Author: K. M. Wasywich
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
Characteristics of Used CANDU Fuel Relevant to the Canadian Nuclear Fuel Waste Management Program
Author: K. M. Wasywich
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
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.
Guide to the Canadian Nuclear Fuel Waste Management Program
Author: E. L. J. Rosinger
Publisher: Pinawa, Man. : Whiteshell Nuclear Research Establishment
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 60
Book Description
Publisher: Pinawa, Man. : Whiteshell Nuclear Research Establishment
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 60
Book Description
Canadian Nuclear Fuel Waste Management Program
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 107
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 107
Book Description
Canada Enters the Nuclear Age
Author: Atomic Energy of Canada Limited
Publisher: McGill-Queen's Press - MQUP
ISBN: 9780773516014
Category : Business & Economics
Languages : en
Pages : 466
Book Description
The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR
Publisher: McGill-Queen's Press - MQUP
ISBN: 9780773516014
Category : Business & Economics
Languages : en
Pages : 466
Book Description
The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR
Fuel Isolation Research for the Canadian Nuclear Fuel Waste Management Program
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An origen-s data library for use in environmental safety assessments for the Canadian nuclear fuel waste management program
Microfiltration of Radioactive Contaminants
Author: Buckley, L. P
Publisher: Chalk River, Ont. : Waste Management Systems, Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages : 12
Book Description
Publisher: Chalk River, Ont. : Waste Management Systems, Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages : 12
Book Description
Radioactive Waste Management
Author:
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 726
Book Description
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 726
Book Description
CANDU Fuel-cycle Vision [electronic Resource]
Author: Boczar, P. G
Publisher: Chalk River, Ont. : Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher: Chalk River, Ont. : Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages :
Book Description