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JAEA Reports

Integral benchmark test of JENDL-4.0 for U-233 systems with ICSBEP Handbook

Kuwagaki, Kazuki*; Nagaya, Yasunobu

JAEA-Data/Code 2017-007, 27 Pages, 2017/03

JAEA-Data-Code-2017-007.pdf:4.77MB
JAEA-Data-Code-2017-007-appendix(CD-ROM).zip:0.37MB

The integral benchmark test of JENDL-4.0 for U-233 systems using the continuous-energy Monte Carlo code MVP was conducted. The previous benchmark test was performed only for U-233 thermal solution and fast metallic systems in the ICSBEP handbook. In this study, MVP input files were prepared for uninvestigated benchmark problems in the handbook including compound thermal systems (mainly lattice systems) and integral benchmark test was performed. The prediction accuracy of JENDL-4.0 was evaluated for effective multiplication factors ($$k_mathrm{eff}$$'s) of the U-233 systems. As a result, a trend of underestimation was observed for all the categories of U-233 systems. In the benchmark test of ENDF/B-VII.1 for U-233 systems with the ICSBEP handbook, it is reported that a decreasing trend of calculated $$k_mathrm{eff}$$ values in association with a parameter ATFF (Above-Thermal Fission Fraction) is observed. The ATFF values were also calculated in this benchmark test of JENDL-4.0 and the same trend as ENDF/B-VII.1 was observed.

Journal Articles

R-matrix analysis of neutron effective total cross section, fission cross section and capture cross section of $$^{233}$$U in the energy range from thermal to 150 eV

H.Derrien*

Journal of Nuclear Science and Technology, 31(5), p.379 - 397, 1994/00

 Times Cited Count:9 Percentile:63.31(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of neutron nuclear data for $$^{2}$$$$^{3}$$$$^{3}$$U

*; *; Kikuchi, Yasuyuki

Journal of Nuclear Science and Technology, 19(12), p.1037 - 1052, 1982/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Preparation of uranium-233

; ; *; ; Saeki, Masakatsu; ; Asano, Masaharu; ; B.Leugger*

Journal of Nuclear Science and Technology, 9(12), p.716 - 720, 1972/12

no abstracts in English

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