Three-Dimensional Benchmark Tests of ENDF/B-VI for Thermal Reactor Core
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Critical experiments of several thermal reactor cores are analyzed with ENDF/B-VI to assess its applicability to light water reactor analyses. The benchmark tests chosen use the continuous energy Monte Carlo code MCNP with exact treatment of a three dimensional geometry, and a cross section library is prepared by using the NJOY91 code. Calculated keff's underestimate experimental values from 0.3 to 0.9%Δk, and differences between calculated and measured keff's linearly increase with <SUP>238</SUP>U effective capture rate. With a view to investigating the differences, sensitivity analyses are performed by minor modification of the <SUP>238</SUP>U capture cross section at resonance as well as thermal energy regions. As a result, calculated keff's agree well with experimental results by changing the <SUP>238</SUP>U resonance parameters to those of Liou and Chrien below 120eV and decreasing the thermal capture cross section value by 2.3%. These modifications improve the keff's of the TRX-1 and TCA 3.00U cores by 0.8 and 0.3%Δk, respectively.
- Journal of Nuclear Science and Technology
Journal of Nuclear Science and Technology 32(5), 456-463, 1995-05-25
Atomic Energy Society of Japan