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Waste Package Neutron Absorber, Thermal Shunt, and Fill Gas Selection Report

Waste Package Neutron Absorber, Thermal Shunt, and Fill Gas Selection Report

Author(s)
CRWMS M&O
Publication Date
Materials for neutron absorber, thermal shunt, and fill gas for use in the waste package were selected using a qualitative approach. For each component, selection criteria were identified; candidate materials were selected; and candidates were evaluated against these criteria. The neutron absorber materials evaluated were essentially boron-containing stainless steels. Two candidates were evaluated for the thermal shunt material. The fill gas candidates were common gases such as helium, argon, nitrogen, carbon dioxide, and dry air.
yucca mountain neutron absorbers waste package design b00000000-01717-2200-00227 thermal shunt fill gas

Geochemistry Model Validation Report: Material Degradation and Release Model

Geochemistry Model Validation Report: Material Degradation and Release Model

Author(s)
Sandia National Laboratories
Publication Date

The purpose of the material degradation and release (MDR) model is to predict the fate of the waste package materials, specifically the retention or mobilization of the radionuclides and the neutron-absorbing material as a function of time after the breach of a waste package during the 10,000 years after repository closure. The output of this model is used directly to assess the potential for a criticality event inside the waste package due to the retention of the radionuclides combined with a loss of the neutron-absorbing material.

yucca mountain criticality analysis neutron absorbers postclosure materials analysis radionuclide transport neutron transport

EQ6 calculations for Chemical Degradation of Navy Waste Packages

EQ6 calculations for Chemical Degradation of Navy Waste Packages

Author(s)
OCRWM
Publication Date

The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Navy (Refs. 1 and , 2). The Navy SNF has been considered for disposal at the potential Yucca Mountain site. For some waste packages, the containment may breach (Ref. 3), allowing the influx of water. Water in the waste package may moderate neutrons, increasing the likelihood of a criticality event within the waste package.

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Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Author(s)
DOE
Publication Date

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.

criticality spent fuel fission products cross-section data safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle benchmarks used fuel

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Author(s)
Office of Civilian Radioactive Waste Management
Publication Date

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.

criticality spent fuel fission products cross-section data benchmark safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle used fuel

EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages

EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages

Author(s)
OCRWM
Publication Date

The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.

criticality yucca mountain heu neutron absorbers monitored geologic repository storage waste package design waste package degradation shippingport corrosion chemical analysis cal-edc-md-000002

EQ6 Calculation for Chemical Degradation of Enrico Fermi Codisposal Waste Packages: Effects of Updated Design and Rates

EQ6 Calculation for Chemical Degradation of Enrico Fermi Codisposal Waste Packages: Effects of Updated Design and Rates

Author(s)
OCRWM
Publication Date

The Monitored Geologic Repository (MGR) Waste Package Project of the BSC Management and Operating Contractor for the Department of Energy's Office of Civilian Radioactive Waste Management performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Enrico Fermi Reactor owned by the DOE (Ref. 9). The Fermi SNF has been considered for disposal at the proposed Yucca Mountain site.

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EQ6 Calculations for Chemical Degradation of TRIGA Codisposal Waste PacKages

EQ6 Calculations for Chemical Degradation of TRIGA Codisposal Waste PacKages

Author(s)
OCRWM
Publication Date

The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Training, Research, Isotopes, General Atomics (TRIGA) reactor (Ref. 1). The TRIGA SNF has been considered for disposal at the potential Yucca Mountain site.

criticality yucca mountain neutron absorbers monitored geologic repository storage high level waste glass triga waste package design corrosion geochemical analysis cal-edc-md-000001

EQ6 Calculation for Chemical Degradation of Shippingport LWBR (Th/U Oxide) Spent Nuclear Fuel Waste Packages

EQ6 Calculation for Chemical Degradation of Shippingport LWBR (Th/U Oxide) Spent Nuclear Fuel Waste Packages

