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Journal Articles

Geochemical and grain composition analysis of embankment and debris flow deposits in the Izusan area, Atami City, Shizuoka Prefecture, central Japan

Kitamura, Akihisa*; Okazaki, Sota*; Kondo, Mitsuru*; Watanabe, Takahiro; Nakanishi, Toshimichi*; Hori, Rie*; Ikeda, Masayuki*; Ichimura, Koji; Nakagawa, Yuki; Mori, Hideki*

Shizuoka Daigaku Chikyu Kagaku Kenkyu Hokoku, (49), p.73 - 86, 2022/07

On July 3 2021, a debris flow caused by a landslide from a landfill occurred along the Aizome River in the Izusan area of Atami City, Shizuoka. In this study, debris flow deposits and soil samples were characterized in terms of their sedimentology and geochemically analyzed.

Journal Articles

Photodisintegration of $$^{80}$$Se as a probe of neutron capture for the s-process branch-point nucleus $$^{79}$$

Makinaga, Ayano*; Hohara, Shinya*; Utsunomiya, Hiroaki*; Goko, Shinji*; Kaihori, Takeshi*; Akimune, Hidetoshi*; Yamagata, Tamio*; Goriely, S.*; Toyokawa, Hiroyuki*; Harano, Hideki*; et al.

Proceedings of Science (Internet), 28, p.239_1 - 239_4, 2010/12

no abstracts in English

Journal Articles

Photodisintegration of $$^{80}$$Se; Implications for the s-process branching at $$^{79}$$Se

Makinaga, Ayano*; Utsunomiya, Hiroaki*; Goriely, S.*; Kaihori, Takeshi*; Goko, Shinji*; Akimune, Hidetoshi*; Yamagata, Tamio*; Toyokawa, Hiroyuki*; Matsumoto, Tetsuro*; Harano, Hideki*; et al.

Physical Review C, 79(2), p.025801_1 - 025801_8, 2009/02

 Times Cited Count:25 Percentile:79.65(Physics, Nuclear)

Photoneutron cross sections were measured for $$^{80}$$Se immediately above the neutron separation energy with quasimonochromatic $$gamma$$-ray beams to experimentally constrain the E1 $$gamma$$ strength function for $$^{79}$$Se. Two sets of the $$gamma$$ strength function and the level density that equally meet the experimental constraint predict largely different neutron capture cross sections for $$^{79}$$Se. Based on the Maxwell-averaged cross sections of the latest compilation complemented with the predicted cross sections for $$^{79}$$Se, we calculated $$sigma$$N values of the main s-process component using a phenomenological model and deduced empirical abundances of the weak s-process component.

Journal Articles

Photoneutron cross sections for $$^{80}$$Se; Implications for the s-process thermometer

Makinaga, Ayano*; Utsunomiya, Hiroaki*; Kaihori, Takeshi*; Yamagata, Tamio*; Akimune, Hidetoshi*; Goriely, S.*; Toyokawa, Hiroyuki*; Matsumoto, Tetsuro*; Harano, Hideki*; Harada, Hideo; et al.

Nuclear Physics A, 805(1-4), p.564 - 566, 2008/06

Photoneutron cross sections were measured for $$^{80}$$Se near the neutron threshold energy with quasi-monochromatic $$gamma$$ rays. Using the $$^{80}$$Se($$gamma$$,$$n$$) cross section as experimental constraints on the E1 $$gamma$$ strength function, we estimate the neutron capture rates for $$^{79}$$Se. The solar abundance ratio of s-only nuclides $$^{80}$$Kr and $$^{82}$$Kr are analyzed in terms of the s-process branching at $$^{79}$$Se within the local approximation. The corresponding temperature and neutron density regimes are discussed in the light of the s-process scenario in massive stars.

