Abstract
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 238U effective capture rate. With a view to investigating the differences, sensitivity analyses are performed by minor modification of the 238U 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 238U 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.
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