Reference Fuel Assembly for Dry Storage Demonstration of L Basin Spent Fuel

Sindelar, Robert L.; Leeper, P.; Vinson, D.W.; Adams, Thad M.

doi:10.2172/1596919

Cited by 1 publication

(1 citation statement)

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“…Following previous sensitivity studies, the primary driver for thermal history is the initial decay heat of the fuel. From the limit specified in Sindelar et al 2012, it was assumed that the RFA and MURR would only be loaded at a maximum of 25 W. This occurs approximately 3 years after reactor discharge for the RFA, it was assumed to use this same period of time for the discharge for the maximum decay heat of the HFIR assembly. Descriptions of the HFIR fuel (Ilas et al 2015;Freels et al 2011) list 2.6 and 6.8 kg U 235 for the inner and outer assemblies, respectively, these sections are split for storage, so decay heats are calculated for each assembly.…”

Section: Thermal Decay Heat and Ambient Conditionsmentioning

confidence: 99%

Modeling of SRS Aluminum-clad Spent Nuclear Fuel in Standard DOE Sealed Canisters

Abboud

2020

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At the Savannah River Site (SRS), approximately 7 MTHM of aluminum-clad spent nuclear fuel is currently in wet storage at L-Basin. Current baseline planning is to process the spent nuclear fuel at H-Canyon. A potential alternative to H-Canyon processing is to dry the fuel and package in a road ready configuration using a multi-purpose canister, such as the DOE standard canister. To understand the potential for gas generation in the canisters, first the thermal and dose rate profiles need to be resolved. A computational fluid dynamics model is built to resolve the 50-year trend for the thermal profile, and MCNP is used to resolve the decay heat and surface dose rate of the fuel. This report will focus on a few fuel types, which should bound all other fuel stored at SRS. These consist of the reference fuel assembly, the MURR fuel and the HFIR fuel. These bound a hypothetical maximum scenario for MTR box fuel, a maximum for decay heat in an assembly, and a maximum for the aluminum surface area, respectively. The geometry for the packages was created from DOE specifications for storage of each of the fuels. As long as the minimum time from reactor discharge to sealed storage is 3 years, then the highest temperatures which occur within the sealed canisters do not exceed 100 C for all scenarios considered here. If the minimum time from reactor discharge to sealed storage is 10 years, the maximum temperature does not exceed 50 C for all the scenarios considered. In the geometry considered, while the HFIR fuel has a large surface area, the packaging configuration leaves large void areas, such that the aluminum surface to free volume ratio is about 30% less than an ATR or MURR packaging configuration. Due to the highest surface area to volume ratio for a loaded DOE standard canister, and a high maximum temperature for the aluminum surface, the MURR loaded DOE standard canister should provide a bounding case for all aluminum-clad fuel currently stored at SRS.

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Section: Thermal Decay Heat and Ambient Conditionsmentioning

confidence: 99%

Modeling of SRS Aluminum-clad Spent Nuclear Fuel in Standard DOE Sealed Canisters

Abboud

2020

View full text Add to dashboard Cite

show abstract

Reference Fuel Assembly for Dry Storage Demonstration of L Basin Spent Fuel

Cited by 1 publication

References 2 publications

Modeling of SRS Aluminum-clad Spent Nuclear Fuel in Standard DOE Sealed Canisters

Modeling of SRS Aluminum-clad Spent Nuclear Fuel in Standard DOE Sealed Canisters

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