Oral presentation

s-process branching of $$^{79}$$Se

Makinaga, Ayano*; Utsunomiya, Hiroaki*; Goko, Shinji*; Kaihori, Takeshi*; Harada, Hideo; Kitatani, Fumito; Hara, Kaoru; Toyokawa, Hiroyuki*; Harano, Hideki*; Matsumoto, Tetsuro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Cu atom clustering and changes in electrical conductivity and hardness in FeCu alloys irradiated with high-energy particles

Ishikawa, Norito; Okamoto, Yoshihiro; Hirao, Norie*; Nakagawa, Sho*; Iwase, Akihiro*; Hori, Fuminobu*; Ono, Hirotaka*; Kitagawa, Michiharu*; Oshima, Ryuichiro*

no journal, , 

In reactor pressure vessel, hardening due to irradiation is partly originated from Cu precipitation promoted by irradiation. In this study, development of evaluation methodology for embrittlement phenominon is the main objective, and it has been found that hardness change due to irradiation correlates well with accompanied electrical resistivity change.

Oral presentation

Study on effects of swift heavy ion irradiation on the crystal structure in CeO$$_{2}$$ doped with Gd$$_{2}$$O$$_{3}$$

Tahara, Yuki*; Zhu, B.-L.*; Kosugi, Shinya*; Ishikawa, Norito; Okamoto, Yoshihiro; Baba, Yuji; Hirao, Norie; Hori, Fuminobu*; Matsui, Toshiyuki*; Iwase, Akihiro*

no journal, , 

In present light-water nuclear power plants, it is useful to dope some elements, which have a high neutron absorption cross section, into fuels (UO$$_{2}$$) in order to control the initial reactivity. During the operation of reactors, UO$$_{2}$$ fuels are exposed to irradiation with high energy fission products which have energies around 100 MeV. Therefore, it is important to study the effects of high energy fission products on UO$$_{2}$$ fuels. Cerium dioxide (CeO$$_{2}$$) has been used so far as a simulation material for UO$$_{2}$$ because it has the same fluorite structure as that of UO$$_{2}$$. In this study, CeO$$_{2}$$ pellets doped with Gd$$_{2}$$O$$_{3}$$ were irradiated with 200 MeV Xe$$^{14+}$$ ions to simulate the irradiation effects of high energy fission products on UO$$_{2}$$ doped with Gd$$_{2}$$O$$_{3}$$. The X-ray diffraction spectra show that the lattice constant of CeO$$_{2}$$ increases with increasing the amount of the Gd-doping. In addition, it also increases by the irradiation and the effect of the irradiation becomes more remarkable by doping Gd$$_{2}$$O$$_{3}$$.

Oral presentation

Radiation effect of high-energy heavy ions on the structure of CeO$$_{2}$$ doped with Gd$$_{2}$$O$$_{3}$$

Tahara, Yuki*; Zhu, B.-L.*; Kosugi, Shinya*; Hori, Fuminobu*; Matsui, Toshiyuki*; Iwase, Akihiro*; Ishikawa, Norito; Okamoto, Yoshihiro; Baba, Yuji; Hirao, Norie

no journal, , 

no abstracts in English

Oral presentation

Raddiation effect of swift heavy ions on the structure of CeO$$_{2}$$ doped with Gd$$_{2}$$O$$_{3}$$ and Er$$_{2}$$O$$_{3}$$

Tahara, Yuki*; Zhu, B.-L.*; Kosugi, Shinya*; Hori, Fuminobu*; Matsui, Toshiyuki*; Iwase, Akihiro*; Ishikawa, Norito; Okamoto, Yoshihiro; Baba, Yuji; Hirao, Norie

no journal, , 

no abstracts in English

Oral presentation

R&D for introducing silicon carbide materials to safety improvement of BWR's core, 3; Plant transient analysis with SiC cladding fuel for RIA accident

Horie, Hideki*; Takeuchi, Yutaka*; Kakiuchi, Kazuo*; Sato, Hisaki*; Shirasu, Noriko; Saito, Hiroaki; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

The problem in the accident tolerance fuel development was considered in comparison the fuel behavior of SiC/SiC composite cladding tube with current Zry cladding tube. In this study, Reactivity Initiated Accident (RIA) was evaluated using the plant excess security analysis code TRACTTM and the fuel performance code FEMAXI.

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