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Journal Articles

Simulation of divertor detachment characteristics in JT-60 with superconducting coils

Shimizu, Katsuhiro; Takizuka, Tomonori; Sakurai, Shinji; Tamai, Hiroshi; Takenaga, Hidenobu; Kubo, Hirotaka; Miura, Yukitoshi

Journal of Nuclear Materials, 313-316, p.1277 - 1281, 2003/00

 Times Cited Count:33 Percentile:88.14(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Remote handling demonstration test facility for spallation target

Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Kogawa, Hiroyuki; Akimoto, Atsushi*; Adachi, Junichi*; Hino, Ryutaro

JAERI-Tech 2000-060, 37 Pages, 2000/11

JAERI-Tech-2000-060.pdf:5.54MB

no abstracts in English

Oral presentation

Simulation analyses by observed record considering applicability of rotational spring in soil embedment, 1; Application of SR model

Kishimoto, Miki*; Kumagai, Kazuto*; Habasaki, Atsushi*; Yabushita, Naoto*

no journal, , 

no abstracts in English

Oral presentation

Simulation analyses by observed record considering applicability of rotational spring in soil embedment, 2; Application of pseudo 3DFEM model

Kumagai, Kazuto*; Kishimoto, Miki*; Habasaki, Atsushi*; Yabushita, Naoto*

no journal, , 

no abstracts in English

Oral presentation

Application of numerical simulation technology to the development of nuclear fuels, 2; Development of irradiation behavior simulation for fast reactor MOX fuels

Ozawa, Takayuki; Ikusawa, Yoshihisa; Hirooka, Shun; Kato, Masato; Novascone, S.*; Medvedev, P.*

no journal, , 

As MOX fuels are irradiation under higher linear power conditions up to high burnup in fast reactor, their irradiation behaviors are influenced by properties at high temperature over 2,000 K, FP accumulation and fast neutron irradiation. However, it is difficult to measure and evaluate fuel properties at high temperature, and it takes much cost and long time to evaluate MOX fuel behavior with the actual irradiation tests. In JAEA, based on knowledge accumulated from study on fuel properties and existing results of irradiation tests, a multi-dimension performance code for fast reactor MOX fuels has been developed in cooperation with Idaho National Laboratory (INL) in the framework of the Civil Nuclear Energy Working Group (CNWG) between Japan and the US. The current status and the future subjects of development of irradiation behavior simulation for fast reactor MOX fuels will be introduced.

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