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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

MOX Spent Nuclear Fuel and LaBS Glass for TSPA-LA

MOX Spent Nuclear Fuel and LaBS Glass for TSPA-LA

Author(s)
Sandia National Laboratories
Publication Date

This analysis provides information necessary for total system performance assessment (TSPA) for the license application (LA) to include the excess U.S. Department of Energy (DOE) plutonium in the form of mixed oxide (MOX) spent nuclear fuel and lanthanide borosilicate (LaBS) glass. This information includes the additional radionuclide inventory due to MOX spent nuclear fuel and LaBS glass and the analysis that shows that the TSPA models for commercial spent nuclear fuel (CSNF) and high-level waste (HLW) degradation are appropriate for MOX spent nuclear fuel and LaBS glass, respectively.

high level waste yucca mountain commercial spent nuclear fuel license application radionuclides mox fuel spent fuel degradation

Intact and Degraded Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package

Intact and Degraded Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package

Author(s)
OCRWM
Publication Date

The objective of these calculations is to perform intact and degraded mode criticality evaluations of the Department of Energy's (DOE) Three Mile Island- Unit 2 (TMI-2) spent nuclear fuel (SNF) in canisters. This analysis evaluates codisposal in a 5-Defense High-Level Waste (5-DHLW/DOE SNF) Long Waste Package (Civilian Radioactive Waste Management System Management and Operating Contractor [CRWMS M&O] 2000b, Attachment V), which is to be placed in a potential monitored geologic repository (MGR).

criticality yucca mountain low-enriched uranium three mile island monitored geologic repository co-disposal waste package doe spent nuclear fuel 5 dhlw wp waste package degradation spent fuel degradation neutron multiplication factor cal-dsd-nu-000004

Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)

Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)

Author(s)
NRC
Publication Date

This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.

pwr bwr operation regulations radioactive waste management standard technical specifications

Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs

Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs

Author(s)
CRWMS
Publication Date

The purpose of this analysis is to provide input on the criticality potential of various degraded configurations to an analysis on the probability of a criticality event in a Pressurized Water Reactor (PWR) Advanced Uncanistered Fuel (AUCF) Waste Package (WP).

criticality storage waste package degradation uncanistered fuel spent fuel degradation corrosion pwr waste package bba000000-01717-0200-00056

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

Author(s)
Solis, J.
Publication Date

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

slides nei used fuel management meeting cfd thermal modeling vacuum drying
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