yucca Mountain site is found suitable for the repository, rail service is desirable to the Office of Civilian Waste Management (OCRWM) Program because of the potential of rail transportation to reduce costs and to reduce the number of shipments relative to highway transportation. A Preliminary Rail Access Study evaluated 13 potential rail spur options. Alternative routes within the major options were also developed. Each of these options was then evaluated for potential land use conflicts and access to regional rail carriers. Three potential routes having few land use conflicts and having access to regional carriers were recommended for further investigation. Figure 1-1 shows these three routes. The Jean route is estimated to be about 120 miles long, the Carlin route to be about 365 miles long, and Caliente route to be about 365 miles long. The remaining ten routes continue to be monitored and should any of the present conflicts change, a re-evaluation of that route will be made. Complete details of the evaluation of the 13 routes can be found in the previous study. The DOE has not identified any preferred route and recognizes that the transportation issues need a full and open treatment under the National Environmental Policy Act. The issue of transportation will be included in public hearings to support development of the Environmental Impact Statement (EIS) proceedings for either the Monitored Retrievable Storage Facility or the Yucca Mountain Project or both.

PLUTONIUM/HIGH-LEVEL VITRIFIED WASTE BDBE DOSE CALCULATION

International Nuclear Information System (INIS)

D.C. Richardson

2003-01-01

In accordance with the Nuclear Waste Policy Amendments Act of 1987, Yucca Mountain was designated as the site to be investigated as a potential repository for the disposal of high-level radioactive waste. The Yucca Mountain site is an undeveloped area located on the southwestern edge of the Nevada Test Site (NTS), about 100 miles northwest of Las Vegas. The site currently lacks rail service or an existing right-of-way. If the Yucca Mountain site is found suitable for the repository, rail service is desirable to the Office of Civilian Waste Management (OCRWM) Program because of the potential of rail transportation to reduce costs and to reduce the number of shipments relative to highway transportation. A Preliminary Rail Access Study evaluated 13 potential rail spur options. Alternative routes within the major options were also developed. Each of these options was then evaluated for potential land use conflicts and access to regional rail carriers. Three potential routes having few land use conflicts and having access to regional carriers were recommended for further investigation. Figure 1-1 shows these three routes. The Jean route is estimated to be about 120 miles long, the Carlin route to be about 365 miles long, and Caliente route to be about 365 miles long. The remaining ten routes continue to be monitored and should any of the present conflicts change, a re-evaluation of that route will be made. Complete details of the evaluation of the 13 routes can be found in the previous study. The DOE has not identified any preferred route and recognizes that the transportation issues need a full and open treatment under the National Environmental Policy Act. The issue of transportation will be included in public hearings to support development of the Environmental Impact Statement (EIS) proceedings for either the Monitored Retrievable Storage Facility or the Yucca Mountain Project or both

PM Levels, Composition and Evolution in a Highly Industrialised Area. Objectives of Improvement

Science.gov (United States)

Minguillon, M. C.; Querol, X.; Alastuey, A.; Monfort, E.; Mantilla, E.; Miro, J. V.

2007-05-01

Evolution of levels and speciation of PM10 in the ceramic producing area of Castello (East Spain) was studied from April 2002 until December 2005. To this end, daily PM10 sampling was carried out at three urban sites and one suburban site of the area and chemical analyses were made in about 35 % of the samples. Average PM10 levels varied between 27-36 µg/m3 for the study period. The major constituent was mineral matter, exceeding by 5-12 µg/m3 the usual ranges of annual mineral loads in PM10 at similar Spanish urban or regional background sites with no industrial influence. Based on this comparison and on the efficiency of emission abatement techniques, a reduction target of 3-5 µgPM10/m3 of the annual mean seems to be achievable at the urban sites. Moreover, levels of Li, Sc, Co, Zn, As, Se, Rb, Zr, Cd, Cs, Ce, Tl and Pb were higher than the usual range of concentration in urban areas of Spain. Of these elements, Zr, Zn, Pb and As may be considered as tracers of the ceramic emissions from the study area. Their levels showed a simultaneous decrease with the progressive implementation of emission abatement techniques in frit (glaze component for the manufacture of glazed tiles) fusion kilns of the area. Given the high proportion of facilities with implemented abatement techniques at the end of the study period, the reduction margin for these elements is very low.

Blood biomarkers and contaminant levels in feathers and eggs to assess environmental hazards in heron nestlings from impacted sites in Ebro basin (NE Spain)

International Nuclear Information System (INIS)

Barata, C.; Fabregat, M.C.; Cotin, J.; Huertas, D.; Sole, M.; Quiros, L.; Sanpera, C.; Jover, L.; Ruiz, X.; Grimalt, J.O.; Pina, B.

2010-01-01

Blood biomarkers and levels of major pollutants in eggs and feathers were used to determine pollution effects in nestlings of the Purple Heron Ardea purpurea and the Little Egret Egretta garzetta, sampled on three Ebro River (NE Spain) areas: a reference site, a site affected by the effluents of a chlor-alkali industry and the river Delta. The two impacted heron populations showed mutually different pollutant and response patterns, suggesting different sources of contamination. In the population nesting near the chlor-alkali plant, elevated levels of hexachlorobenzene (HCB) and polychlorobiphenyls (PCBs) in eggs, and mercury in feathers in A. purpurea chicks were related with reduced blood antioxidant defenses and increased levels of micronuclei. In Ebro Delta, high levels of plasmatic lactate dehydrogenase in A. purpurea chicks and high frequency of micronuclei in blood of both species were tentatively associated with intensive agricultural activities taking place in the area. These results provide the first evidence of a biological response in heron chicks to the release of pollutants at a chlor-alkali plant. - High levels of organochlorine and mercury levels in eggs and feathers were related with altered blood biomarkers of heron nesting chicks.

Status of technology for isolating high-level radioactive wastes in geologic repositories

International Nuclear Information System (INIS)

Klingsberg, C.; Duguid, J.

1980-10-01

This report attempts to summarize the status of scientific and technological knowledge relevant to long-term isolation of high-level and transuranic wastes in a mined geologic repository. It also identifies and evaluates needed information and identifies topics in which work is under way or needed to reduce uncertainties. The major findings and conclusions on the following topics are presented: importance of the systems approach; prospects for successful isolation of wastes; need for site-specific investigations; human activities in the future; importance of modelling; disposal of transuranic wastes; status of technology of isolation barriers, performance assessment, site selection and characterization, and potential host rocks

Potential host media for a high-level waste repository

Energy Technology Data Exchange (ETDEWEB)

Hustrulid, W

1982-01-01

Earlier studies of burial of radioactive wastes in geologic repositories had concentrated on salt formations for well-publicized reasons. However, under the Carter administration, significant changes were made in the US nuclear waste management program. Changes which were made were: (1) expansion of the number of rock types under consideration; (2) adoption of the multiple-barrier approach to waste containment; (3) additional requirements for waste retrieval; and (4) new criteria proposed by the Nuclear Regulatory Commission for the isolation of high-level waste in geologic repositories. Results of the studies of different types of rocks as repository sites are summarized herein. It is concluded that each generic rock type has certain advantages and disadvantages when considered from various aspects of the waste disposal problem and that characteristics of rocks are so varied that a most favorable or least favorable rock type cannot be easily identified. This lack of definitive characteristics of rocks makes site selection and good engineering barriers very important for containment of the wastes. (BLM)

Environmental assessment for the off-site volume reduction of low-level radioactive waste from the Savannah River Site

International Nuclear Information System (INIS)

1995-07-01

The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1061) for the proposed off-site volume reduction of low-level radioactive wastes (LLW) generated at the Savannah River Site (SRS), near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement (EIS) is not required, and DOE is issuing this Finding of No Significant Impact (FONSI)

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

Anon.

