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Pu
Am
)O
(z = 0.05, 0.10, and 0.15)Yokoyama, Keisuke; Watanabe, Masashi; Tokoro, Daishiro*; Sugimoto, Masatoshi*; Morimoto, Kyoichi; Kato, Masato; Hino, Tetsushi*
Nuclear Materials and Energy (Internet), 31, p.101156_1 - 101156_7, 2022/06
Times Cited Count：3 Percentile：68.71(Nuclear Science & Technology)In current nuclear fuel cycle systems, to reduce the amount of high-level radioactive waste, minor actinides (MAs) bearing MOX fuel is one option for burning MAs using fast reactor. However, the effects of Am content in fuel on thermal conductivity are unclear because there are no experimental data on thermal conductivity of high Am bearing MOX fuel. In this study, The thermal conductivities of near stoichiometric (UPuAm)O solid solutions(z = 0.05, 0.10, and 0.15) have been measured between room temperature (RT) and 1473 K. The thermal conductivities decreased with increasing Am content and satisfied the classical phonon transport model ((A+BT)
) up to about 1473 K. A values increased linearly with increasing Am content because the change in ionic radius affects the conduction of the phonon due to the solid solution in U
and Am
. B values were independent of Am content.
with Pu = 0.45 and 0.68 and related defect formation energyHirooka, Shun; Matsumoto, Taku; Sunaoshi, Takeo*; Hino, Tetsushi*
Journal of Nuclear Materials, 558, p.153375_1 - 153375_8, 2022/01
Times Cited Count：2 Percentile：31.78(Materials Science, Multidisciplinary)no abstracts in English
Watanabe, Yukinobu*; Fukahori, Tokio; Kosako, Kazuaki*; Shigyo, Nobuhiro*; Murata, Toru*; Yamano, Naoki*; Hino, Tetsushi*; Maki, Koichi*; Nakashima, Hiroshi; Odano, Naoteru*; et al.
AIP Conference Proceedings 769, p.326 - 331, 2005/05
An overview is presented of recent nuclear data evaluations performed for the JENDL high-energy (JENDL-HE) file, in which neutron and proton cross sections for energies up to 3 GeV are included for the whole 132 nuclides. The current version of the JENDL-HE file consists of neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double-differential cross sections of secondary light particles (
He, 
, and 
) and 
-rays, isotope production cross sections, and fission cross sections in the ENDF6 format. The present evaluations are performed on the basis of experimental data and theoretical model calculations. For the cross section calculations, we have constructed a hybrid calculation code system with some available nuclear model codes and systematics-based codes, such as ECIS96, OPTMAN, GNASH, JQMD, JAM, TOTELA, FISCAL, and so on. The evaluated cross sections are compared with available experimental data and the other evaluations. Future plans of our JENDL-HE project are discussed along with prospective needs of high-energy cross section data.
Zukeran, Atsushi*; Nakagawa, Tsuneo; Shibata, Keiichi; Ishikawa, Makoto*; Hino, Tetsushi*
JAERI-Research 2004-026, 102 Pages, 2005/02
JAERI-Research-2004-026.pdf:7.68MB
Reactivity uncertainties such as effective multiplication factor can be estimated by the sensitivity coefficients of the infinitely diluted cross section and resonance self-shielding factor to the changes of resonance parameters of interest. In the present work, the uncertainties of the resolved resonance parameters for the evaluated nuclear data file JENDL-3.2 were estimated on the basis of Breit-Wigner Multi-level formula. The resonance self-shielding factor based on NR-approximation is analytically described. Reactivity uncertainty evaluation method for the effective multiplication factor k
, temperature coefficient , and Doppler reactivity worth 
is developed by means of the sensitivity coefficient against the resonance parameter. Final uncertainties are estimated by means of error propagation law using the level-wise uncertainties. Preliminary uncertainty of Doppler reactivity worth results about 4% at the temperature 728 K for large sodium-cooled FBR.
Fukahori, Tokio; Kunieda, Satoshi; Chiba, Satoshi; Harada, Hideo; Nakashima, Hiroshi; Mori, Takamasa; Shimakawa, Satoshi; Maekawa, Fujio; Watanabe, Yukinobu*; Shigyo, Nobuhiro*; et al.
no journal, ,
The latest version of JENDL High Energy File (JENDL/HE) and JENDL Photonuclear Data File (JENDL/PD) is being planed to be released as JENDL/HE-2007 and JENDL/PD-2007. In JENDL/HE-2007, nuclear data for about 100 nuclides, which are newly ecaluated and revised from JENDL/HE-2004 will be stored. The JENDL/PD-2007 will have nuclear data for about 170 nuclides.
Murakami, Yohei*; Mitsuyasu, Takeshi*; Miwa, Junichi*; Hino, Tetsushi*; Suyama, Kenya; Nagaya, Yasunobu
no journal, ,
A Monte Carlo code system has been developed to design an innovative water-cooled reactor, Resource-renewable Boiling Water Reactor (RBWR), which enables to burn transuranium elements (TRUs) efficiently. The system can perform multiphysics calculations of whole-core Monte Carlo neutronics, thermal-hydraulics and burnup; thus uncertainty induced by group-constant generation can be excluded. It has been confirmed that the pseudo material construct method can reduce memory requirement significantly and thus the reactor core design with whole core Monte Carlo calculations can be performed even with current computational resource.
Miwa, Junichi*; Hino, Tetsushi*; Mitsuyasu, Takeshi*; Nagaya, Yasunobu
no journal, ,
We performed whole-core Monte Carlo calculations for core design verification of an innovative BWR concept, resource-renewable boiling water reactor (RBWR). The calculations include a coupled neutronics/thermal-hydraulics calculation with a continuous-energy Monte Carlo code MVP and an inhouse thermal-hydraulics code, and a burnup calculation with the MVP-BURN code. Such calculations for the RBWR is challenging because it requires a large memory size and a large amount of calculation time. The typical memory size required for the RBWR calculations was an order of 10 GBytes per CPU in parallel computing using a desktop PC cluster. The total calculation time for calculating the characteristics of the equilibrium core of RBWR with the whole-core Monte Carlo burnup calculation using the desktop PC cluster was about 20 days. We demonstrated that the design calculations for the RBWR were possible with such a desktop PC cluster.
Morimoto, Kyoichi; Watanabe, Masashi; Kato, Masato; Hino, Tetsushi*
no journal, ,
no abstracts in English
Watanabe, Masashi; Yokoyama, Keisuke; Kato, Masato; Hino, Tetsushi*
no journal, ,
no abstracts in English
with high Am contentWatanabe, Masashi; Yokoyama, Keisuke; Kato, Masato; Hino, Tetsushi*
no journal, ,
no abstracts in English
