Validation of the ORIGEN-S code for predicting radionuclide inventories in used CANDU fuel

The safety assessment being conducted by AECL Research for the concept of deep geological disposal of used CANDU UO 2 fuel requires the calculation of radionuclide inventories in the fuel to provide source terms for radionuclide release. This report discusses the validation of selected actinide and...

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Bibliographic Details
Published inJournal of nuclear materials Vol. 223; no. 2; pp. 109 - 121
Main Authors Tait, J.C., Gauld, I., Kerr, A.H.
Format Journal Article
LanguageEnglish
Published Amsterdam Elsevier B.V 01.05.1995
Elsevier
Subjects
Applied sciences
Energy
Exact sciences and technology
Fuels
Nuclear fuels
Preparation and processing of nuclear fuels
Radioactive waste
Breeder
Fission product
Fast reactor
Nuclear fuel
Radioisotope
Forecast model
Reprocessing
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Summary:The safety assessment being conducted by AECL Research for the concept of deep geological disposal of used CANDU UO 2 fuel requires the calculation of radionuclide inventories in the fuel to provide source terms for radionuclide release. This report discusses the validation of selected actinide and fission-product inventories calculated using the ORIGEN-S code coupled with the WIMS-AECL lattice code, using data from analytical measurements of radioisotope inventories in Pickering CANDU reactor fuel. The recent processing of new ENDF/B-VI cross-section data has allowed the ORIGEN-S calculations to be performed using the most up-to-date nuclear data available. The results indicate that the code is reliably predicting actinide and the majority of fission-product inventories to within the analytical uncertainty.
Bibliography:ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
content type line 23
ISSN:0022-3115
1873-4820
DOI:10.1016/0022-3115(94)00683-0