1985-01-01

This study presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste. Broad in scope and balanced in approach, its coverage extends from technological and organizational questions to political ramifications...the environmental impact of building repositories...and even dealing with Indian tribes affected by repository site selection and development. Emphasis is on workable strategies for implementing the National Waste Policy Act of 1982, including a mission plan for the program...a monitored retrievable storage proposal...and a report on mechanisms for financing and managing the program. Nine appendicies are included. They furnish additional data on such topics as policymaking, history, and the system issues resolved in NWPA

Participation in the management of Greek Natura 2000 sites: evidence from a cross-level analysis.

Science.gov (United States)

Apostolopoulou, Evangelia; Drakou, Evangelia G; Pediaditi, Kalliope

2012-12-30

The governance of protected areas has experienced rapid advancement over the last two decades with regard to the inclusion of stakeholders and local communities into the management process. During the same period Greek biodiversity governance has been characterized by a shift, at least on paper, towards the adoption of participatory approaches primarily through the establishment of management agencies. However, this has not been institutionalized for the majority of Natura 2000 sites, thus posing questions on the existence, nature, and effectiveness of participation in sites with no management agency. This is the first conducted large scale, cross level participation analysis for Greek Natura 2000 sites enabling the formation of a representative picture of the situation in the country. We investigated the nature and role of participation in Greek biodiversity governance by exploring both general opinions regarding the national context of participation in Greek Natura 2000 network as well as site-specific opinions regarding three case study areas where Natura 2000 sites have been established. Overall, we analyzed the results of 96 interviews, conducted with national, regional and local level stakeholders and 734 questionnaires conducted with local communities of the three case study areas. Results indicate with non-significant difference among governance levels, or between case study sites, that stakeholders' participation exists mainly on paper whereas community participation is practically absent. Stakeholder engagement seems to take place through administrational documentation across levels and to be locally confined based mainly on personal contacts and initiatives. Interviewees and survey respondents indicated a preference towards improving stakeholders' participation and the community's engagement in the management of Natura 2000 sites. Overall, the results of this study revealed the urgent need for policy initiatives towards adopting meaningful, fair and

Partitioning high-level waste from alkaline solution: A literature survey

International Nuclear Information System (INIS)

Marsh, S.F.

1993-05-01

Most chemical partitioning procedures are designed for acidic feed solutions. However, the high-level waste solutions in the underground storage tanks at US Department of Energy defense production sites are alkaline. Effective partitioning procedures for alkaline solutions could decrease the need to acidify these solutions and to dissolve the solids in acid, which would simplify subsequent processing and decrease the generation of secondary waste. The author compiles candidate technologies from his review of the chemical literature, experience, and personal contacts. Several of these are recommended for evaluation

The application of assessment principles to an operational low level waste disposal site in England

International Nuclear Information System (INIS)

McHugh, J.O.; Newstead, S.; Weedon, C.J.

1988-01-01

This paper reviews the current assessment principles utilized in England and discusses their application to the Drigg low-level Radioactive Waste Disposal Site. The Drigg Site was established in 1959 and the assessment principles were published in 1985; therefore, although the Drigg Site has operated successfully, the application of the assessment principles has caused changes in operations and the establishment of further site research by the Department of the Environment

On-Site Decontamination System for Liquid Low Level Radioactive Waste - 13010

Energy Technology Data Exchange (ETDEWEB)

OSMANLIOGLU, Ahmet Erdal [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)

2013-07-01

This study is based on an evaluation of purification methods for liquid low-level radioactive waste (LLLW) by using natural zeolite. Generally the volume of liquid low-level waste is relatively large and the specific activity is rather low when compared to other radioactive waste types. In this study, a pilot scale column was used with natural zeolite as an ion exchanger media. Decontamination and minimization of LLLW especially at the generation site decrease operational cost in waste management operations. Portable pilot scale column was constructed for decontamination of LLW on site. Effect of temperature on the radionuclide adsorption of the zeolite was determined to optimize the waste solution temperature for the plant scale operations. In addition, effect of pH on the radionuclide uptake of the zeolite column was determined to optimize the waste solution pH for the plant scale operations. The advantages of this method used for the processing of LLLW are discussed in this paper. (authors)

Final disposal of high levels waste and spent nuclear fuel

International Nuclear Information System (INIS)

Gelin, R.

1984-05-01

Foreign and international activities on the final disposal of high-level waste and spent nuclear fuel have been reviewed. A considerable research effort is devoted to development of acceptable disposal options. The different technical concepts presently under study are described in the report. Numerous studies have been made in many countries of the potential risks to future generations from radioactive wastes in underground disposal repositories. In the report the safety assessment studies and existing performance criteria for geological disposal are briefly discussed. The studies that are being made in Canada, the United States, France and Switzerland are the most interesting for Sweden as these countries also are considering disposal into crystalline rocks. The overall time-tables in different countries for realisation of the final disposal are rather similar. Normally actual large-scale disposal operations for high-level wastes are not foreseen until after year 2000. In the United States the Congress recently passed the important Nuclear Waste Policy Act. It gives a rather firm timetable for site-selection and construction of nuclear waste disposal facilities. According to this act the first repository for disposal of commercial high-level waste must be in operation not later than in January 1998. (Author)

Low level radioactive waste disposal siting: a social and technical plan for Pennsylvania. Volume 2. Socioeconomic analyses

International Nuclear Information System (INIS)

Aron, G.; Bord, R.J.; Clemente, F.A.; Dornsife, W.P.; Jarrett, A.R.; Jester, W.A.; Schmalz, R.F.; Witzig, W.F.

1984-09-01

Volume II comprises five chapters: Socioeconomic Screening Criteria for LLRW Facility Siting and An Application to Counties in Pennsylvania; Evaluating Public Participation Options for the Case of Low Level Radioactive Waste Siting in Pennsylvania; Potential Socioeconomic Impacts of a LLRW Facility in Pennsylvania; The Role of Community Incentives in Low Level Radioactive Waste Management; and Institutional Aspects of LLRW Site Development and Operations in Pennsylvania

The management of high-level radioactive wastes

International Nuclear Information System (INIS)

Lennemann, Wm.L.

1979-01-01

The definition of high-level radioactive wastes is given. The following aspects of high-level radioactive wastes' management are discussed: fuel reprocessing and high-level waste; storage of high-level liquid waste; solidification of high-level waste; interim storage of solidified high-level waste; disposal of high-level waste; disposal of irradiated fuel elements as a waste

Utility of the Measurement of Carboxyhemoglobin Level at the Site of Acute Carbon Monoxide Poisoning in Rural Areas

Directory of Open Access Journals (Sweden)

Makoto Onodera

2016-01-01

Full Text Available Objective. This study examined the hypothesis that correlations exist between the carbon monoxide exposure time and the carboxyhemoglobin concentration at the site of carbon monoxide poisoning, using a pulse carbon monoxide oximeter in rural areas or the carboxyhemoglobin concentration measured at a given medical institution. Background. In previous studies, no definitive relationships between the arterial blood carboxyhemoglobin level and the severity of carbon monoxide poisoning have been observed. Method. The subjects included patients treated for acute carbon monoxide poisoning in whom a medical emergency team was able to measure the carboxyhemoglobin level at the site of poisoning. We examined the relationship between the carboxyhemoglobin level at the site of poisoning and carbon monoxide exposure time and the relationships between the arterial blood carboxyhemoglobin level and carbon monoxide exposure time. Results. A total of 10 patients met the above criteria. The carboxyhemoglobin levels at the site of poisoning were significantly and positively correlated with the exposure time (rs = 0.710, p=0.021, but the arterial blood carboxyhemoglobin levels were not correlated with the exposure time. Conclusion. In rural areas, the carboxyhemoglobin level measured at the site of carbon monoxide poisoning correlated with the exposure time.

