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ENDF/B-VII.0 Data Testing of 233 U/Th ICSBEP Benchmarks

ENDF/B-VII.0 Data Testing of 233 U/Th ICSBEP Benchmarks. A. C. (Skip) Kahler Los Alamos National Laboratory IAEA Consultants Meeting to Review Benchmarking of Nuclear Data for the U/Th Fuel Cycle December, 2010.

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ENDF/B-VII.0 Data Testing of 233 U/Th ICSBEP Benchmarks

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  1. ENDF/B-VII.0 Data Testing of 233U/Th ICSBEP Benchmarks A. C. (Skip) Kahler Los Alamos National Laboratory IAEA Consultants Meeting to Review Benchmarking of Nuclear Data for the U/Th Fuel Cycle December, 2010 This work was carried out under the auspices of the National Nuclear Security Adminis-tration of the U.S. Department of Energy at Los Alamos National Laboratory under Contract No. DE-AC52-06NA25396.

  2. Introduction • What’s in the ICSBEP Handbook? • ENDF/B-VII.0 Data Testing • Strengths, Weaknesses & What Comes Next?

  3. What is in the ICSBEP Handbook?

  4. Data Testing – Fast Assemblies

  5. Data Testing – Be & Poly Reflected Solutions

  6. Data Testing – Bare & H2O Reflected Solutions

  7. Data Testing – 233UO2/ThO2 Lattice

  8. Data Testing – Combined Results

  9. Data Testing – Reaction Rate Ratios

  10. Observations • With ENDF/B-VII.0 Cross Sections • Fast Critical Assembly calculated eigenvalues are accurate. • Intermediate and Thermal Spectrum calculated eigenvalues for solution assemblies exhibit a decreasing trend with increasing average fission energy. • 233UO2/232ThO2 fuelled lattice assembly calculated eigenvalues are accurate, but are consistent with the solution assembly trend line. • 233U(n,f) reaction rate ratios are calculated accurately. • 232Th(n,2n), (n,f) and (n,g) reaction rate ratios are not calculated accurately.

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