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Mori, Tetsuya; Hazama, Taira; Katagiri, Hiroki*; Ohgama, Kazuya
Nuclear Technology, 211(1), p.143 - 160, 2025/01
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)The reliability and usefulness of the reaction rate distribution data measured in the prototype fast breeder reactor Monju were examined through a comparison with a calculation using JENDL-4.0, mainly focusing on shielding regions around the reactor core. The 
U(n,f) and 
Ni(n,p) reaction rates sensitive to high-energy neutrons were all judged reliable. The calculation-to-experiment values are slightly worse in the shielding regions, where those for the Ni(n,p) reaction rates were improved by employing JEFF-3.3 instead of JENDL-4.0. A different tendency was observed between the two reactions, probably due to the U(n,f) cross section in the energy range of around 700 eV. The reaction rates of 
U(n,f), 
Pu(n,f), U(n,
), and 
Au(n,) sensitive to the lower energy neutrons were mostly judged reliable. The data in the lower shielding region are less reliable but acceptable for the shielding calculation.
Ohgama, Kazuya; Hazama, Taira; Katagiri, Hiroki*; Takegoshi, Atsushi*; Mori, Tetsuya
Nuclear Technology, 210(8), p.1336 - 1353, 2024/08
Times Cited Count：1 Percentile：51.66(Nuclear Science & Technology)In the prototype fast breeder reactor Monju, reaction rate distributions of fission reaction rates of Pu, U and U, and capture reaction rate of U were measured by using activation foils during its system startup test. The measurements in the core and radial blanket regions were evaluated in detail, and their reliability and usefulness as the validation data for fast reactor neutronics design methodologies were examined through a comparison with calculations. The reaction rate data measured in Monju were confirmed all reliable and useful as the validation data. The fission reactions of Pu, U, and U can be validated with an accuracy of a few percent in the core and blanket regions. The capture reaction of U in the core region also can be validated with a similar accuracy, whereas a precise calculation of the foil cross section is necessary to consider resonance shielding effects of surrounding fuel pins and a foil.
Ohgama, Kazuya; Takegoshi, Atsushi*; Katagiri, Hiroki; Hazama, Taira
Nuclear Technology, 208(10), p.1619 - 1633, 2022/10
Times Cited Count：4 Percentile：51.78(Nuclear Science & Technology)Ohgama, Kazuya; Katagiri, Hiroki; Takegoshi, Atsushi*; Hazama, Taira
Nuclear Technology, 207(12), p.1810 - 1820, 2021/12
Times Cited Count：4 Percentile：39.96(Nuclear Science & Technology)Ohgama, Kazuya; Takegoshi, Atsushi; Katagiri, Hiroki*; Hazama, Taira
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05
LiF scintillating and MSGC neutron detectors in JAERINakamura, Tatsuya; Katagiri, Masaki; Yamagishi, Hideshi; Tanaka, Hiroki; Sakasai, Kaoru; Soyama, Kazuhiko
Hamon, 15(1), p.67 - 73, 2005/01
Development of scintillating and gaseous neutron detectors in Japan Atomic Energy Research Institute is briefly described. In this paper, the performances of the developed 2-d neutron detectors, concerning ZnS/LiF scintillating detectors with wavelength shifting fiber read-out and micro-strip gas chambers with individual read-out, are presented.
Ohgama, Kazuya; Takegoshi, Atsushi; Katagiri, Hiroki*; Hazama, Taira
no journal, ,
no abstracts in English