Utility of the Measurement of Carboxyhemoglobin Level at the Site of Acute Carbon Monoxide Poisoning in Rural Areas.

Science.gov (United States)

Onodera, Makoto; Fujino, Yasuhisa; Kikuchi, Satoshi; Sato, Masayuki; Mori, Kiyofumi; Beppu, Takaaki; Inoue, Yoshihiro

2016-01-01

Objective. This study examined the hypothesis that correlations exist between the carbon monoxide exposure time and the carboxyhemoglobin concentration at the site of carbon monoxide poisoning, using a pulse carbon monoxide oximeter in rural areas or the carboxyhemoglobin concentration measured at a given medical institution. Background. In previous studies, no definitive relationships between the arterial blood carboxyhemoglobin level and the severity of carbon monoxide poisoning have been observed. Method. The subjects included patients treated for acute carbon monoxide poisoning in whom a medical emergency team was able to measure the carboxyhemoglobin level at the site of poisoning. We examined the relationship between the carboxyhemoglobin level at the site of poisoning and carbon monoxide exposure time and the relationships between the arterial blood carboxyhemoglobin level and carbon monoxide exposure time. Results. A total of 10 patients met the above criteria. The carboxyhemoglobin levels at the site of poisoning were significantly and positively correlated with the exposure time (rs = 0.710, p = 0.021), but the arterial blood carboxyhemoglobin levels were not correlated with the exposure time. Conclusion. In rural areas, the carboxyhemoglobin level measured at the site of carbon monoxide poisoning correlated with the exposure time.

Reevaluation Of Vitrified High-Level Waste Form Criteria For Potential Cost Savings At The Defense Waste Processing Facility

International Nuclear Information System (INIS)

Ray, J. W.; Marra, S. L.; Herman, C. C.

2013-01-01

At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

International Nuclear Information System (INIS)

Burgard, K.C.

1998-01-01

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

Energy Technology Data Exchange (ETDEWEB)

Burgard, K.C.

1998-04-09

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

Rethinking high-level radioactive waste disposal: making the safety case

International Nuclear Information System (INIS)

Parker, F.L.

1991-01-01

There is worldwide consensus that geological disposal is best for disposing of high-level radioactive waste; nevertheless, the U.S. program is unlikely to succeed. The program is hampered by its high degree of inflexibility with respect to both schedule and technical specifications that assume the properties and future behavior of a geological repository can be determined and specified with a very high degree of certainty. Geological models, and scientific knowledge generally, have been inappropriately applied. Geophysical analysis can and should have a key role in the assessment of long-term repository isolation; however, geophysial models are being asked to predict the detailed structure and behavior of sites over thousands of years. This is scientifically unsound and will lead to bad engineering practice. The United States has written detailed regulations for repository siting and construction before all of the data are in and is thus bound by requirements that may be impossible to meet. An alternative approach emphasizing flexibility can succeed. It will require time to assess performance, a willingness to respond to problems as they arise, remediation if necessary, and revision of the design and regulations if they are found to impede progress toward the health goal already defined as safe disposal. 6 refs

Methodology for selecting low-level radioactive waste disposal sites with application to the Oak Ridge Reservation

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.

1984-01-01

A methodology was developed to select an environmentally acceptable site for low-level radioactive waste disposal for a predetermined region of interest using prescribed site suitability requirements. The methodology provides a defensible means for identifying candidate areas within the region, candidate sites within the areas, and an environmentally preferred site from the candidate sites. This is accomplished in site screening and site characterization stages. The site screening stage relies on reconnaissance data to identify a preferred site. The site characterization stage relies on a detailed site investigation to determine site acceptability. The methodology was applied to the US Department of Energy Oak Ridge Reservation through the site screening stage. 6 references, 3 figures, 7 tables

Session II-A. Site characterization

International Nuclear Information System (INIS)

McIntosh, W.

1981-01-01

Section II-A on Site Characterization consists of the following papers which describe the progress made during the past fiscal year toward identifying sites for high-level radioactive waste repositories in deep geologic formations: (1) progress in expanded studies for repository sites; (2) evaluation of geologic and hydrologic characteristics in the Basin and Range Province relative to high-level nuclear waste disposal; (3) siting progress: Permian region; (4) Paradox Basin site exploration: a progress report; (5) progress toward recommending a salt site for an exploratory shaft; (6) status of geologic investigations for nuclear waste disposal at the Nevada Test Site; (7) geohydrologic investigation of the Hanford Site, Washington: basalt waste isolation project. Highlights include: expanding studies in crystalline rocks, both in the Appalachian and Lake Superior regions; laying the ground work with the states in the Basin and Range Province to kick off a joint USGS-state province study; narrowing areas of the Permian and Paradox bedded salt regions to a few promising locations; issuing a Gulf Coast Salt Dome Evaluation report (ONWI-109) for public review and comment; narrowing the Nevada Test Site area and Hanford Site area to locations for detailed site investigations and exploratory shafts; progress in developing the subseabed and space disposals alternatives

Validation of the Performance of High-level Waste Disposal System

Energy Technology Data Exchange (ETDEWEB)

Cho, Won Jin; Park, J. H.; Lee, J. O. (and others)

2007-06-15

The experimental researches to validate the integrity and safety of high-level waste disposal system were carried out. The studies on the construction of KURT, and the site rock characteristics were conducted. Thermal-hydro-mechanical behavior of engineered barrier system was investigated using the engineering-scale test facility. The migration and retardation of radionuclide through the rock fracture under anaerobic and reducing condition were studied. The distribution coefficients of radionuclides onto granite, the rock matrix diffusion coefficients, and the gap and grain boundary inventories of spent fuel were measured.

Comprehensive comparison of preselected regions for a high level radioactive waste repository: a subjective quantitative evaluation method

International Nuclear Information System (INIS)

Wang Ju; Zong Zihua; Jin Yuanxin; Zhu Pengfei; Su Rui; Chen Weiming

2012-01-01

Based on the comprehensive features of the 6 preselected regions (Northwest China, Southwest China East China, South China, Inner Mongolia, Xinjiang regions) for China's high level radioactive waste repository, this paper uses the subjective quantitative method to evaluate the weight of each site selection criterion and provides the scores of each region. The results shows that the future natural changes and the hydrogeological conditions are considered as the most important natural siting criteria, while the social impact and human activities are the most important social siting criteria. According to the scores, the priority order of the regions are Northwest China, Xinjiang, Inner Mongolia, South China, East China, Southwest China. On the whole, the scores of' the regions in western China (Northwest China, Xinjiang and Inner Mongolia) are higher than those in eastern China (South China, East China Southwest China), which obviously shows that the participated experts considers that the disposal of high level waste in west China is more favorable than in east China. (authors)

Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

International Nuclear Information System (INIS)

Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

1979-01-01

The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

High mercury wet deposition at a “clean Air” site in Puerto Rico

Science.gov (United States)

Shanley, James B.; Engle, Mark A.; Scholl, Martha A.; Krabbenhoft, David P.; Brunette, Robert; Olson, Mark L.; Conroy, Mary E.

