Zobrazeno 1 - 10
of 313
pro vyhledávání: '"Iwamoto Osamu"'
Publikováno v:
EPJ Web of Conferences, Vol 294, p 07001 (2024)
Graphite is a candidate of moderator in innovative nuclear reactors such as high-temperature gas-cooled reactors and molten salt reactors. Scattering of thermal neutrons by a moderator material has a significant impact on the reactor core design. To
Externí odkaz:
https://doaj.org/article/5f9143d3b2dd46e8a2c0637b131725e8
The uranium-233 neutron capture cross section between 3 keV and 1 MeV was evaluated with the new alpha value recently measured at the Los Alamos National Laboratory LANCE facility and compiled in the EXFOR library. The obtained capture cross section
Externí odkaz:
http://arxiv.org/abs/2408.10098
Autor:
Iwamoto Osamu, Iwamoto Nobuyuki, Kunieda Satoshi, Minato Futoshi, Nakayama Shinsuke, Kimura Atsushi, Nakamura Shoji, Endo Shunsuke, Nagaya Yasunobu, Tada Kenichi, Konno Chikara, Matsuda Norihiro, Yokoyama Kenji, Taninaka Hiroshi, Oizumi Akito, Okita Shoichiro
Publikováno v:
EPJ Web of Conferences, Vol 284, p 14001 (2023)
Japanese Evaluated Nuclear Data Library version 5 (JENDL-5) was released in 2021. JENDL-5 is intended to extend its generality from JENDL-4.0 by covering a wide variety of nuclear data for applications not only to nuclear design and decommissioning,
Externí odkaz:
https://doaj.org/article/2d67d0c649ee484a96813e22857c6107
Autor:
Iwamoto Osamu
Publikováno v:
EPJ Web of Conferences, Vol 281, p 00009 (2023)
Evaluation of covariance for JENDL was virtually started after the release of JENDL-3.2. The covariance data were obtained for 16 nuclides and compiled to the JENDL-3.2 Covariance File. At the time of the JENDL-4.0 development, covariances were much
Externí odkaz:
https://doaj.org/article/0711c813037e4e69bfe4f79ca2c6fcf8
Autor:
Katabuchi Tatsuya, Iwamoto Osamu, Hori Jun-ich, Kimura Atsushi, Iwamoto Nobuyuki, Nakamura Shoji, Rovira Gerard, Endo Shunsuke, Shibahara Yuji, Terada Kazushi, Kodama Yu, Nakano Hideto, Sato Yaoki, Matsuura Shota
Publikováno v:
EPJ Web of Conferences, Vol 281, p 00014 (2023)
The neutron capture cross sections of 237Np, 243Am and 241Am in the keV energy region were measured by the time-of-flight method at the Japan Proton Accelerator Research Complex (J-PARC). Characterization of the minor actinide samples were made to re
Externí odkaz:
https://doaj.org/article/306e7e59ddf64ea1a5228a4f49f2bfb8
Publikováno v:
EPJ Web of Conferences, Vol 281, p 00002 (2023)
It was tried to get useful information feedback on cross section and covariance by application of extended bias factor method with experimental benchmarks’ C/E, sensitivity coefficient and covariance data. As a result, it was succeeded to distingui
Externí odkaz:
https://doaj.org/article/36689cc1d72542fdbf3c8e715579d786
Autor:
Endo Shunsuke, Kimura Atsushi, Nakamura Shoji, Iwamoto Osamu, Iwamoto Nobuyuki, Rovira Gerard
Publikováno v:
EPJ Web of Conferences, Vol 281, p 00012 (2023)
In resonance analyses, experimental uncertainties affect the accuracy of resonance parameters. The resonance analysis code REFIT can consider the statistical uncertainty of the experimental data when evaluating the resonance parameter uncertainty. Ho
Externí odkaz:
https://doaj.org/article/702b29df2c3948538d986312604033e7
Autor:
Minato, Futoshi, Iwamoto, Osamu
Fission fragment yield evaluations are one of the important nuclear data studies. Fission accompanies various physical observables such as prompt fission neutron, prompt fission gamma, and delayed-neutrons. When evaluating fission fragment yields, a
Externí odkaz:
http://arxiv.org/abs/2404.17728
Publikováno v:
Journal of Nuclear Science and Technology 61 (2024) 57
The $^{242}$Pu neutron-induced fission cross section was evaluated from 100 keV to 200 MeV. The experimental $^{242}$Pu and $^{235}$U fission cross sections and their ratios in the EXFOR library were reviewed and analysed by the least-squares method.
Externí odkaz:
http://arxiv.org/abs/2309.07489
Autor:
Endo, Shunsuke, Kawamura, Shiori, Okudaira, Takuya, Yoshikawa, Hiromoto, Rovira, Gerard, Kimura, Atsushi, Nakamura, Shoji, Iwamoto, Osamu, Iwamoto, Nobuyuki
Neutron total and capture cross sections of Lanthanum(La)-139 were measured at the Accurate Ne-utron-Nucleus Reaction measurement Instrument (ANNRI) of the Materials and Life Science Experimental Facility (MLF) in the Japan Proton Accelerator Researc
Externí odkaz:
http://arxiv.org/abs/2308.08802