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General Reports, Various Sources, NUREGs, etc

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

Author(s)

Duke Engineering & Services, Inc.

Publication Date

December 1, 1991

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.

Data

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

Author(s)

CRWMS

Publication Date

October 1, 1999

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

Data

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

Author(s)

CRWMS

Publication Date

June 1, 1997

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

Presentation

Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods

Author(s)

Jy-An John Wang, Hong Wang, Bruce Bevard, Rob Howard

Publication Date

March 1, 2014

Slides - WM2014 Symposia, March 2-6, 2014, Phoenix, AZ

structure analysis slides bending fatigue zry-4 surrogate rods wm2014 symposia march 2-6 2014

Data

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

Author(s)

CRWMS

Publication Date

December 1, 1997

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.

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Data

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

Author(s)

Bechtel SAIC Company, LLC

Publication Date

August 1, 2007

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).

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General Reports, Various Sources, NUREGs, etc

UFD Storage and Transportation - Transportation Working Group Report

Author(s)

DOE, Used Fuel Disposition Campaign

Publication Date

August 1, 2011

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

General Reports, Various Sources, NUREGs, etc

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

Publication Date

February 1, 2003

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

General Reports, Various Sources, NUREGs, etc

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

January 1, 2012

<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, “Storage R&D Opportunities Report” under Work Package Number FTPN11UF0414. </span></p>

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SED Publication Type

Document

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

Author

Commonwealth of Australia

Publication Date

October 1, 2011

This is the fourth National Report by Australia.1 The 2008 National Report and Australia’s presentation to the Third Review Meeting in 2009 highlighted the following major issues:
• progress on national uniformity;
• progress with development of a national waste classification scheme;
• radioactive waste management policy – achievements, consultation, strategy;
• spent fuel management and management of reprocessing waste;
• decommissioning;
• uranium mining waste management; and
• recruitment and skills management.

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

SED Publication Type

Document

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report from the Commonwealth of Australia, October 2008

Author

Australian Government

Publication Date

October 1, 2008

This is the third National Report by Australia1. The 2005 National Report and Australia’s presentation to the Second Review Meeting in 2006 highlighted issues as to how each of the nine Australian jurisdictions within Australia’s federal system are complying with the Joint Convention. A challenge identified for Australia in the Rapporteur’s Report for Country Group 3 was “ensuring a coherent approach to regulations and waste management practice in view of the complex nature of national and regional legislation”.

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

SED Publication Type

Document

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Australian National Report, October 2005

Author

Australian Radiation Protection and Nuclear Safety Agency

Publication Date

October 1, 2005

The responsibility for the governance of Australia is shared by the Australian government and the governments of the six states and two self governing territories. Responsibility for radiation health and safety in each State and Territory rests with the respective State/Territory government, unless the activity is carried out by an Australian government agency or a contractor to a Australian government agency; in those cases the activity is regulated by the Australian government.

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

SED Publication Type

Document

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Australian National Report, July 2003

Author

Australian Radiation Protection and Nuclear Safety Agency

Publication Date

July 1, 2003

The responsibility for the governance of Australia is shared by Australia's federal government (also known as the Commonwealth government) and the governments of the six states and two self governing territories. Responsibility for radiation health and safety in each State and Territory rests with the respective State/Territory government, unless the activity is carried out by a Commonwealth agency or a contractor to a Commonwealth agency; in those cases the activity is regulated by the Federal government (Commonwealth government of Australia).

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

SED Publication Type