2015-01-01

Atmospheric mercury deposition measurements are rare in tropical latitudes. Here we report on seven years (April 2005 to April 2012, with gaps) of wet Hg deposition measurements at a tropical wet forest in the Luquillo Mountains, northeastern Puerto Rico, U.S. Despite receiving unpolluted air off the Atlantic Ocean from northeasterly trade winds, during two complete years the site averaged 27.9 μg m–2 yr–1 wet Hg deposition, or about 30% more than Florida and the Gulf Coast, the highest deposition areas within the U.S. These high Hg deposition rates are driven in part by high rainfall, which averaged 2855 mm yr–1. The volume-weighted mean Hg concentration was 9.8 ng L–1, and was highest during summer and lowest during the winter dry season. Rainout of Hg (decreasing concentration with increasing rainfall depth) was minimal. The high Hg deposition was not supported by gaseous oxidized mercury (GOM) at ground level, which remained near global background concentrations (<10 pg m–3). Rather, a strong positive correlation between Hg concentrations and the maximum height of rain detected within clouds (echo tops) suggests that droplets in high convective cloud tops scavenge GOM from above the mixing layer. The high wet Hg deposition at this “clean air” site suggests that other tropical areas may be hotspots for Hg deposition as well.

Pairwise comparisons of ten porcine tissues identify differential transcriptional regulation at the gene, isoform, promoter and transcription start site level

International Nuclear Information System (INIS)

Farajzadeh, Leila; Hornshøj, Henrik; Momeni, Jamal; Thomsen, Bo; Larsen, Knud; Hedegaard, Jakob; Bendixen, Christian; Madsen, Lone Bruhn

2013-01-01

Highlights: •Transcriptome sequencing yielded 223 mill porcine RNA-seq reads, and 59,000 transcribed locations. •Establishment of unique transcription profiles for ten porcine tissues including four brain tissues. •Comparison of transcription profiles at gene, isoform, promoter and transcription start site level. •Highlights a high level of regulation of neuro-related genes at both gene, isoform, and TSS level. •Our results emphasize the pig as a valuable animal model with respect to human biological issues. -- Abstract: The transcriptome is the absolute set of transcripts in a tissue or cell at the time of sampling. In this study RNA-Seq is employed to enable the differential analysis of the transcriptome profile for ten porcine tissues in order to evaluate differences between the tissues at the gene and isoform expression level, together with an analysis of variation in transcription start sites, promoter usage, and splicing. Totally, 223 million RNA fragments were sequenced leading to the identification of 59,930 transcribed gene locations and 290,936 transcript variants using Cufflinks with similarity to approximately 13,899 annotated human genes. Pairwise analysis of tissues for differential expression at the gene level showed that the smallest differences were between tissues originating from the porcine brain. Interestingly, the relative level of differential expression at the isoform level did generally not vary between tissue contrasts. Furthermore, analysis of differential promoter usage between tissues, revealed a proportionally higher variation between cerebellum (CBE) versus frontal cortex and cerebellum versus hypothalamus (HYP) than in the remaining comparisons. In addition, the comparison of differential transcription start sites showed that the number of these sites is generally increased in comparisons including hypothalamus in contrast to other pairwise assessments. A comprehensive analysis of one of the tissue contrasts, i

Geochemical information for sites contaminated with low-level radioactive wastes: II. St. Louis Airport Storage Site

International Nuclear Information System (INIS)

Seeley, F.G.; Kelmers, A.D.

1985-01-01

The St. Louis Airport Storage Site (SLASS) became radioactively contaminated as a result of wastes that were being stored from operations to recover uranium from pitchblende ores in the 1940s and 1950s. The US Department of Energy is considering various remedial action options for the SLASS under the Formerly Utilized Site Remedial Action Program (FUSRAP). This report describes the results of geochemical investigations, carried out to support the FUSRAP activities and to aid in quantifying various remedial action options. Soil and groundwater samples from the site were characterized, and sorption ratios for uranium and radium and apparent concentration limit values for uranium were measured in soil/groundwater systems by batch contact methodology. The uranium and radium concentrations in soil samples were significantly above background near the old contaminated surface horizon (now at the 0.3 - to 0.9 - m depth); the maximum values were 1566 μg/g and 101 pCi/g, respectively. Below about the 6 - m depth, the concentrations appeared to be typical of those naturally present in soils of this area (3.8 +- 1.2 μg/g and 3.1 +- 0.6 pCi/g). Uranium sorption ratios showed stratigraphic trends but were generally moderate to high (100 to 1000 L/kg). The sorption isotherm suggested an apparent uranium concentration limit of about 200 mg/L. This relatively high solubility can probably be correlated with the carbonate content of the soil/groundwater systems. The lower sorption ratio values obtained from the sorption isotherm may have resulted from changes in the experimental procedure or the groundwater used. The SLASS appears to exhibit generally favorable behavior for the retardation of uranium solubilized from waste in the site. Parametric tests were conducted to estimate the sensitivity of uranium sorption and solubility to the pH and carbonate content of the system

Waste acceptance product specifications for vitrified high-level waste forms

International Nuclear Information System (INIS)

Applewhite-Ramsey, A.; Sproull, J.F.

1993-01-01

The Nuclear Waste Policy Act of 1982 mandated that all high-level waste (HLW) be sent to a federal geologic repository for permanent disposal. DOE published the Environmental Assessment in 1982 which identified borosilicate glass as the chosen HLW form. 1 In 1985 the Department of Energy instituted a Waste Acceptance Process to assure that DWPF glass waste forms would be acceptable to such a repository. This assurance was important since production of waste forms will precede repository construction and licensing. As part of this Waste Acceptance Process, the DOE Office of Civilian Radioactive Waste Management (RW) formed the Waste Acceptance Committee (WAC). The WAC included representatives from the candidate repository sites, the waste producing sites and DOE. The WAC was responsible for developing the Waste Acceptance Preliminary Specifications (WAPS) which defined the requirements the waste forms must meet to be compatible with the candidate repository geologies

The 1986 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites

International Nuclear Information System (INIS)

1987-12-01

The data are grouped and presented by compact regions. The data include activity and volume by waste classes, generator type, and disposal site. The report uses the volume of low-level waste reported as received at each commercial disposal site as the national baseline figure. A volume of 1,804,998 cubic feet (51,113 cubic meters) of radioactive waste containing 233,726 curies of activity was reported disposed at the commercial sites in 1986. The total volume and curie values tabulated for each state were obtained directly from the commercial disposal site operators. The total is the sum of the volume and radioactivity reported by Chem Nuclear Systems, Inc., and US Ecology for each state. Sixty-three percent of low-level waste volumes disposed at commercial sites was assigned to the state of origin. These volumes represent those disposed at Beatty and Barnwell disposal sites. Thirty-seven percent, or 665,066 cubic feet (18,831 cubic meters), of the waste disposed in the US in 1986 went to the Richland site. 8 refs., 75 figs., 4 tabs

Seismic design ampersand analysis considerations for high level nuclear waste repositories

International Nuclear Information System (INIS)

Hossain, Q.A.

1993-01-01

A high level nuclear waste repository, like the one at Nevada's Yucca Mountain that is being investigated for site suitability, will have some unique seismic design and analysis considerations. These are discussed, and a design philosophy that can rationally account for the unique performance objectives of such facilities is presented. A case is made for the use of DOE's performance goal-based seismic design and evaluation methodology that is based on a hybrid open-quotes deterministicclose quotes and open-quotes probabilisticclose quotes concept. How and to what extent this methodology should be modified to adopt it for a potential site like Yucca Mountain is also outlined. Finally, the issue of designing for seismic fault rupture is discussed briefly, and the desirability of using the proposed seismic design philosophy in fault rupture evaluation is described

Seismic design and analysis considerations for high level nuclear waste repositories

International Nuclear Information System (INIS)

Hossain, Q.A.

