Unclassified Source Term And Radionuclide Data For Corrective Action Unit 98
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Unclassified Source Term And Radionuclide Data For Corrective Action Unit 98
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Author :
language : en
Publisher:
Release Date : 2005
Unclassified Source Term And Radionuclide Data For Corrective Action Unit 98 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2005 with categories.
Frenchman Flat is one of several areas of the Nevada Test Site (NTS) used for underground nuclear testing (Figure 1-1). These nuclear tests resulted in groundwater contamination in the vicinity of the underground test areas. As a result, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is currently conducting a corrective action investigation (CAI) of the Frenchman Flat underground test areas. Since 1996, the Nevada Division of Environmental Protection (NDEP) has regulated NNSA/NSO corrective actions through the ''Federal Facility Agreement and Consent Order'' ([FFACO], 1996). Appendix VI of the FFACO agreement, ''Corrective Action Strategy'', was revised on December 7, 2000, and describes the processes that will be used to complete corrective actions, including those in the Underground Test Area (UGTA) Project. The individual locations covered by the agreement are known as corrective action sites (CASs), which are grouped into corrective action units (CAUs). The UGTA CASs are grouped geographically into five CAUs: Frenchman Flat, Central Pahute Mesa, Western Pahute Mesa, Yucca Flat/Climax Mine, and Rainier Mesa/Shoshone Mountain (Figure 1-1). These CAUs have distinctly different contaminant source, geologic, and hydrogeologic characteristics related to their location (FFACO, 1996). The Frenchman Flat CAU consists of 10 CASs located in the northern part of Area 5 and the southern part of Area 11 (Figure 1-1). This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for Frenchman Flat, CAU 98. The methodology used to estimate hydrologic source terms (HSTs) for the Frenchman Flat CAU is also documented. The HST of an underground nuclear test is the portion of the total inventory of radionuclides that is released over time into the groundwater following the test. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. This evaluation was conducted in support of the development of a CAU contaminant transport model for the Frenchman Flat CAU.
Unclassified Source Term And Radionuclide Data For Corrective Action Unit 97
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Author :
language : en
Publisher:
Release Date : 2009
Unclassified Source Term And Radionuclide Data For Corrective Action Unit 97 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2009 with categories.
This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for CAU 97: Yucca Flat/Climax Mine. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. The hydrologic source term (HST) of an underground nuclear test is the portion of the total RST that is released into the groundwater over time following the test. In this report, the HST represents radionuclide release some time after the explosion and does not include the rapidly evolving mechanical, thermal, and chemical processes during the explosion. The CAU 97: Yucca Flat/Climax Mine has many more detonations and a wider variety of settings to consider compared to other CAUs. For instance, the source term analysis and evaluation performed for CAUs 101 and 102: Central and Western Pahute Mesa and CAU 98: Frenchman Flat did not consider vadose zone attenuation because many detonations were located near or below the water table. However, the large number of Yucca Flat/Climax Mine tests and the location of many tests above the water table warrant a more robust analysis of the unsaturated zone.
Unclassified Sources Term And Radionuclide Data For Corrective Action Unit 97
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Author :
language : en
Publisher:
Release Date : 2009
Unclassified Sources Term And Radionuclide Data For Corrective Action Unit 97 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2009 with categories.
This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for CAU 97: Yucca Flat/Climax Mine. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. The hydrologic source term (HST) of an underground nuclear test is the portion of the total RST that is released into the groundwater over time following the test. In this report, the HST represents radionuclide release some time after the explosion and does not include the rapidly evolving mechanical, thermal, and chemical processes during the explosion. The CAU 97: Yucca Flat/Climax Mine has many more detonations and a wider variety of settings to consider compared to other CAUs. For instance, the source term analysis and evaluation performed for CAUs 101 and 102: Central and Western Pahute Mesa and CAU 98: Frenchman Flat did not consider vadose zone attenuation because many detonations were located near or below the water table. However, the large number of Yucca Flat/Climax Mine tests and the location of many tests above the water table warrant a more robust analysis of the unsaturated zone. The purpose of this report is to develop and document conceptual models of the Yucca Flat/Climax Mine HST for use in implementing source terms for the Yucca Flat/Climax Mine models. This document presents future plans to incorporate the radionuclide attenuation mechanisms due to unsaturated/multiphase flow and transport within the Yucca Flat CAU scale modeling. The important processes that influence radionuclide migration for the unsaturated and saturated tests in alluvial, volcanic, and carbonate settings are identified. Many different flow and transport models developed by Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL), including original modeling of multiphase flow and transport by the Stoller-Navarro Joint Venture (SNJV), are integrated to form a general understanding of how the RST relates to the HST. This report is unlike the Frenchman Flat source term analysis because it does not calculate the HST for each test. Instead, this work only identifies the important processes that must be considered when the CAU-transport modeling is performed.
