Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII BENCHMARK: STUDY OF SPENT FUEL COMPOSITIONS FOR LONG TERM DISPOSAL

Conference ·
OSTI ID:1081705

This paper summarizes the problem specification and compares participants results for the OECD/NEA/WPNCS Expert Group on Burn-up Credit Criticality Safety Phase VII Benchmark Study of Spent Fuel Compositions for Long-Term Disposal. The Phase VII benchmark was developed to study the ability of relevant computer codes and associated nuclear data to predict spent fuel isotopic compositions and corresponding keff values in a cask configuration over the time duration relevant to spent nuclear fuel (SNF) disposal. The benchmark was divided into two sets of calculations: (1) decay calculations out to 1,000,000 years for provided pressurized-water-reactor (PWR) UO2 discharged fuel compositions and (2) burnup credit criticality calculations for a representative cask model at selected time steps. Contributions from 15 organizations and companies in 10 countries were submitted to the Phase VII benchmark exercise. This paper provides a description of the Phase VII benchmark and detailed comparisons of the participants isotopic compositions and keff values that were calculated with a diversity of computer codes and nuclear data sets. Differences observed in the calculated time-dependent nuclide densities are attributed to different decay data or code-specific numerical approximations. The variability of the keff results is consistent with the evaluated uncertainty associated with cross-section data.

Research Organization:
Oak Ridge National Laboratory (ORNL)
Sponsoring Organization:
NE USDOE - Office of Nuclear Energy
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1081705
Country of Publication:
United States
Language:
English

Similar Records

Activities of the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel
Conference · Fri Oct 30 00:00:00 EDT 2009 · OSTI ID:1025821

Experiment Isotopic Data Compiled by the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel
Conference · Sat Nov 14 23:00:00 EST 2009 · OSTI ID:980701

SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data
Journal Article · Wed Aug 02 00:00:00 EDT 2017 · Annals of Nuclear Energy (Oxford) · OSTI ID:1376611

Related Subjects