Review of SCALE Validations Applicable to Spent Nuclear Fuel Shielding Calculations

Georgeta Radulescu, F. Arzu Alpan

Research output: Book/ReportCommissioned report

Abstract

This report presents a review of publicly available documents providing validations of SCALE code system capabilities for depletion and shielding calculations. The validation studies primarily used information available in the Spent Fuel Isotopic Composition Database, the Shielding Integral Benchmark Archive and Database, and the International Criticality Safety Benchmark Evaluation Project Handbook. Validation results based on radiochemical assay data and shielding benchmark experiments relevant to spent nuclear fuel shielding applications are summarized in this report. The information summarized in this report supports pressurized water reactor and boiling water reactor spent fuel storage and transportation safety analyses.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2022

Keywords

  • 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

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