Environmental Standard Review Plan For The Review Of License Renewal Applications For Nuclear Power Plants
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Author : J. O'Brien
language : en
Publisher:
Release Date : 1991
Environmental Standard Review Plan For The Review Of License Renewal Applications For Nuclear Power Plants written by J. O'Brien and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1991 with Aquatic ecosystems categories.
Aging And Life Extension Of Major Light Water Reactor Components
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Author : Vikram N. Shah
language : en
Publisher: Elsevier Science Limited
Release Date : 1993
Aging And Life Extension Of Major Light Water Reactor Components written by Vikram N. Shah and has been published by Elsevier Science Limited this book supported file pdf, txt, epub, kindle and other format this book has been release on 1993 with Technology & Engineering categories.
In a comprehensive and lucid manner this book presents an understanding of the aging degradation of the major pressurized and boiling water reactor structures and components. The design and fabrication of each structure or component is briefly described followed by information on the associated stressors. Interactions between the design, materials, and various stressors that cause aging degradation are reviewed. In many cases, aging degradation problems have occurred, and the plant experience to date is analysed. The discussions summarize the available aging-related information and are supported with extensive references, including references to U.S. Nuclear Regulatory Commission (USNRC) documents, Electric Power Research Institute reports, U.S. and international conference proceedings and other publications. The book will prove a useful reference for engineers engaged in the operation and life extension of the present generation of nuclear power plants and for those engaged in the design of advanced light water reactors. It will also provide engineering students with insight into the practical materials-related issues associated with the design and operation of nuclear power plants. The work will also serve as a basis for programs to address the new aging-related issues likely to arise as plants get older.
Brittle Power
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Author : Amory B. Lovins
language : en
Publisher:
Release Date : 1982
Brittle Power written by Amory B. Lovins and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1982 with Political Science categories.
Practical Nuclear Medicine
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Author : Peter F. Sharp
language : en
Publisher: Springer Science & Business Media
Release Date : 2006-10-27
Practical Nuclear Medicine written by Peter F. Sharp and has been published by Springer Science & Business Media this book supported file pdf, txt, epub, kindle and other format this book has been release on 2006-10-27 with Medical categories.
This book is an essential guide for all practitioners. The emphasis throughout is on the practice of nuclear medicine. Primarily aimed at the radiologist, physician, physicist or technologist starting in nuclear medicine, it will also appeal to more experienced practitioners who are keen to stay up-to-date. The practical approach with tables as "recipes" for acquisition protocols means it is essential for any departmental shelf. 3rd edition expanded - now covering areas of development in nuclear medicine, such as PET and other methods of tumour imaging, data processing. All illustrations are up-to-date to reflect current standards of image quality.
A Three Dimensional Method Of Characteristics Solute Transport Model Moc3d
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Author : Leonard F. Konikow
language : en
Publisher:
Release Date : 1996
A Three Dimensional Method Of Characteristics Solute Transport Model Moc3d written by Leonard F. Konikow and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1996 with Diffusion in hydrology categories.
Nato Handbook
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Author :
language : en
Publisher:
Release Date : 1985
Nato Handbook written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1985 with categories.
Status Of Fast Reactor Research And Technology Development
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Author : International Atomic Energy Agency
language : en
Publisher:
Release Date : 2012
Status Of Fast Reactor Research And Technology Development written by International Atomic Energy Agency and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with Fast reactors categories.
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
