Author:
Publisher:
ISBN:
Category : Administrative law
Languages : en
Pages : 876
Book Description
Federal Register
Author:
Publisher:
ISBN:
Category : Administrative law
Languages : en
Pages : 876
Book Description
Publisher:
ISBN:
Category : Administrative law
Languages : en
Pages : 876
Book Description
Advances in High Temperature Gas Cooled Reactor Fuel Technology
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639
Book Description
This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639
Book Description
This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
Electrometallurgical Techniques for DOE Spent Fuel Treatment
Author: National Research Council
Publisher: National Academies Press
ISBN: 0309070953
Category : Science
Languages : en
Pages : 128
Book Description
The Committee on Electrometallurgical Techniques for DOE Spent Fuel Treatment was formed in September 1994 in response to a request made to the National Research Council (NRC) by the U.S. Department of Energy DOE. DOE requested an evaluation of electrometallurgical processing technology proposed by Argonne National Laboratory (ANL) for the treatment of DOE spent nuclear fuel. Electrometallurgical treatment of spent reactor fuel involves a set of operations designed to remove the remaining uranium metal and to incorporate the radioactive nuclides into well defined and reproducible waste streams. Over the course of the committee's operating life, this charge has remained constant. Within the framework of this overall charge, the scope of the committee's workâ€"as defined by its statement of taskâ€"has evolved in response to further requests from DOE, as well as technical accomplishments and regulatory and legal considerations. As part of its task, the committee has provided periodic assessments of ANL's R&D program on the electrometallurgical technology. Electrometallurgical Techniques for DOE Spent Fuel Treatment assesses the viability of electrometallurgical technology for treating DOE spent nuclear fuel and monitors the scientific and technical progress of the ANL program on electrometallurgical technology, specifically within the context of ANL's demonstration project on electrometallurgical treatment of EBR-II SNF. This report evaluates ANL's performance relative to the success criteria for the demonstration project, which have served as the basis for judging the efficacy of using electrometallurgical technology for the treatment of EBR-II spent nuclear fuel. It also addresses post-demonstration activities related to ANL's electrometallurgical demonstration project, and makes related recommendations in this area.
Publisher: National Academies Press
ISBN: 0309070953
Category : Science
Languages : en
Pages : 128
Book Description
The Committee on Electrometallurgical Techniques for DOE Spent Fuel Treatment was formed in September 1994 in response to a request made to the National Research Council (NRC) by the U.S. Department of Energy DOE. DOE requested an evaluation of electrometallurgical processing technology proposed by Argonne National Laboratory (ANL) for the treatment of DOE spent nuclear fuel. Electrometallurgical treatment of spent reactor fuel involves a set of operations designed to remove the remaining uranium metal and to incorporate the radioactive nuclides into well defined and reproducible waste streams. Over the course of the committee's operating life, this charge has remained constant. Within the framework of this overall charge, the scope of the committee's workâ€"as defined by its statement of taskâ€"has evolved in response to further requests from DOE, as well as technical accomplishments and regulatory and legal considerations. As part of its task, the committee has provided periodic assessments of ANL's R&D program on the electrometallurgical technology. Electrometallurgical Techniques for DOE Spent Fuel Treatment assesses the viability of electrometallurgical technology for treating DOE spent nuclear fuel and monitors the scientific and technical progress of the ANL program on electrometallurgical technology, specifically within the context of ANL's demonstration project on electrometallurgical treatment of EBR-II SNF. This report evaluates ANL's performance relative to the success criteria for the demonstration project, which have served as the basis for judging the efficacy of using electrometallurgical technology for the treatment of EBR-II spent nuclear fuel. It also addresses post-demonstration activities related to ANL's electrometallurgical demonstration project, and makes related recommendations in this area.
The EBR-II Fuel Cycle Story
Author: Charles E. Stevenson
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 274
Book Description
In this comprehensive volume, Stevenson recounts the history of the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF), and the process requirements of this unique technology. The author also explains the reasons behind the remarkable success of both the EBR-II and the FCF. These data, presented as a useful information source, should be of considerable significance to the continuing development of nuclear power.
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 274
Book Description
In this comprehensive volume, Stevenson recounts the history of the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF), and the process requirements of this unique technology. The author also explains the reasons behind the remarkable success of both the EBR-II and the FCF. These data, presented as a useful information source, should be of considerable significance to the continuing development of nuclear power.
Proposed Consolidation of Nuclear Operations Related to Production of Radioisotope Power Systems
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 542
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 542
Book Description
107-1 Hearings: Energy and Water Development Appropriations for 2002, Part 4, 2001
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 1580
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 1580
Book Description
U.S. Department of Energy Performance and Accountability Report: Fiscal Year 2000
Author:
Publisher: DIANE Publishing
ISBN: 1428918337
Category :
Languages : en
Pages : 313
Book Description
Publisher: DIANE Publishing
ISBN: 1428918337
Category :
Languages : en
Pages : 313
Book Description
Safety Related Issues of Spent Nuclear Fuel Storage
Author: North Atlantic Treaty Organization. Public Diplomacy Division
Publisher: Springer Science & Business Media
ISBN: 1402059019
Category : Science
Languages : en
Pages : 357
Book Description
This book contains papers from a NATO-sponsored workshop in Almaty in September 2005, which discussed safety-related issues of storing spent nuclear fuel. Fifteen papers cover aluminum-clad fuel discharged from research reactors worldwide, while five papers examine stainless steel-clad fuel from fast reactors, and two Zircaloy-clad fuel from commercial light-water reactors.
Publisher: Springer Science & Business Media
ISBN: 1402059019
Category : Science
Languages : en
Pages : 357
Book Description
This book contains papers from a NATO-sponsored workshop in Almaty in September 2005, which discussed safety-related issues of storing spent nuclear fuel. Fifteen papers cover aluminum-clad fuel discharged from research reactors worldwide, while five papers examine stainless steel-clad fuel from fast reactors, and two Zircaloy-clad fuel from commercial light-water reactors.
Programmatic EIS for Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the United States, Including the Role of the Fast Flux Test Facility
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 790
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 790
Book Description
Comprehensive Nuclear Materials
Author: Todd R Allen
Publisher: Elsevier
ISBN: 0080560334
Category : Technology & Engineering
Languages : en
Pages : 3552
Book Description
Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants
Publisher: Elsevier
ISBN: 0080560334
Category : Technology & Engineering
Languages : en
Pages : 3552
Book Description
Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants