Abstract
Benchmark calculation has been made for fast and thermal reactors by using ENDF/B-VI release 2(ENDF/B-VI.2) and JENDL-3.2 nuclear data. Effective multiplication factors (k{sub eff}s) calculated for fast reactors calculated with ENDF/B-VI.2 becomes about 1% larger than the results with JENDL-3.2. The difference in k{sub eff} is caused mainly from the difference in inelastic scattering cross section of U-238. In all thermal benchmark cores, ENDF/B-VI.2 gives smaller multiplication factors than JENDL-3.2. In U-235 cores, the difference is about 0.3%dk and it becomes about 0.6% in TCA U cores. The difference in U-238 data is also important in thermal reactors, while there are found 0.1-0.3% different v values of U isotopes in thermal energy between ENDF/B-VI.2 and JENDL-3.2. (author)
Akie, Hiroshi;
Takano, Hideki;
[1]
Kaneko, Kunio
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Akie, Hiroshi, Takano, Hideki, and Kaneko, Kunio.
Effect of U-238 and U-235 cross sections on nuclear characteristics of fast and thermal reactors.
Japan: N. p.,
1997.
Web.
Akie, Hiroshi, Takano, Hideki, & Kaneko, Kunio.
Effect of U-238 and U-235 cross sections on nuclear characteristics of fast and thermal reactors.
Japan.
Akie, Hiroshi, Takano, Hideki, and Kaneko, Kunio.
1997.
"Effect of U-238 and U-235 cross sections on nuclear characteristics of fast and thermal reactors."
Japan.
@misc{etde_544660,
title = {Effect of U-238 and U-235 cross sections on nuclear characteristics of fast and thermal reactors}
author = {Akie, Hiroshi, Takano, Hideki, and Kaneko, Kunio}
abstractNote = {Benchmark calculation has been made for fast and thermal reactors by using ENDF/B-VI release 2(ENDF/B-VI.2) and JENDL-3.2 nuclear data. Effective multiplication factors (k{sub eff}s) calculated for fast reactors calculated with ENDF/B-VI.2 becomes about 1% larger than the results with JENDL-3.2. The difference in k{sub eff} is caused mainly from the difference in inelastic scattering cross section of U-238. In all thermal benchmark cores, ENDF/B-VI.2 gives smaller multiplication factors than JENDL-3.2. In U-235 cores, the difference is about 0.3%dk and it becomes about 0.6% in TCA U cores. The difference in U-238 data is also important in thermal reactors, while there are found 0.1-0.3% different v values of U isotopes in thermal energy between ENDF/B-VI.2 and JENDL-3.2. (author)}
place = {Japan}
year = {1997}
month = {Mar}
}
title = {Effect of U-238 and U-235 cross sections on nuclear characteristics of fast and thermal reactors}
author = {Akie, Hiroshi, Takano, Hideki, and Kaneko, Kunio}
abstractNote = {Benchmark calculation has been made for fast and thermal reactors by using ENDF/B-VI release 2(ENDF/B-VI.2) and JENDL-3.2 nuclear data. Effective multiplication factors (k{sub eff}s) calculated for fast reactors calculated with ENDF/B-VI.2 becomes about 1% larger than the results with JENDL-3.2. The difference in k{sub eff} is caused mainly from the difference in inelastic scattering cross section of U-238. In all thermal benchmark cores, ENDF/B-VI.2 gives smaller multiplication factors than JENDL-3.2. In U-235 cores, the difference is about 0.3%dk and it becomes about 0.6% in TCA U cores. The difference in U-238 data is also important in thermal reactors, while there are found 0.1-0.3% different v values of U isotopes in thermal energy between ENDF/B-VI.2 and JENDL-3.2. (author)}
place = {Japan}
year = {1997}
month = {Mar}
}