Author: P. Baumgartner
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Understanding the behaviour of candu fuel under accident conditions is important for licensing current candu-phw reactors and for improving the safety performance of future candu designs. the btf in-reactor severe fuel damage experiments are being performed to increase our understanding of fuel thermo-mechanical behaviour, and fission-product release and transport under the degraded-cooling conditions typical of loss-of-coolant accident (loca) and loss-of-emergency-core-cooling (loecc) accident scenarios. data from the btf experiments will be used to benchmark candu safety analysis codes. this study of the fission-product retention characteristics of stainless steel and inconel surfaces was partially funded as an "in-kind" contribution to the phebus fp research program within the framework of the cog-phebus fp agreement. the primary objective of the btf-104 test was to determine the amount and timing of fission-product release from a candu fuel element under loca/loecc conditions resulting in a volume-average fuel temperature of 1550 degrees c. the value of this report is that it presents the results of a comparison of the fission-product retention characteristics of stainless steel and inconel at 500 to 700 degrees c in a steam-hydrogen atmosphere. the tellurium retention was similar on the two materials but the iodine and cesium were retained more effectively by the stainless steel. the implications of this work are that stainless steel piping surfaces are more effective than inconel surfaces in reducing the amount of iodine and cesium released to the containment under loca/loecc conditions.
The Canadian nuclear fuel waste disposal concept and related research programs
Author: P. Baumgartner
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Understanding the behaviour of candu fuel under accident conditions is important for licensing current candu-phw reactors and for improving the safety performance of future candu designs. the btf in-reactor severe fuel damage experiments are being performed to increase our understanding of fuel thermo-mechanical behaviour, and fission-product release and transport under the degraded-cooling conditions typical of loss-of-coolant accident (loca) and loss-of-emergency-core-cooling (loecc) accident scenarios. data from the btf experiments will be used to benchmark candu safety analysis codes. this study of the fission-product retention characteristics of stainless steel and inconel surfaces was partially funded as an "in-kind" contribution to the phebus fp research program within the framework of the cog-phebus fp agreement. the primary objective of the btf-104 test was to determine the amount and timing of fission-product release from a candu fuel element under loca/loecc conditions resulting in a volume-average fuel temperature of 1550 degrees c. the value of this report is that it presents the results of a comparison of the fission-product retention characteristics of stainless steel and inconel at 500 to 700 degrees c in a steam-hydrogen atmosphere. the tellurium retention was similar on the two materials but the iodine and cesium were retained more effectively by the stainless steel. the implications of this work are that stainless steel piping surfaces are more effective than inconel surfaces in reducing the amount of iodine and cesium released to the containment under loca/loecc conditions.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Understanding the behaviour of candu fuel under accident conditions is important for licensing current candu-phw reactors and for improving the safety performance of future candu designs. the btf in-reactor severe fuel damage experiments are being performed to increase our understanding of fuel thermo-mechanical behaviour, and fission-product release and transport under the degraded-cooling conditions typical of loss-of-coolant accident (loca) and loss-of-emergency-core-cooling (loecc) accident scenarios. data from the btf experiments will be used to benchmark candu safety analysis codes. this study of the fission-product retention characteristics of stainless steel and inconel surfaces was partially funded as an "in-kind" contribution to the phebus fp research program within the framework of the cog-phebus fp agreement. the primary objective of the btf-104 test was to determine the amount and timing of fission-product release from a candu fuel element under loca/loecc conditions resulting in a volume-average fuel temperature of 1550 degrees c. the value of this report is that it presents the results of a comparison of the fission-product retention characteristics of stainless steel and inconel at 500 to 700 degrees c in a steam-hydrogen atmosphere. the tellurium retention was similar on the two materials but the iodine and cesium were retained more effectively by the stainless steel. the implications of this work are that stainless steel piping surfaces are more effective than inconel surfaces in reducing the amount of iodine and cesium released to the containment under loca/loecc conditions.