1993-01-01

A high level nuclear waste repository, like the one at Nevada's Yucca Mountain that is being investigated for site suitability, will have some unique seismic design and analysis considerations. These are discussed, and a design philosophy that can rationally account for the unique performance objectives of such facilities is presented. A case is made for the use of DOE's performance goal-based seismic design and evaluation methodology that is based on a hybrid ''deterministic'' and ''probabilistic'' concept. How and to what extent this methodology should be modified to adopt it for a potential site like Yucca Mountain is also outlined. Finally, the issue of designing for seismic fault rupture is discussed briefly, and the desirability of using the proposed seismic design philosophy in fault rupture evaluation is described

RPython high-level synthesis

Science.gov (United States)

Cieszewski, Radoslaw; Linczuk, Maciej

2016-09-01

The development of FPGA technology and the increasing complexity of applications in recent decades have forced compilers to move to higher abstraction levels. Compilers interprets an algorithmic description of a desired behavior written in High-Level Languages (HLLs) and translate it to Hardware Description Languages (HDLs). This paper presents a RPython based High-Level synthesis (HLS) compiler. The compiler get the configuration parameters and map RPython program to VHDL. Then, VHDL code can be used to program FPGA chips. In comparison of other technologies usage, FPGAs have the potential to achieve far greater performance than software as a result of omitting the fetch-decode-execute operations of General Purpose Processors (GPUs), and introduce more parallel computation. This can be exploited by utilizing many resources at the same time. Creating parallel algorithms computed with FPGAs in pure HDL is difficult and time consuming. Implementation time can be greatly reduced with High-Level Synthesis compiler. This article describes design methodologies and tools, implementation and first results of created VHDL backend for RPython compiler.

Determining site-specific background level with geostatistics for remediation of heavy metals in neighborhood soils

Directory of Open Access Journals (Sweden)

Tammy M. Milillo

2017-03-01

Full Text Available The choice of a relevant, uncontaminated site for the determination of site-specific background concentrations for pollutants is critical for planning remediation of a contaminated site. The guidelines used to arrive at concentration levels vary from state to state, complicating this process. The residential neighborhood of Hickory Woods in Buffalo, NY is an area where heavy metal concentrations and spatial distributions were measured to plan remediation. A novel geostatistics based decision making framework that relies on maps generated from indicator kriging (IK and indicator co-kriging (ICK of samples from the contaminated site itself is shown to be a viable alternative to the traditional method of choosing a reference site for remediation planning. GIS based IK and ICK, and map based analysis are performed on lead and arsenic surface and subsurface datasets to determine site-specific background concentration levels were determined to be 50 μg/g for lead and 10 μg/g for arsenic. With these results, a remediation plan was proposed which identified regions of interest and maps were created to effectively communicate the results to the environmental agencies, residents and other interested parties.

Topic I: Induced changes in hydrology at low-level radioactive waste repository sites: A section in Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings (Circular 1036)

Science.gov (United States)

Prudic, David E.; Dennehy, Kevin F.; Bedinger, Marion S.; Stevens, Peter R.

1990-01-01

Engineering practices, including the excavation of trenches, placement of waste, nature of waste forms, backfilling procedures and materials, and trench-cover construction and materials at low-level radioactive-waste repository sites greatly affect the geohydrology of the sites. Engineering practices are dominant factors in eventual stability and isolation of the waste. The papers presented relating to Topic I were discussions of the hydrogeologic setting at existing low-level radioactive-waste repository sites and changes in the hydrology induced by site operations. Papers summarizing detailed studies presented at this workshop include those at sites near Sheffield, Ill.; Oak Ridge National Laboratory, Tenn.; West Valley, N.Y.; Maxey Flats, Ky.; Barnwell, S.C.; and Beatty, Nev. 

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

International Nuclear Information System (INIS)

Di Sanza, E.F.; Carilli, J.T.

2006-01-01

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now requiring attention. The U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NSO) Environmental Management Program is charged with the responsibility of carrying out the disposal of onsite and off-site defense-generated and research-related LLW at the Nevada. Test Site (NTS). The NSO and its generator community are constantly pursuing new LLW disposal techniques while meeting the core mission of safe and cost-effective disposal that protects the worker, the public and the environment. From trenches to present-day super-cells, the NTS disposal techniques must change to meet the LLW generator's disposal needs. One of the many ways the NTS is addressing complex waste streams is by designing waste specific pits and trenches. This ensures unusual waste streams with high-activity or large packaging have a disposal path. Another option the NTS offers is disposal of classified low-level radioactive-contaminated material. In order to perform this function, the NTS has a safety plan in place as well as a secure facility. By doing this, the NTS can accept DOE generated classified low-level radioactive-contaminated material that would be equivalent to U.S. Nuclear Regulatory Commission Class B, C, and Greater than Class C waste. In fiscal year 2006, the NTS will be the only federal disposal facility that will be able to dispose mixed low-level radioactive waste (MLLW) streams. This is an activity that is highly anticipated by waste generators. In order for the NTS to accept MLLW, generators will have to meet the stringent requirements of the NTS

Performance Assessment Monitoring Plan for the Hanford Site Low-Level Burial Grounds

International Nuclear Information System (INIS)

2006-01-01

The U.S. Department of Energy Order 435.1, Radioactive Waste Management, requires a disposal authorization statement authorizing operation (or continued operation) for low-level waste disposal facilities. In fulfillment of these requirements, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area burial grounds and the 200 West Area burial grounds. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area low-level burial grounds be written and approved by the Richland Operations Office. As a result of a record of decision for the Hanford Site Solid Waste Program and acceptance of the Hanford Site Solid Waste Environmental Impact Statement, the use of the low-level burial ground (LLBG) as a disposal facility for low-level and mixed low-level wastes has been restricted to lined trenches and the Navy reactor-compartment trench only. Hence, as of July 2004, only the two lined trenches in burial ground 218-W-5 (trenches 31 and 34, see Appendix A) and the Navy reactor-compartment trench in burial ground 218 E 12B (trench 94) are allowed to receive waste. When the two lined trenches are filled, the LLBG will cease to operate except for reactor compartment disposal at trench 94. Remaining operational lifetime of the LLBG is dependent on waste volume disposal rates. Existing programs for air sampling and analyses and subsidence monitoring are currently adequate for performance assessment at the LLBG. The waste disposal authorization for the Hanford Site is based (in part) on the post-closure performance assessments for the LLBG. In order to maintain a useful link between operational monitoring (e.g., Resource Conservation and Recovery Act [RCRA], Comprehensive Environmental Response, Compensation, and Liability Act, and State Waste Discharge Permits), constituents, monitoring frequencies, and boundaries require

Environmental Assessment for the Closure of the High-Level Waste Tanks in F- & H-Areas at the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

