Decay Heat Code Validation Activities at ORNL: Supporting Expansion of NRC Regulatory Guide 3.54

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Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and validation of the ORIGEN series of isotope summation codes and nuclear data libraries, widely recognized and used to predict the decay heat for spent nuclear fuel. In particular, the ORIGEN-S code, the depletion/decay module of the SCALE code system, has been extensively validated using experimental isotopic assay data and decay heat measurements for commercial spent fuel. This work was used in the development of the technical basis for NRC Regulatory Guide 3.54 on spent fuel decay heat. The bulk of the experimental data used to ... continued below

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Gauld, I.C. July 20, 2001.

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Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and validation of the ORIGEN series of isotope summation codes and nuclear data libraries, widely recognized and used to predict the decay heat for spent nuclear fuel. In particular, the ORIGEN-S code, the depletion/decay module of the SCALE code system, has been extensively validated using experimental isotopic assay data and decay heat measurements for commercial spent fuel. This work was used in the development of the technical basis for NRC Regulatory Guide 3.54 on spent fuel decay heat. The bulk of the experimental data used to validate spent fuel decay heat predictions are from programs of the 1970s and 1980s and consequently involve older-design fuel assemblies with a relatively low enrichment and burnup. This has led to a situation where the spent fuel now being discharged from operating reactors extends well beyond the regime of the experimental data and area of code applicability based o n the data. The absence of validation data for modern fuel designs has potentially serious consequences for decay heat predictions in terms of added safety factors to account for larger uncertainties and lower volumetric transport and storage capacities.

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  • American Nuclear Society 2001 Winter Meeting, ''Nuclear Research and Development'', Reno, NV (US), 11/11/2001--11/15/2001

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  • Report No.: P01-111200
  • Grant Number: AC05-00OR22725
  • Office of Scientific & Technical Information Report Number: 788725
  • Archival Resource Key: ark:/67531/metadc720377

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  • July 20, 2001

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  • Sept. 29, 2015, 5:31 a.m.

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  • Jan. 19, 2016, 12:36 p.m.

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Gauld, I.C. Decay Heat Code Validation Activities at ORNL: Supporting Expansion of NRC Regulatory Guide 3.54, article, July 20, 2001; Tennessee. (digital.library.unt.edu/ark:/67531/metadc720377/: accessed August 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.