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Journal Articles

Japanese Evaluated Nuclear Data Library version 5; JENDL-5

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Abe, Yutaka*; Tsubakihara, Kosuke*; Okumura, Shin*; Ishizuka, Chikako*; Yoshida, Tadashi*; et al.

Journal of Nuclear Science and Technology, 60(1), p.1 - 60, 2023/01

 Times Cited Count:64 Percentile:99.99(Nuclear Science & Technology)

Journal Articles

Theoretical evaluation of neutron thermal scattering laws of heavy water for JENDL-5

Ichihara, Akira; Abe, Yutaka*

JAEA-Conf 2022-001, p.175 - 180, 2022/11

Thermal neutron scattering law data were calculated for the heavy water molecule toward the fifth version of the Japanese evaluated nuclear data library, JENDL-5. The scattering laws for deuterium and oxygen atoms were computed using the molecular dynamics simulations. The simulations have been performed in the temperature range from 283.6 K to 600 K. The scattering law data have been evaluated in the neutron incident energies between 0.01 meV and 10 eV. With the obtained scattering laws, we calculated the cross sections for the heavy water molecule, and confirmed that the experimental data at room temperature were well reproduced. Moreover, in the computed temperature range, the cross sections were almost consistent with the ENDF/B-VIII.0 evaluations.

Journal Articles

Neutronic design of neutron moderator on a reentrant-hole configuration for Kyoto University Accelerator-based Neutron Source (KUANS)

Okita, Shoichiro; Tasaki, Seiji*; Abe, Yutaka*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 19(3), p.178 - 184, 2020/09

The Kyoto University Accelerator-based Neutron Source (KUANS) is a compact neutron source that is mainly used for spectrometer and detector development. In addition, it is also suited for experiments to study the neutronic design of moderators owing to the relatively low neutron generation yield by $$^{9}$$Be(p,n). We present a neutronic design of the neutron moderator on a reentrant-hole configuration for KUANS to enhance the neutron emission, and some experiments are conducted at KUANS for verification. A polyethylene moderator on a reentrant-hole configuration is designed by PHITS calculation and is introduced to KUANS to obtain intense oblong neutron beams. The intensity of the pulsed neutron beam is experimentally measured. The results reveal that the intensity becomes approximately 1.9 times stronger than that of the conventional rectangular design. In addition, the ratio of its intensity to the conventional intensity increases to approximately threefold as the neutron wavelength increases. It is interesting to note that the longer the neutron wavelength, the more efficiently they are extracted from the inside of the moderator owing to the existence of the reentrant-hole configuration.

JAEA Reports

Behavior of irradiated ATR/MOX fuel under reactivity initiated accident conditions (Joint research)

Sasajima, Hideo; Fuketa, Toyoshi; Nakamura, Takehiko; Nakamura, Jinichi; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*

JAERI-Research 99-060, p.62 - 0, 2000/03

JAERI-Research-99-060.pdf:12.05MB

no abstracts in English

Journal Articles

Behavior of PWR and BWR fuels during reactivity-initiated accident conditions

Fuketa, Toyoshi; Nakamura, Takehiko; Sasajima, Hideo; Nagase, Fumihisa; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*

Proceedings of an International Topical Meeting on Light Water Reactor Fuel Performance (CD-ROM), 15 Pages, 2000/00

no abstracts in English

Journal Articles

MOX fuel behavior under reactivity accident conditions

Sasajima, Hideo; Fuketa, Toyoshi; Ishijima, Kiyomi; Kikuchi, Keiichi*; Abe, Tomoyuki*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Oral presentation

Cross section measurement of hydrogen containing materials, 1; Light water and ethanol

Harada, Masahide; Abe, Yutaka*; Teshigawara, Makoto; Oi, Motoki; Ikeda, Yujiro; Oikawa, Kenichi; Nakajima, Kenji; Kawamura, Seiko

no journal, , 

By using neutron instruments, NOBORU and AMATERAS, in J-PARC spallation neutron source, we started to measure temperature dependent total and scattering cross section data of hydrogenous material ranging in thermal and cold neutron region. The cross section data of light water and ethanol were measured.