N/A

1996-07-31

This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the closure of 51 high-level radioactive waste tanks and tank farm ancillary equipment (including transfer lines, evaporators, filters, pumps, etc) at the Savannah River Site (SRS) located near Aiken, South Carolina. The waste tanks are located in the F- and H-Areas of SRS and vary in capacity from 2,839,059 liters (750,000 gallons) to 4,921,035 liters (1,300,000 gallons). These in-ground tanks are surrounded by soil to provide shielding. The F- and H-Area High-Level Waste Tanks are operated under the authority of Industrial Wastewater Permits No.17,424-IW; No.14520, and No.14338 issued by the South Carolina Department of Health and Environmental Control (SCDHEC). In accordance with the Permit requirements, DOE has prepared a Closure Plan (DOE, 1996) and submitted it to SCDHEC for approval. The Closure Plan identifies all applicable or relevant and appropriate regulations, statutes, and DOE Orders for closing systems operated under the Industrial Wastewater Permits. When approved by SCDHEC, the Closure Plan will present the regulatory process for closing all of the F- and H-Area High Level Waste Tanks. The Closure Plan establishes performance objectives or criteria to be met prior to closing any tank, group of tanks, or ancillary tank farm equipment. The proposed action is to remove the residual wastes from the tanks and to fill the tanks with a material to prevent future collapse and bind up residual waste, to lower human health risks, and to increase safety in and around the tanks. If required, an engineered cap consisting of clay, backfill (soil), and vegetation as the final layer to prevent erosion would be applied over the tanks. The selection of tank system closure method will be evaluated against the following Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) criteria described in 40

Developments in support of low level waste disposal at BNFL's Drigg Site

International Nuclear Information System (INIS)

Johnson, L.F.

1988-01-01

The continued upgrading of low-level waste pretreatment and disposal practices related to the United Kingdom Drigg disposal site is described, noting the need to take into account operational safety, long term post-closure safety, regulatory and public acceptance factors

National Low-Level Radioactive Waste Management Program. Use of compensation and incentives in siting Low-Level Radioactive Waste Disposal Facilities. Revision 1

International Nuclear Information System (INIS)

1985-10-01

This document was prepared to increase understanding of compensation and incentives as they pertain to the siting of Low-Level Radioactive Waste Disposal Facilities. Compensation and incentives are discussed as methods to facilitate siting Low-Level Radioactive Waste Facilities. Compensations may be in the form of grants to enable host communities to evaluate potential impacts of the proposed facility. Compensations may also include reimbursements to the host community for costs incurred during facility construction, operation and closure. These may include required improvements to local roads, new equipment, and payments for revenue losses in local property taxes when disposal sites are removed from the tax base. Incentives provide benefits to the community beyond the costs directly related to the operation of the facility. Greater local control over waste facilities can be a powerful incentive. Local officials may be more willing to accept a facility if they have some control over the operation and monitoring associated with the facility. Failure to secure new disposal sites may cause such problems as illegal dumping which would create public health hazards. Also, lack of disposal capacity may restrict research and medical use of radioactive materials. The use of compensation and incentives may increase acceptance of communities for hosting a low-level waste disposal facility

Ecological assessment of oil-gas producing area in Kazakhstan zone of Caspian sea and using the bioremediation technology for cleaning of high level oil polluted sites

International Nuclear Information System (INIS)

Bigaliev, A.A.; Ishanova, N.E.; Bijazheva, S.M.; Novikova, A.; Bigaliev, A.B.

2008-01-01

A significant part of mineral raw material resources of Kazakhstan placed in the depth of the Caspian region, where more than 90% extracting of oil and natural gas, 100% balance store rare ground, 3.2% uranium, ore 0.3%, 90.5% sawn store concentrated. Last years, it takes intensive works by extraction of carbon raw materials in Kazakhstan sector of the Caspian sea. It brought to exceeding of coastal pollution at the North and middle the Caspian coastal pollution with oil products in average till 0.282 mg/l. Maximum meaning oil product pollution reaches 0.56 mg/l (which means exceeding of limited concentration on 11 times). How much money need to cover cost of remediation in real sites? Develop of assessment and monitoring procedures based on fate mechanisms for most of representative hydrocarbons in polluted soils. Step 1 - Collection of heavily polluted portions of soils, separation of hydrocarbons by cost efficient mechanical procedures and send HC rich material (HC>95%) to prepare of alternative fuel. Return of low HC content sand to project area (HC<5.0%). Step 2 - Development of low cost bioremediation procedures in areas transformed to moderately polluted site (HC<5% after removing of heavily polluted portions) with uniform HC content. We are needed to develop of coast efficiency approach for cleaning of high level oily polluted sites around urban areas in Kazakhstan new methodology to estimate polluted area and recover of pollution history, low cost bioremediation

Environmental program overview for a high-level radioactive waste repository at Yucca Mountain

International Nuclear Information System (INIS)

1988-12-01

The United States plans to begin operating the first repository for the permanent disposal of high-level nuclear waste early in the next century. In February 1983, the US Department of Energy (DOE) identified Yucca Mountain, in Nevada, as one of nine potentially acceptable sites for a repository. To determine its suitability, the DOE evaluated the Yucca Mountain site, along with eight other potentially acceptable sites, in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. The purpose of the Environmental Program Overview (EPO) for the Yucca Mountain site is to provide an overview of the overall, comprehensive approach being used to satisfy the environmental requirements applicable to sitting a repository at Yucca Mountain. The EPO states how the DOE will address the following environmental areas: aesthetics, air quality, cultural resources (archaeological and Native American components), noise, radiological studies, soils, terrestrial ecosystems, and water resources. This EPO describes the environmental program being developed for the sitting of a repository at Yucca Mountain. 1 fig., 3 tabs

Opting for cooperation: A case study in siting a low level radioactive waste management facility

International Nuclear Information System (INIS)

Armour, A.

1991-01-01

In 1976, the Canadian federal government called a halt to efforts by a crown corporation to site a low-level radioactive waste management facility when it became apparent that continuation of the siting process would likely result in significant social disruption and political conflict. It established an independent six-person Task Force to advise it on how to proceed. Twelve months later, the Task Force put forward a radically different siting process based on the voluntary participation of communities and collaborative, joint problem-solving and decision making. Cabinet endorsed the approach and in September 1988 authorized the Task Force to begin implementing the recommended process. The first three phases of the process have been implemented and so far it appears to be achieving its desired objective -- to encourage less confrontation and more cooperation in the siting of the low-level radioactive waste management facility

Technical baseline description of high-level waste and low-activity waste feed mobilization and delivery

International Nuclear Information System (INIS)

Papp, I.G.

1997-01-01

This document is a compilation of information related to the high-level waste (HLW) and low-activity waste (LAW) feed staging, mobilization, and transfer/delivery issues. Information relevant to current Tank Waste Remediation System (TWRS) inventories and activities designed to feed the Phase I Privatization effort at the Hanford Site is included. Discussions on the higher level Phase II activities are offered for a perspective on the interfaces

Nevada test site low-level and mixed waste repository design in the unsaturated zone

International Nuclear Information System (INIS)

Kawamura, T.A.; Warren, D.M.

