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Fukushima, Masahiro; Goda, J.*; Oizumi, Akito; Bounds, J.*; Cutler, T.*; Grove, T.*; Hayes, D.*; Hutchinson, J.*; McKenzie, G.*; McSpaden, A.*; et al.
Nuclear Science and Engineering, 194(2), p.138 - 153, 2020/02
Times Cited Count：7 Percentile：55.16(Nuclear Science & Technology)To validate lead (Pb) nuclear cross sections, a series of integral experiments to measure lead void reactivity worth was conducted systematically in three fast spectra with different fuel compositions on the Comet critical assembly of the National Criticality Experiments Research Center. Previous experiments in a high-enriched uranium (HEU)/Pb and a low-enriched uranium (LEU)/Pb systems had been performed in 2016 and 2017, respectively. A follow-on experiment in a plutonium (Pu)/Pb system has been completed. The Pu/Pb system was constructed using lead plates and weapons grade plutonium plates that had been used in the Zero Power Physics Reactor (ZPPR) of Argonne National Laboratory until the 1990s. Furthermore, the HEU/Pb system was re-examined on the Comet critical assembly installed newly with a device that can guarantee the gap reproducibility with a higher accuracy and precision, and then the experimental data was re evaluated. Using the lead void reactivity worth measured in these three cores with different fuel compositions, the latest nuclear data libraries, JENDL 4.0 and ENDF/B VIII.0, were tested with the Monte Carlo calculation code MCNP version 6.1. As a result, the calculations by ENDF/B-VIII.0 were confirmed to agree with lead void reactivity worth measured in all the cores. It was furthermore found that the calculations by JENDL 4.0 overestimate by more than 20% for the Pu/Pb core while being in good agreements for the HEU/Pb and LEU/Pb cores.
Fukushima, Masahiro; Goda, J.*; Bounds, J.*; Cutler, T.*; Grove, T.*; Hutchinson, J.*; James, M.*; McKenzie, G.*; Sanchez, R.*; Oizumi, Akito; et al.
Nuclear Science and Engineering, 189, p.93 - 99, 2018/01
Times Cited Count：9 Percentile：62.35(Nuclear Science & Technology)To validate lead (Pb) nuclear cross sections, a series of integral experiments to measure lead void reactivity worths was conducted in a high-enriched uranium (HEU)/Pb system and a low enriched uranium (LEU)/Pb system using the Comet Critical Assembly at NCERC. The critical experiments were designed to provide complementary data sets having different sensitivities to scattering cross sections of lead. The larger amount of the 
U present in the LEU/Pb core increases the neutron importance above 1 MeV compared with the HEU/Pb core. Since removal of lead from the core shifts the neutron spectrum to the higher energy region, positive lead void reactivity worths were observed in the LEU/Pb core while negative values were observed in the HEU/Pb core. Experimental analyses for the lead void reactivity worths were performed with the Monte Carlo calculation code MCNP6.1 together with nuclear data libraries, JENDL 4.0 and ENDF/B VII.1. The calculation values were found to overestimate the experimental ones for the HEU/Pb core while being consistent for the LEU/Pb core.
Fukushima, Masahiro; Tsujimoto, Kazufumi; Okajima, Shigeaki
EPJ Web of Conferences, 111, p.07002_1 - 07002_5, 2016/03
Times Cited Count：2 Percentile：79.85(Nuclear Science & Technology)In the IX-th series at FCA, central fission rate ratios for TRU such as 
Np, Pu, 
Pu, 
Am, 
Am, 
Cm and 
Pu were measured in the seven uranium-fueled assemblies with systematically changed neutron spectra. The FCA-IX assemblies were constructed with simplicity both in geometry and composition. Taking their advantage, benchmark models with respect to central fission rate ratios had been recently established for the assessment of the TRU's fission cross sections. By virtue of these FCA-IX assemblies where the simple combinations of uranium fuel and diluent in their core regions were systematically varied, the neutron spectra of these benchmark models cover those of various reactor types, from fast to epithermal reactors. As an application of these benchmark models, JENDL-4.0 was utilized by a Monte Carlo calculation code. Several results show obvious discrepancies between calculation and experimental values. The benchmark models would be well suited for the assessment and improvement of the nuclear data for TRU's fission cross sections.
; Akino, Fujiyoshi;
Journal of Nuclear Science and Technology, 25(9), p.673 - 681, 1988/09
Times Cited Count：8 Percentile：64.66(Nuclear Science & Technology)no abstracts in English
;
Journal of Fusion Energy, 3(5-6), p.421 - 424, 1983/00
no abstracts in English
;
Journal of Nuclear Science and Technology, 12(11), p.663 - 680, 1975/11
Times Cited Count：18no abstracts in English
Nagaya, Yasunobu; Yokoyama, Kenji; Tada, Kenichi; Konno, Chikara
no journal, ,
The latest version of Japanese Evaluated Nuclear Data Library, JENDL-5, is planned to be released in 2021. To this end, we have performed integral tests of preliminary versions of JENDL-5 since 2018. In this presentation, we show the integral test results of JENDL-5 beta 3 update 1 for critical and shielding experiments. The critical test calculations have been done for experiments mainly in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook and conducted at JAEA. The shielding benchmark tests have been done mainly for FNS experiments at JAEA and OKTAVIAN experiments. We have confirmed that JENDL-5 beta 3 update 1 gives better than or the same prediction accuracy as the previous version of JENDL-4.0 in many test cases for the critical and shielding experiments.
