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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

Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package

Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package

Author(s)
Dionisie R. Moscalu
Publication Date
The objective of this calculation is to perform intact and degraded mode criticality evaluations of the US Department of Energy's (DOE) Advanced Test Reactor (ATR) Spent Nuclear Fuel (SNF) placed in the DOE standardized SNF canister. This analysis evaluates the codisposal of the DOE SNF canister containing the ATR SNF in a 5-Defense High-Level Waste (%-DHLW) Short Waste Package (WP) (Bechtel SAIC Company, LLC [BSC] 2004a), which is to be placed in a monitored geologic repository (MGR).
criticality yucca mountain advanced test reactor monitored geologic repository co-disposal waste package doe spent nuclear fuel 5 dhlw wp waste package degradation spent fuel degradation atr spent nuclear fuel neutron multiplication factor cal-dsd-nu-000007

Extended Storage and Transportation - Evaluation of Drying Adequacy

Extended Storage and Transportation - Evaluation of Drying Adequacy

Author(s)
CNWRA ,
Hundal Jung ,
Pavan Shukla ,
Tae Ahn ,
Lynn Tipton ,
Kaushik Das ,
Xihua He ,
Debashis Basu
Publication Date

The U.S. Nuclear Regulatory Commission (NRC) is evaluating the safety and security of spent nuclear fuel (SNF) stored in dry casks for extended time periods before transportation to a location where the SNF is further processed or permanently disposed.

criticality storage vacuum drying spent fuel degradation corrosion ml13169a039 residual water

DSNF and Other Waste Form Degradation Abstraction

DSNF and Other Waste Form Degradation Abstraction

Author(s)
Bechtel SAIC Company, LLC
Publication Date

Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters.

yucca mountain licensing storage doe spent nuclear fuel spent fuel degradation

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

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

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

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<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>

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