Oral presentation

Theoretical study of thermal neutron scattering by light and heavy water with molecular dynamics simulation

Ichihara, Akira; Abe, Yutaka*

no journal, , 

Light and heavy water are being used as moderators in fission reactors. Reliable data of thermal neutron scattering in these materials is essential to the analysis of reactor cores. In this study we tried to evaluate angular distribution and energy spectrum of emitted neutrons employing the information obtained from molecular dynamics simulations. The simulations have been performed for light and heavy water. The thermal neutron scattering has been evaluated by using the fluctuation-dissipation theorem of statistical mechanics, where the trajectory data for hydrogen, deuterium and oxygen atoms were utilized. In calculation, incoherent scattering was assumed to be dominant in light water, while both the coherent and incoherent scattering contributions were considered in heavy water.

Oral presentation

Measurement of cross sections for hydrogenous materials

Harada, Masahide; Abe, Yutaka*; Oikawa, Kenichi; Kawasaki, Takuro; Kawamura, Seiko; Nakajima, Kenji; Inamura, Yasuhiro; Takahashi, Ryuta*; Teshigawara, Makoto; Oi, Motoki; et al.

no journal, , 

no abstracts in English

Oral presentation

Nuclear data evaluation for JENDL-5, 4; Evaluation of thermal neutron scattering law

Abe, Yutaka*; Ichihara, Akira

no journal, , 

In the JENDL-5 thermal neutron scattering law sublibrary, the thermal neutron scattering data have been stored for 37 materials. In Kyoto University and JAEA, we evaluated the scattering law data for light water, heavy water, methane, ethanol, benzene, toluene, m-xylene, mesitylene, and triphenylmethane. We will show the evaluation methods of the thermal neutron scattering and compare the evaluated data with experimental data.

Oral presentation

Cross section measurement of hydrogen containing materials at 20 $$sim$$ 300 K; Methanol, benzene and toluene

Harada, Masahide; Abe, Yutaka*; Teshigawara, Makoto; Oi, Motoki; Ikeda, Yujiro*; Oikawa, Kenichi; Kawamura, Seiko; Inamura, Yasuhiro

no journal, , 

no abstracts in English

Oral presentation

Measurement of cross sections for hydrogenous materials

Harada, Masahide; Abe, Yutaka*; Oikawa, Kenichi; Kawamura, Seiko; Inamura, Yasuhiro; Teshigawara, Makoto; Oi, Motoki; Ikeda, Yujiro*

no journal, , 

no abstracts in English

Oral presentation

Neutron-induced cross-section measurement of hydrogen containing materials at 20 $$sim$$ 300 K; o-xylene, m-xylene and p-xylene

Harada, Masahide; Abe, Yutaka*; Teshigawara, Makoto; Oi, Motoki; Ikeda, Yujiro*; Oikawa, Kenichi; Kawamura, Seiko; Inamura, Yasuhiro

no journal, , 

Hydrogenous materials are mainly applied as a moderator material used in high-intense and small neutron sources because of good moderating characterization for neutrons. Scattering data including total cross sections of cold-thermal neutrons are important to characterize moderators. However, as some measurements are old, we have been continuously and systematically measuring the cross sections of hydrogenous materials since 2018 for a new neutron source development. In this presentation, the measurements of o-xylene, m-xylene and p-xylene carried out in 2020 and 2021 will be presented as a hydrogenous material. The measurements were performed at NOBORU and AMATERAS in MLF of J-PARC. The total cross sections were measured at NOBORU, and the scattering cross sections were measured at AMATERAS. The sample temperatures were 20, 100, 200, 300 K and temperatures near the melting point. The sample was contained in an aluminum cell. The time-of-flight method was used to measure the energy-dependent transmission of the sample. The scattering data was converted to the scattering cross section by a multiple energy chopping. Details will be reported on the day.

Oral presentation

Measurement of cross sections for hydrogenous materials

Harada, Masahide; Abe, Yutaka*; Oikawa, Kenichi; Kawamura, Seiko; Inamura, Yasuhiro; Teshigawara, Makoto; Oi, Motoki; Ikeda, Yujiro*

no journal, , 

no abstracts in English

Oral presentation

Measurement of cross sections for hydrogenous materials

Harada, Masahide; Abe, Yutaka*; Oikawa, Kenichi; Tsuchikawa, Yusuke; Kawamura, Seiko; Inamura, Yasuhiro; Teshigawara, Makoto; Oi, Motoki; Yamaguchi, Yuji; Ikeda, Yujiro*

no journal, , 

no abstracts in English

15 (Records 1-15 displayed on this page)
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