Nuclear Fuel Waste Management and Disposal Concept
Author: Canadian Environmental Assessment Agency. Nuclear Fuel Waste Management and Disposal Concept Environmental Assessment Panel
Publisher: [Hull, Quebec] : The Panel
ISBN:
Category : Science
Languages : en
Pages : 188
Book Description
In accordance with the terms of reference announced in October 1989, the Environmental Assessment Panel has completed its review of nuclear fuel waste management and a disposal concept proposed by Atmomic Energy of Canada Limited.
Publisher: [Hull, Quebec] : The Panel
ISBN:
Category : Science
Languages : en
Pages : 188
Book Description
In accordance with the terms of reference announced in October 1989, the Environmental Assessment Panel has completed its review of nuclear fuel waste management and a disposal concept proposed by Atmomic Energy of Canada Limited.
The Disposal of Canada's Nuclear Fuel Waste
A Review of Various Approaches Being Undertaken by Industrialized Nations for the Management and Disposal of High-level Nuclear Waste
Author: Acres International Limited
Publisher:
ISBN:
Category : Nuclear industry
Languages : en
Pages : 178
Book Description
The high-level nuclear waste (HLW) disposal concept proposed by Atomic Energy of Canada Ltd. was submitted for review by the federal environmental assessment and review process (EARP). This report summarizes the status of high-level nuclear waste management programs in other countries. A brief review of the Canadian HLW program is made for comparison with other countries' progress, particularly that of Belgium, France, the Federal Republic of Germany, Sweden, Switzerland, and the United States, which are described in detail. For each country, descriptions are given of key organizations, disposal facility schedules, waste quantities, interim storage and transportation, site investigations, repository design, impact analysis, monitoring, licensing and other regulatory requirements, disposal concept assessment, and public participation processes.
Publisher:
ISBN:
Category : Nuclear industry
Languages : en
Pages : 178
Book Description
The high-level nuclear waste (HLW) disposal concept proposed by Atomic Energy of Canada Ltd. was submitted for review by the federal environmental assessment and review process (EARP). This report summarizes the status of high-level nuclear waste management programs in other countries. A brief review of the Canadian HLW program is made for comparison with other countries' progress, particularly that of Belgium, France, the Federal Republic of Germany, Sweden, Switzerland, and the United States, which are described in detail. For each country, descriptions are given of key organizations, disposal facility schedules, waste quantities, interim storage and transportation, site investigations, repository design, impact analysis, monitoring, licensing and other regulatory requirements, disposal concept assessment, and public participation processes.
Nuclear Fuel Waste Management
Author: Reto Zach
Publisher: Pinawa, Manitoba : Environmental Science Branch, Whiteshell Laboratories
ISBN:
Category : Environmental impact analysis
Languages : en
Pages : 130
Book Description
This report highlights many of the key achievements of the biosphere program in support of the development of the disposal concept for Canadian nuclear fuel waste, particularly those achievements related to the development of the BIOTRAC biosphere model and its supporting research. That model was used for the assessment and review of the disposal concept in an environmental impact statement (EIS). The report also treats highlights related to alternative models, external scientific/technical reviews, EIS feedback, and the international BIOMOVS model validation program. Furthermore, it highlights basic aspects of future modelling and research needs in relation to siting a disposal facility, taking into account feedback from the various reviews and the EIS. Appendices include listings of key staff involved, all the scientific/technical reports produced, contracts let to outside agencies, and issues raised during the EIS review.
Publisher: Pinawa, Manitoba : Environmental Science Branch, Whiteshell Laboratories
ISBN:
Category : Environmental impact analysis
Languages : en
Pages : 130
Book Description
This report highlights many of the key achievements of the biosphere program in support of the development of the disposal concept for Canadian nuclear fuel waste, particularly those achievements related to the development of the BIOTRAC biosphere model and its supporting research. That model was used for the assessment and review of the disposal concept in an environmental impact statement (EIS). The report also treats highlights related to alternative models, external scientific/technical reviews, EIS feedback, and the international BIOMOVS model validation program. Furthermore, it highlights basic aspects of future modelling and research needs in relation to siting a disposal facility, taking into account feedback from the various reviews and the EIS. Appendices include listings of key staff involved, all the scientific/technical reports produced, contracts let to outside agencies, and issues raised during the EIS review.
