Review of SCALE Validations Applicable to Spent Nuclear Fuel Shielding Calculations

Radulescu, Georgeta; Alpan, F. Arzu

doi:10.2172/1906576

Cited by 1 publication

(6 citation statements)

References 14 publications

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“…ORNL/SPR-2022/2518 [17] provides a summary of available experimental data for validating computer codes used in source term and shielding calculations for spent fuel storage and transportation systems. ORNL/SPR-2022/2692 [18] provides a review of SCALE validations applicable to SNF shielding calculations.…”

Section: Purpose and Scopementioning

confidence: 99%

“…Light nuclei-such as 6,7 Li, 9 Be, 10,11 B, 12,13 C, 14,15 N, and 17,18 O-have large cross sections for neutron production [48,49]. NUREG/CR-6802 [9] indicates that for situations in which the (α,n) contribution to the total neutron source is significant, it is necessary to accurately quantify or establish bounding values for all impurities, especially light elements that are known to produce significant (α,n) quantities.…”

Section: Light Element Impurities In Uo2 Matrixmentioning

confidence: 99%

“…Thus, the neutron source depends on the actinides present in the waste and the resin elemental composition. A significant neutron source can be produced from 17 O (α,n) and 18 O (α,n) reactions, as well as (α,n) reactions with light-element impurities in the waste matrix material. Actinide neutron and gamma source terms were calculated in ORNL/TM-2020/1586 [14] based on spent resin actinide loading data provided in NUREG/CR-2830 [88] and DOE/EIS-0375 [90].…”

Section: Actinidesmentioning

confidence: 99%

“…A review of recent ORNL publications [100,101] providing nuclide inventory validations is available in ORNL/SPR-2022/2692 [18]. These validation studies used (1) SCALE 6.2.4 and nuclear cross sections based on ENDF/B-VII.1 [102] and (2) SCALE 6.1 and nuclear cross sections based on ENDF/B-VII.0 [103].…”

Section: Depletion Code Validationsmentioning

confidence: 99%

“…This report provides updated recommendations relevant to current shielding designs and analyses, which are primarily based on a series of ORNL research studies sponsored by the NRC. These research studies are documented in sponsor reports [13,14,15,16,17,18] that are publicly available from the DOE Office of Scientific and Technical Information (OSTI.GOV). More justification for updated shielding recommendations is provided in Section 1.1.…”

Section: Introductionmentioning

confidence: 99%

See 4 more Smart Citations

Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses

Radulescu¹

2023

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Section: Purpose and Scopementioning

confidence: 99%