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Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

Author(s)
SR Suffield ,
JM Cuta ,
JA Fort ,
BA Collins ,
HE Adkins ,
ER Siciliano
Publication Date
As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). The inspection procedure included surface temperature measurements on one end of the DSC within the storage module.
isfsi thermal modeling used nuclear fuel thermal performance sensitivity study nuhoms computational fluid dynamics cobra-sfs

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

Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel

Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel

Author(s)
Electric Power Research Institute
Publication Date

As nuclear power plants began to run out of storage capacity in spent nuclear fuel (SNF) storage pools, many nuclear operating companies added higher density pool storage racks to increase pool capacity. Most nuclear power plant storage pools have been re-racked one or more times. As many spent fuel storage pools were re-racked to the maximum extent possible, nuclear operating companies began to employ interim dry storage technologies to store SNF in certified casks and canister-based systems outside of the storage pool in independent spent fuel storage installations (ISFSIs).

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Technical Bases for Extended Dry Storage of Spent Nuclear Fuel

Technical Bases for Extended Dry Storage of Spent Nuclear Fuel

Author(s)
Electric Power Research Institute
Publication Date

Independent spent fuel storage installations (ISFSIs) are currently licensed for 20 years. However, delays in developing permanent spent fuel disposal capability require continued ISFSI storage beyond the 20-year term. This report provides a technical basis for demonstrating the feasibility of extended spent fuel storage in ISFSIs.

isfsi spent fuel casks fuel assemblies licensing storage material degradation waste package degradation used fuel spent fuel storage aging

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

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL

Author(s)
HE Adkins ,
JA Fort ,
SR Suffield ,
JM Cuta
Publication Date

The work reported here is an investigation of the sensitivity of component temperatures in a specific storage system, including fuel cladding temperatures, in response to modeling assumptions that differ from design-basis, including age-related changes that could degrade the thermal behavior of the system. Preliminary evaluations of representative horizontal and vertical storage systems at design basis conditions provides general insight into the expected behavior of storage systems over extended periods of time.

isfsi cfd material degradation used nuclear fuel material modeling thermal performance sensitivity study nuhoms computational fluid dynamics ufd pnnl hsm15

DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION

DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION

Author(s)
TLG Services, Inc. ,
Exelon Generation Company, LLC ,
William Cloutier ,
John Carlson ,
Francis Seymore
Publication Date

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isfsi wet storage decommissioning cost estimate exelon clinton ml13063a531 e16-1640-006

Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT

Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT

Author(s)
Duke Energy ,
Terry Hobbs ,
William Cloutier ,
John Carlson ,
Francis Seymore ,
TLG Services, Inc.
Publication Date

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isfsi wet storage crystal river decommissioning cost estimates dpr-72 50-302 ml13340a008 ml13343a178

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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