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Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft

Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft

Author(s)
Duke Engineering & Services, Inc.
Publication Date
The Design Criteria Policy Document will provide guidance on the types of Design Events, Design Basis Accidents, and Design Criteria for Important To Radiological Safety Systems, Structures, and Components (SSCs) to be assumed during the design of the MRS facility. Definitions of key terms associated with Design Events are also included with this document. Appropriate combinations of Design Events and criteria is identified.
structure analysis spent fuel mol.19970729.0629 mrs radioactive waste radiation protection storage used fuel

Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package

Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package

Author(s)
John A. McClure
Publication Date
The purpose of this calculation is to evaluate the transient behavior and consequences of a worstcase criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package (WP). This calculation will provide information necessary for demonstrating that the consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant in their effect on the overall radioisotopic inventory and on the integrity of the repository.
yucca mountain criticality analysis mox fuel pwr snf

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

Author(s)
Paul L. Cloke
Publication Date
The Monitored Geologic Repository (MGR) Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating (CRWMS M&O) contractor performed calculations to provide input to the design of a waste package (WP). This document analyzes the degradation processes of two types of pressurized water reactor (PWR) spent nuclear fuel (SNF): • Fuel fabricated from low enriched uranium oxide, which has been used, or will ~ used, in commercial nuclear power plants.
criticality low-enriched uranium monitored geologic repository storage mox fuel waste package degradation pwr snf corrosion plutonium oxide geochemical analysis bba000000-01717-0210-00009 uranium oxide

Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister

Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister

Author(s)
CRWMS
Publication Date

The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR.

structure analysis doe spent nuclear fuel waste package design shippingport bba000000-01717-0210-00056 lwbr snf light water breeder reactor

Isotopic Generation and Verification of the PWR Application Model

Isotopic Generation and Verification of the PWR Application Model

Author(s)
OCRWM
Publication Date

The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from pressurized water reactors (PWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (YMP 2000).

criticality yucca mountain commercial spent nuclear fuel isotopic measurements monitored geologic repository isotopic concentrations pwr snf cal-dsu-nu-000004

Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package

Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package

Author(s)
OCRWM
Publication Date

The purpose of this calculation is to evaluate the transient behavior and consequences of a worst- case criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package (WP). This calculation will provide information necessary for demonstrating that the consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant in their effect on the overall radioisotopic inventory and on the integrity of the repository.

criticality storage 21 pwr waste package mox fuel waste package degradation pwr snf criticality consequence reactivity flooding leakage cal-ebs-nu-000008

Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase I Intact Codisposal Canister

Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase I Intact Codisposal Canister

Author(s)
CRWMS
Publication Date

This evaluation is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide analyses of disposal of aluminum (AI)-based Department of Energy-owned research reactor spent nuclear fuel (DOE-SNF) in a codisposal waste package with five canisters of high-level waste (HLW). The analysis was performed in sufficient detail to establish the technical viability of the Al-based DOE-SNF codisposal canister option.

thermal analysis structure analysis criticality high level waste co-disposal waste package doe spent nuclear fuel mit orr savannah river site aluminum clad fuel mined geologic disposal system bba000000-01717-5705-00011

PWR Axial Burnup Profile Analysis

PWR Axial Burnup Profile Analysis

Author(s)
OCRWM
Publication Date

The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the “end-effect”. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package.

criticality commercial spent nuclear fuel end effect storage axial burnup profile isotopic concentrations 21 pwr waste package pwr snf cal-dsu-nu-000012

Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase ll Degraded Codisposal Canister Internal Criticality

Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase ll Degraded Codisposal Canister Internal Criticality

Author(s)
CRWMS
Publication Date

This report presents the analysis and conclusions with respect to disposal criticality for canisters containing aluminum-based fuels from research reactors. The analysis has been divided into three phases. Phase I, dealt with breached and flooded waste packages containing relatively intact canisters and intact internal (basket) structures; Phase II, the subject of this report, covers the degradation of the spent nuclear fuel (SNF) and structures internal to the codisposal waste package including high level waste (HLW), canisters, and criticality control material.

structure analysis criticality high level waste yucca mountain criticality control storage co-disposal waste package doe spent nuclear fuel mit orr aluminum clad fuel waste package degradation spent fuel degradation bba000000-01717-5705-00017

TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package

TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package

Author(s)
Bechtel SAIC Company, LLC
Publication Date

The objective of this calculation is to determine the structural response of the 5-DHLW/DOE (Defense High Level Waste/Department of Energy) SNF (Spent Nuclear Fuel) Short Co-disposal Waste Package (WP) when subjected (while in the horizontal orientation emplaced in the drift) to a collision by a loaded (with WP) Transport and Emplacement Vehicle (TEV) due to an over-run. The scope of this calculation is limited to reporting the calculation results in terms of maximum total stress intensities (Sis) in the outer corrosion barrier (dCB).

thermal analysis structure analysis transportation license application tev collision 5 dhlw wp accident testing

Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package

Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package

Author(s)
John A. McClure ,
James R. Worsham, III
Publication Date

The purpose of this analysis is to evaluate the transient behavior and consequences of a worst case criticality event involving intact pressurized water reactor (PWR) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR assembly waste package (WP). The objective of this analysis is to demonstrate that the consequences of a worst case criticality event involving intact PWR SNF are insignificant in their effect on the overall radioisotopic inventory in a WP. An internal WP criticality is modeled in a manner analogous to transient phenomena in a nuclear reactor core.