Author(s)
OCRWM
Publication Date

The Monitored Geologic Repository (MGR) Waste Package Department of the Civilian Radioactive Waste Management System Management & Operating contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Light Water Breeder Reactor (LWBR) (Ref. 1). The Shippingport LWBR SNF has been considered for disposal at the potential Yucca Mountain site.

criticality yucca mountain neutron absorbers monitored geologic repository storage high level waste glass waste package degradation shippingport corrosion geochemical analysis lwbr snf flooding cal-edc-md-000008 thorium

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions, April 2009

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions, April 2009

Author
Government of Canada
Publication Date

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions, April 2009

siting national report joint convention spent fuel management canada radioactive waste management

Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Report, October 2008

SED Publication Type

Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Report, October 2008

Author
Government of Canada
Publication Date

This report demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. A collaboration by government, industry and the regulatory body, this document focuses specifically on the progress of long-term management initiatives for spent fuel and radioactive waste in Canada, revisions and updates to Canada’s Second National Report and comments and issues raised at the Second Review Meeting.

siting national report joint convention spent fuel management canada radioactive waste management

Regulatory Guide - Geological Considerations in Siting a Repository for Underground Disposal of High-level Radioactive Waste

SED Publication Type

Regulatory Guide - Geological Considerations in Siting a Repository for Underground Disposal of High-level Radioactive Waste

Author
Canadian Atomic Energy Control Board
Publication Date

At the present time in Canada, high-level radioactive waste is accumulating in the form of irradiated, used fuel from research reactors and nuclear power generating stations. The used fuel bundles are kept in water-filled bays at each of the reactor sites. Because water is both a radiation barrier and an effective coolant, this system provides a safe means of storage. Used fuel is also safely stored above ground in dry concrete canisters in several Canadian locations.

high level waste repository siting regulations canada

Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report

SED Publication Type

Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report

Author
Government of Canada
Publication Date

This report demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. A collaboration by government, industry and the regulatory body, this document focuses specifically on the progress of long-term management initiatives for spent fuel and radioactive waste in Canada, revisions and updates to Canada’s Third National Report and comments and issues raised at the Third Review Meeting.

siting national report joint convention spent fuel management canada radioactive waste management

INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - Northern Village of Pinehouse, Saskatchewan

SED Publication Type

INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - Northern Village of Pinehouse, Saskatchewan

Author
Erin A. Moss ,
George Schneider ,
Rashid Bashir ,
NWMO
Publication Date

On August 17, 2010, the Northern Village of Pinehouse, Saskatchewan and the Kineepik Métis Local expressed interest in learning more about the Nuclear Waste Management Organization (NWMO) site selection process to find an informed and willing community to host a deep geological repository for Canada’s used nuclear fuel (NWMO 2010). This report summarizes the findings of an initial screening, conducted by Golder Associates Ltd., to evaluate the potential suitability of the Pinehouse area against five screening criteria using readily available information.

spent fuel repository fission gas siting northern village of pinehouse saskatchewan canada used fuel

Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report

SED Publication Type

Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report

Author
Government of Canada
Publication Date

Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report

siting national report joint convention spent fuel management canada radioactive waste management

Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management -- Second Report

SED Publication Type

Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management -- Second Report

Author
Canada
Publication Date

This is Canada's Second National Report and it demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The main aspect addressed in this report is the progress on initiatives for the long-term management of spent fuel and radioactive waste in Canada. This report also includes information on Canada's systematic monitoring programs and their implementation and addresses specific topics raised at the First Review Meeting.

high level waste spent fuel repository waste management siting canada used fuel

INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan

SED Publication Type

INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan

Author
Erin A. Moss ,
George Schneider ,
Rashid Bashir ,
NWMO
Publication Date

On September 13, 2010, the English River First Nation expressed interest in learning more about the Nuclear Waste Management Organization (NWMO) site selection process to find an informed and willing community to host a deep geological repository for Canada’s used nuclear fuel (NWMO, 2010). This report summarizes the findings of an initial screening, conducted by Golder Associates Ltd., to evaluate the potential suitability of thirteen English River First Nation reserve areas against five screening criteria using readily available information.

spent fuel repository fission gas siting saskatchewan english river first nation canada used fuel
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