1989-01-01

The Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) is used for shallow land disposal of Low-Level Radioactive (LLW) and for retrievable disposal of Mixed Wastes (MW) from various Department of Energy (DOE) facilities. The site is situated in southern Nevada, one of the most arid regions of the United States. Design considerations include vadose zone monitoring in lieu of groundwater monitoring, stringent waste acceptance and packaging criteria, a waste examination and real-time radiography facility, and trench design. 4 refs

NOx AND HETEROGENEITY EFFECTS IN HIGH LEVEL WASTE (HLW)

International Nuclear Information System (INIS)

Meisel, Dan; Camaioni, Donald M.; Orlando, Thom

2000-01-01

We summarize contributions from our EMSP supported research to several field operations of the Office of Environmental Management (EM). In particular we emphasize its impact on safety programs at the Hanford and other EM sites where storage, maintenance and handling of HLW is a major mission. In recent years we were engaged in coordinated efforts to understand the chemistry initiated by radiation in HLW. Three projects of the EMSP (''The NOx System in Nuclear Waste,'' ''Mechanisms and Kinetics of Organic Aging in High Level Nuclear Wastes, D. Camaioni--PI'' and ''Interfacial Radiolysis Effects in Tanks Waste, T. Orlando--PI'') were involved in that effort, which included a team at Argonne, later moved to the University of Notre Dame, and two teams at the Pacific Northwest National Laboratory. Much effort was invested in integrating the results of the scientific studies into the engineering operations via coordination meetings and participation in various stages of the resolution of some of the outstanding safety issues at the sites. However, in this Abstract we summarize the effort at Notre Dame

Measuring site occupancy

DEFF Research Database (Denmark)

Rogowska-Wrzesinska, Adelina; Wojdyla, Katarzyna; Williamson, James

2014-01-01

occupancy of the modification site. We show that, on one hand, heavily modified cysteines are not necessarily involved in the response to oxidative stress. On the other hand residues with low modification level can be dramatically affected by mild oxidative imbalance. We make use of high resolution mass...... peptides corresponding to 90 proteins. Only 6 modified peptides changed significantly under mild oxidative stress. Quantitative information allowed us to determine relative modification site occupancy of each identified modified residue and pin point heavily modified ones. The method proved to be precise...... and sensitive enough to detect and quantify endogenous levels of oxidative stress on proteome-wide scale and brings a new perspective on the role of the modification site occupancy in cellular redox response....

Spent nuclear fuel project high-level information management plan

Energy Technology Data Exchange (ETDEWEB)

Main, G.C.

1996-09-13

This document presents the results of the Spent Nuclear Fuel Project (SNFP) Information Management Planning Project (IMPP), a short-term project that identified information management (IM) issues and opportunities within the SNFP and outlined a high-level plan to address them. This high-level plan for the SNMFP IM focuses on specific examples from within the SNFP. The plan`s recommendations can be characterized in several ways. Some recommendations address specific challenges that the SNFP faces. Others form the basis for making smooth transitions in several important IM areas. Still others identify areas where further study and planning are indicated. The team`s knowledge of developments in the IM industry and at the Hanford Site were crucial in deciding where to recommend that the SNFP act and where they should wait for Site plans to be made. Because of the fast pace of the SNFP and demands on SNFP staff, input and interaction were primarily between the IMPP team and members of the SNFP Information Management Steering Committee (IMSC). Key input to the IMPP came from a workshop where IMSC members and their delegates developed a set of draft IM principles. These principles, described in Section 2, became the foundation for the recommendations found in the transition plan outlined in Section 5. Availability of SNFP staff was limited, so project documents were used as a basis for much of the work. The team, realizing that the status of the project and the environment are continually changing, tried to keep abreast of major developments since those documents were generated. To the extent possible, the information contained in this document is current as of the end of fiscal year (FY) 1995. Programs and organizations on the Hanford Site as a whole are trying to maximize their return on IM investments. They are coordinating IM activities and trying to leverage existing capabilities. However, the SNFP cannot just rely on Sitewide activities to meet its IM requirements

Determining site-specific background level with geostatistics for remediation of heavy metals in neighborhood soils

OpenAIRE

Tammy M. Milillo; Gaurav Sinha; Joseph A. Gardella Jr.

2017-01-01

The choice of a relevant, uncontaminated site for the determination of site-specific background concentrations for pollutants is critical for planning remediation of a contaminated site. The guidelines used to arrive at concentration levels vary from state to state, complicating this process. The residential neighborhood of Hickory Woods in Buffalo, NY is an area where heavy metal concentrations and spatial distributions were measured to plan remediation. A novel geostatistics based decision ...

System Specification for Immobilized High-Level Waste Interim Storage

International Nuclear Information System (INIS)

CALMUS, R.B.

2000-01-01

This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

Status of the Texas low-level radioactive waste disposal site - construction sequencing and staffing patterns

International Nuclear Information System (INIS)

Jacobi, L.R. Jr.

1996-01-01

The Texas Low-Level Radioactive Waste Disposal Authority, an agency of the State of Texas, has been attempting to develop a site for the disposal of low-level radioactive waste in Texas for more than fourteen years. Since 1991, the agency has been evaluating a site near Sierra Blanca, in far west Texas. Site characterization was completed in 1992, and a license application was filed that year. Construction plans were completed in 1993. In April 1996, the licensing agency, the Texas Natural Resource Conservation Commission, completed its review and proposed to issue a license. The administrative hearings on the proposed license should be completed by July 1997. The Authority is prepared to begin construction and operations as soon as a final license can be issued

A critically educated public explores high level radioactive waste management

International Nuclear Information System (INIS)

Blum, J.E.

1994-01-01

It is vital to the citizens of Nevada that they and their children are given an opportunity to explore all sides of the characterization of Yucca Mountain as a potential repository site for spent nuclear fuel. The state-wide, national and international implications demand a reasoned and complete approach to this issue, which has become emotionally and irrationally charged and fueled by incomplete perception and information. The purpose of this paper is to provide curriculum suggestions and recommend concomitant policy developments that will lead to the implementation of a Critical Thinking (CT) approach to High Level Radioactive Waste Management

High potassium level

Science.gov (United States)

... level is very high, or if you have danger signs, such as changes in an ECG . Emergency ... Seifter JL. Potassium disorders. In: Goldman L, Schafer AI, eds. Goldman-Cecil Medicine . 25th ed. Philadelphia, PA: ...

High-level Petri Nets

DEFF Research Database (Denmark)

various journals and collections. As a result, much of this knowledge is not readily available to people who may be interested in using high-level nets. Within the Petri net community this problem has been discussed many times, and as an outcome this book has been compiled. The book contains reprints...... of some of the most important papers on the application and theory of high-level Petri nets. In this way it makes the relevant literature more available. It is our hope that the book will be a useful source of information and that, e.g., it can be used in the organization of Petri net courses. To make......High-level Petri nets are now widely used in both theoretical analysis and practical modelling of concurrent systems. The main reason for the success of this class of net models is that they make it possible to obtain much more succinct and manageable descriptions than can be obtained by means...

Hydraulic containment of low-level radioactive waste disposal sites: [Final technical report

International Nuclear Information System (INIS)

Ostendorf, D.W.; Noss, R.R.; Miller, A.B.; Phillips, H.S.

1987-01-01

This document describes the use of impermeable barriers for the containment of liquid radioactive wastes at low-level radioactive waste disposal sites. Included are a review of existing barrier systems, assessments of laboratory and field data, and simulations of system performance under humid and arid conditions. Alternatives are identified as the most promising of the existing systems based on retention of irradiated water, field installation feasibility, and response to aggressive permeation. In decreasing order of preference, the favored systems are asphalt slurry, high density polyethylene synthetic liner, polyvinyl chloride synthetic liner, lean portland cement concrete, and compacted bentonite liner. It should be stressed that all five of these alternatives effectively retain irradiated water in the humid and arid simulations. Recommendations on the design and operation of the hydraulic containment system and suggestions on avenues for future research are included. 102 refs., 27 figs., 23 tabs

Siting Study for the Remote-Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

Application of a visual soil examination and evaluation technique at site and farm level

NARCIS (Netherlands)

Sonneveld, M.P.W.; Heuvelink, G.B.M.; Moolenaar, S.W.