criticality analysis 21 pwr waste package pwr snf degraded waste package

UFD Storage and Transportation - Transportation Working Group Report

UFD Storage and Transportation - Transportation Working Group Report

Author(s)
DOE, Used Fuel Disposition Campaign
Publication Date

The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during extended storage. The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of used nuclear fuel (UNF) storage system SSCs and degradation mechanisms developed by the UFD Storage Task (Hanson et al. 2011).

structure analysis transportation spent fuel systems components degradation mechanisms storage used fuel

PWR Axial Burnup Profile Analysis

PWR Axial Burnup Profile Analysis

Author(s)
John M. Scaglione
Publication Date

The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to

burnup credit commercial spent nuclear fuel axial burnup profile 21 pwr waste package pwr snf

NUREG-1768 United States Nuclear Regulatory Commisssion Package Performance Study Test Protocals

NUREG-1768 United States Nuclear Regulatory Commisssion Package Performance Study Test Protocals

Publication Date

This test protocols report presents the NRC staff’s preliminary plans for an experimental phase of the Package Performance Study (PPS), which is examining the response of transportation casks to extreme transportation accident conditions. The staff proposes to conduct tests of full-scale rail and full-scale truck casks including a high-speed impact with an unyielding surface followed by an extreme fire test. The NRC has a contract in place with Sandia National Laboratories (SNL) to conduct the impact and fire tests and to carry out a series of analyses to support the test program.

thermal analyses structure analysis transportation

3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF

3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF

Author(s)
Peter Gottlieb
Publication Date

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to describe the latest version of the probabilistic criticality analysis methodology and its application to the entire commercial waste stream of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) expected to be emplaced in the repository. The purpose of this particular application is to evaluate the 21 assembly PWR absorber plate waste package (WP) with respect to degradedmode criticality performance.

21 pwr waste package waste package degradation pwr snf boron dissolution

Gap Analysis to Support Extended Storage of Used Nuclear Fuel

Gap Analysis to Support Extended Storage of Used Nuclear Fuel

Author(s)
DOE-NE UFD ,
Brady Hanson ,
Halim Alsaed ,
Christine Stockman ,
David Enos ,
Ryan Meyer ,
Ken Sorenson
Publication Date

<div class="page" title="Page 5">
<div class="layoutArea">
<div class="column">
<p><span style="font-size: 12.000000pt; font-family: 'TimesNewRomanPSMT'">This report fulfills the M1 milestone M11UF041401, &ldquo;Storage R&amp;D Opportunities Report&rdquo; under Work Package Number FTPN11UF0414. </span></p>

disposition clad delayed hydride cracking pellet clad interation thermal analysis structure analysis spent fuel used fuel

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report

Author
Austria
Publication Date

This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report

Author
Argentina
Publication Date

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3

Author
Czech Republic
Publication Date

. On 25 March 1999 the Government of the Czech Republic approved the Joint Convention which came into effect in the Czech Republic on 18 June 2001. In agreement with the obligations resulting from its accession to the Joint Convention the Czech Republic has already drawn the second National Report for the purposes of Review Meetings of the Contracting Parties, which describes the system of spent fuel and radioactive waste management in the scope required by selected articles of the Joint Convention.

siting national report joint convention spent fuel management czech republic radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report

Author
U.S. Department of Energy ,
U.S. Nuclear Regulatory Commission ,
U.S. Environmental Protection Agency ,
U.S. Department of State
Publication Date

The United States of America ratified the “Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management” (Joint Convention) on April 9, 2003. The Joint Convention establishes an international peer review process among Contracting Parties and provides incentives for nations to take appropriate steps to bring their nuclear activities into compliance with general safety standards and practices. This first Review Meeting of the Contracting Parties under the Joint Convention is scheduled to take place in November 2003 in Vienna, Austria.

siting national report joint convention spent fuel management united states radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention

Author
SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY (STUK)
Publication Date

Finland signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The major generators of radioactive waste in Finland are the two nuclear power plants, the Loviisa and Olkiluoto plants. The Loviisa plant has two PWR units, operated by Fortum Power and Heat Oy, and the Olkiluoto plant two BWR units, operated by Teollisuuden Voima Oy.

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

Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report

SED Publication Type

Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report

Author
Federal Agency for Nuclear Control on behalf of Belgium. Contributions were also made by ONDRAF/NIRAS, Electrabel, Association Vinçotte Nuclear and the SCK•CEN
Publication Date

On 8 December 1997 Belgium has signed the Joint Convention. The Belgian legislator has expressed its consent with the obligations resulting from the Convention via the Law of 2 August 2002. The ratification was obtained on 5 September 2002. The Convention became effective on 4 December 2002, or 90 days after the Ratification Act had been deposited. Belgium belongs to the group of Contracting Parties having at least one operational nuclear generating unit on their territory.

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Denmark National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Denmark National Report

Author
Denmark National Board of Health, National Institute of Radiation Hygiene
Publication Date

Denmark signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management 29 September 1997, the day it opened for signature. The Convention was accepted 3 September 1999 by letter from the Foreign Ministry to the International Atomic Energy Agency (IAEA). Until further notice the Convention does not apply for the autonomous territories Greenland and the Faroe Islands, which both do not possess spent nuclear fuel or radioactive waste. The present report is the Danish National Report for the Second Review Meeting to the Convention.

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting

Author
Government of Japan
Publication Date

Nuclear facilities in Japan are as listed in the following table, the details of which are described in Section D.

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