Fast and thermal reactor benchmark test for JENDL-3.2 and ENDF/B-VI

Benchmark calculation was made for fast and thermal reactors by using ENDF/B-VI release 2(ENDF/B-VI.2) and JENDL-3.2. In 235U and Pu fuel fast reactors with 238U, multiplication factors obtained with ENDF/B-VI.2 are larger than those with JENDL-3.2. The difference is mainly caused from the difference in 238U nuclear data, especially in inelastic scattering matrix. Multiplication factors calculated with ENDF/B-VI.2 become smaller than the JENDL-3.2 calculations in 235U and Pu fuel thermal reactors. The effect of 238U is also important in thermal reactors. There is also a discrepancy in ν values of fissile nuclides in thermal energy range. In 233U cores, ENDF/B-VI.2 gives smaller multiplication factors than JENDL-3.2. (author)