2014-01-01

Visual soil examination and evaluation (VSEE) techniques are semi-quantitative methods that provide rapid and cost-effective information on soil quality. These are mostly applied at site or field level, but there is an increased need for soil quality indicators at farm level to allow integration

The status of siting activities for a low level waste repository in the Philippines

International Nuclear Information System (INIS)

Valdezco, E.M.; Visitacion, M.; Palattao, B.; Marcelo, E.A.; Venida, L.L.

2001-01-01

The process of site selection for a low level waste repository was initiated in 1976 when the Philippine Government decided to go nuclear and constructed the first Philippine Nuclear Power Plant in the Bataan Peninsula. However, all siting activities were suspended when the nuclear power plant was mothballed and the final decision was made to convert the plant into a combined cycle power plant. In 1995, an inter-agency committee was created under the Nuclear Power Steering Committee and mandated to conduct studies on siting of radioactive waste disposal facilities, and at the same time, perform R and D activities in support of the project. This paper describes the various siting activities carried out to date. (author)

Vitrification technology for Hanford Site tank waste

International Nuclear Information System (INIS)

Weber, E.T.; Calmus, R.B.; Wilson, C.N.

1995-04-01

The US Department of Energy's (DOE) Hanford Site has an inventory of 217,000 m 3 of nuclear waste stored in 177 underground tanks. The DOE, the US Environmental Protection Agency, and the Washington State Department of Ecology have agreed that most of the Hanford Site tank waste will be immobilized by vitrification before final disposal. This will be accomplished by separating the tank waste into high- and low-level fractions. Capabilities for high-capacity vitrification are being assessed and developed for each waste fraction. This paper provides an overview of the program for selecting preferred high-level waste melter and feed processing technologies for use in Hanford Site tank waste processing

Geological disposal of high level radioactive waste in China: progress during 1985-2004

International Nuclear Information System (INIS)

Wang Ju; Xu Guoqing; Zheng Hualing; Fan Xianhua; Wang Chengzu; Fan Zhiwen

2005-01-01

Safe disposal of high level radioactive waste (HLW) is a challenging issue for the sustainable development of nuclear energy. The studies for the disposal of HLW in China started in 1985, the proposed goal was to build China's high level waste repository by mid-21st Century, while the waste to be disposed of will be vitrified waste, transuranic waste and small amount of spent fuel. The proposed repository was a shaft-tunnel-silo model hosted by granite in saturated zone. In the period of 1985 to 2004, progress was made in China's HLW disposal program. It was decided that 'deep geological disposal' will be used to dispose of China's HLW, while the technical strategy for the development of repository will a 3-step strategy, that includes steps of site selection and site evaluation, construction of underground research laboratory, and construction of repository. Based on nation wide screening, the Beishan area, Gansu Province, northwestern China, located in Gobi desert area with few inhabitants, integral crust structure and favorable geological and hydrogeological conditions, was selected as the most potential area for China's repository. In early 1990's, site selection for underground research laboratory was conducted, 2 sites in the suburb of Beijing were preliminarily selected as the potential sites for a 'generic underground research laboratory'. It was determined to use bentonite as backfill material for the repository, while the bentonite from Gaomiaozi deposit in Inner Mongolia was selected as potential buffer and backfill material for China's repository. The studies on the mineralogical, geotechnical, physico-mechanical and thermal properties of the Gaomiaozi bentonite have been conducting. Some parameters such as sorption radio, diffusion coefficient and dispersion coefficient of radionuclides (Np, Pu and Tc) in Beishan granite and bentonite have been obtained. A low-oxygen glove box and a device simulating the temperature, pressure and redox potential of

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Bullen, D.B.; Gdowski, G.E.

1988-08-01

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of high-level radioactive-waste disposal containers. The waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The copper-based alloy materials are CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The austenitic materials are Types 304L and 316L stainless steels and Alloy 825. The waste-package containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr, and they must be retrievable from the disposal site during the first 50 yr after emplacement. The containers will be exposed to high temperatures and high gamma radiation fields from the decay of high-level waste. This volume surveys the available data on the phase stability of both groups of candidate alloys. The austenitic alloys are reviewed in terms of the physical metallurgy of the iron-chromium-nickel system, martensite transformations, carbide formation, and intermetallic-phase precipitation. The copper-based alloys are reviewed in terms of their phase equilibria and the possibility of precipitation of the minor alloying constituents. For the austenitic materials, the ranking based on phase stability is: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is: CDA 102 (oxygen-free copper) (best), and then both CDA 715 and CDA 613. 75 refs., 24 figs., 6 tabs

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Gdowski, G.E.; Bullen, D.B.

1988-08-01

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of containers for disposal of high-level radioactive waste. This waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr. During the first 50 yr after emplacement, they must be retrievable from the disposal site. Shortly after the containers are emplaced in the repository, they will be exposed to high temperatures and high gamma radiation fields from the decay of the high-level waste. This volume surveys the available data on oxidation and corrosion of the iron- to nickel-based austenitic materials (Types 304L and 316L stainless steels and Alloy 825) and the copper-based alloy materials [CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni)], which are the present candidates for fabrication of the containers. Studies that provided a large amount of data are highlighted, and those areas in which little data exists are identified. Examples of successful applications of these materials are given. On the basis of resistance to oxidation and general corrosion, the austenitic materials are ranked as follows: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is as follows: CDA 715 and CDA 613 (both best), and CDA 102 (worst). 110 refs., 30 figs., 13 tabs

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Energy Technology Data Exchange (ETDEWEB)

Gdowski, G.E.; Bullen, D.B. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-08-01

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of containers for disposal of high-level radioactive waste. This waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr. During the first 50 yr after emplacement, they must be retrievable from the disposal site. Shortly after the containers are emplaced in the repository, they will be exposed to high temperatures and high gamma radiation fields from the decay of the high-level waste. This volume surveys the available data on oxidation and corrosion of the iron- to nickel-based austenitic materials (Types 304L and 316L stainless steels and Alloy 825) and the copper-based alloy materials (CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni)), which are the present candidates for fabrication of the containers. Studies that provided a large amount of data are highlighted, and those areas in which little data exists are identified. Examples of successful applications of these materials are given. On the basis of resistance to oxidation and general corrosion, the austenitic materials are ranked as follows: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is as follows: CDA 715 and CDA 613 (both best), and CDA 102 (worst). 110 refs., 30 figs., 13 tabs.

Performance Assessment Monitoring Plan for the Hanford Site Low-Level Waste Burial Grounds

International Nuclear Information System (INIS)

SONNICHSEN, J.C.

2000-01-01

As directed by the U.S. Department of Energy (DOE), Richland Operations Office (DOE-RL), Fluor Hanford, Inc. will implement the requirements of DOE Order 435.1, Radioactive Waste Management, as the requirements relate to the continued operation of the low-level waste disposal facilities on the Hanford Site. DOE Order 435.1 requires a disposal authorization statement authorizing operation (or continued operation) of a low-level waste disposal facility. The objective of this Order is to ensure that all DOE radioactive waste is managed in a manner that protects the environment and personnel and public health and safety. The manual (DOE Order 435.1 Manual) implementing the Order states that a disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) of 1980 documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility. Failure to obtain a disposal authorization statement shall result in shutdown of an operational disposal facility. In fulfillment of the requirements of DOE Order 435.1, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area and the 200 West Area Low-Level Burial Grounds. The disposal authorization statement constitutes approval of the performance assessment and composite analysis, authorizes operation of the facility, and includes conditions that the disposal facility must meet. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area Low-Level Burial Grounds be written and approved by the DOE-RL. The monitoring plan is to be updated and implemented within 1 year following issuance of the disposal authorization statement to