Advanced Containment Research for the Canadian Nuclear Fuel Waste Management Program
Author: Atomic Energy of Canada Limited
Publisher: Pinawa, Man. : Whiteshell Nuclear Research Establishment
ISBN:
Category : Radioactive waste disposal in the ground
Languages : en
Pages : 28
Book Description
Publisher: Pinawa, Man. : Whiteshell Nuclear Research Establishment
ISBN:
Category : Radioactive waste disposal in the ground
Languages : en
Pages : 28
Book Description
Nuclear Waste Management in Canada
Author: Darrin Durant
Publisher: UBC Press
ISBN: 0774859032
Category : Technology & Engineering
Languages : en
Pages : 211
Book Description
As oil reserves decline and the environment takes centre stage in public policy discussions, the merits and dangers of nuclear power and nuclear waste management are once again being debated. Nuclear Waste Management in Canada provides a critical counterpoint to the position of government and industry by examining not only the technical but also the social and ethical aspects of the issue. What do frequently used terms such as safety, risk, and acceptability really mean? And how and why did the public consultation process in Canada fail to address ethical and social issues? This timely collection defuses the uncertainty, ambiguity, and ignorance that surrounds discussions of nuclear energy.
Publisher: UBC Press
ISBN: 0774859032
Category : Technology & Engineering
Languages : en
Pages : 211
Book Description
As oil reserves decline and the environment takes centre stage in public policy discussions, the merits and dangers of nuclear power and nuclear waste management are once again being debated. Nuclear Waste Management in Canada provides a critical counterpoint to the position of government and industry by examining not only the technical but also the social and ethical aspects of the issue. What do frequently used terms such as safety, risk, and acceptability really mean? And how and why did the public consultation process in Canada fail to address ethical and social issues? This timely collection defuses the uncertainty, ambiguity, and ignorance that surrounds discussions of nuclear energy.
Radioactive Waste Management in Canada
Author: Norma J. Hawley
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 52
Book Description
The Management of Nuclear Fuel Waste
Author: Ontario. Legislative Assembly. Select Committee on Ontario Hydro Affairs
Publisher:
ISBN:
Category : Hazardous wastes
Languages : en
Pages : 128
Book Description
Publisher:
ISBN:
Category : Hazardous wastes
Languages : en
Pages : 128
Book Description
Natural Analogs in Support of the Canadian Concept for Nuclear Fuel Waste Disposal
Author: Jan J. Cramer
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN:
Category : Science
Languages : en
Pages : 118
Book Description
Data used for the assessment modelling of the Canadian concept for disposal of nuclear fuel waste is mainly based on observations from short-term laboratory and field experiments, although it must apply to periods of 10,000 to one million years. Natural analogs can provide useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU fuel. The report gives a definition of natural analogs and an overview of the various types of analogs and analog studies; describes the main components of the disposal system, including the vault, the geosphere, and the biosphere, and gives specific examples for each; and describes several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by other countries as part of their waste disposal management programs.
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN:
Category : Science
Languages : en
Pages : 118
Book Description
Data used for the assessment modelling of the Canadian concept for disposal of nuclear fuel waste is mainly based on observations from short-term laboratory and field experiments, although it must apply to periods of 10,000 to one million years. Natural analogs can provide useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU fuel. The report gives a definition of natural analogs and an overview of the various types of analogs and analog studies; describes the main components of the disposal system, including the vault, the geosphere, and the biosphere, and gives specific examples for each; and describes several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by other countries as part of their waste disposal management programs.