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Search Results: Records 1-7 displayed on this page of 7
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Journal Articles

Routing study of above core structure with mock-up experiment for ASTRID

Takano, Kazuya; Sakamoto, Yoshihiko; Morohoshi, Kyoichi*; Okazaki, Hitoshi*; Gima, Hiromichi*; Teramae, Takuma*; Ikarimoto, Iwao*; Botte, F.*; Dirat, J.-F.*; Dechelette, F.*

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05

ASTRID has the objective to integrate innovative options in order to prepare the 4th generation reactors. In ASTRID, large number of tubes are installed above each fuel subassembly to monitor the core. These instrumentations such as thermocouples (TC) and Failed Fuel Detection and Location (FFDL) systems are integrated into Above Core Structure (ACS) with various sizes tubes. In the present study, the routing study for TC tubes and FFDL tubes was performed with 3D modeling and mock-up experiment of the ACS designed for ASTRID with 1500 MW thermal power in order to clarify the integration process and secure the design hypotheses. Although some problems on fabricability were found in the mock-up experiment, the possible solutions were proposed. The present study gives manufacturing feedback to design team and will contribute to increase the knowledge for ACS design and fabricability.

Journal Articles

Thermal conductivities of Cs-$$M$$-O ($$M$$ = Mo or U) ternary compounds

Tokushima, Kazuyuki*; Tanaka, Kosuke; Kurosaki, Ken*; Gima, Hiromichi*; Muta, Hiroaki*; Uno, Masayoshi*; Yamanaka, Shinsuke*

Materials Research Society Symposium Proceedings, Vol.1215, p.151 - 156, 2010/10

https://doi.org/10.1557/PROC-1215-V16-34

The thermal diffusivities of Cs$$_{2}$$MoO$$_{4}$$ and Cs$$_{2}$$UO$$_{4}$$ using samples fabricated by hot press and SPS techniques were measured by a laser flash method in the range from room temperature to 823 K for Cs$$_{2}$$MoO$$_{4}$$ and to 900 K for Cs$$_{2}$$UO$$_{4}$$. The thermal conductivities of these cesium ternary oxides were quite low compared with UO$$_{2}$$ and MOX fuel. This is consistent with previous findings. These results would be useful for evaluating the thermal performance of MOX fuels at the high burn-up region in the fast reactors.

Oral presentation

Advancement of detailed core bowing analysis code for fast reactor, 4; Overall plan for thermal bowing experiments of simulated subassemblies

Ota, Hirokazu*; Ogata, Takanari*; Kusumi, Koji*; Ohgama, Kazuya; Yamano, Hidemasa; Futagami, Satoshi; Nakagawa, Naoki*; Kawabata, Ryo*; Gima, Hiromichi*; Matsubara, Shinichiro*

no journal, , 

no abstracts in English

Oral presentation

Advancement of detailed core bowing analysis code for fast reactor, 5; Thermal bowing experiment using a single simulated subassembly

Nakagawa, Naoki*; Kawabata, Ryo*; Gima, Hiromichi*; Matsubara, Shinichiro*; Ota, Hirokazu*; Ogata, Takanari*; Kusumi, Koji*; Ohgama, Kazuya; Yamano, Hidemasa; Futagami, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Evaluation of earthquake and tsunami on sodium cooled reactor, 3; Study on manual control of decay heat removal system by operating the air cooler dampers

Gima, Hiromichi*; Yamada, Yumi*; Kanei, Mikako*; Shimakawa, Yoshio*; Kubo, Shigenobu

no journal, , 

no abstracts in English

Oral presentation

Investigation on fuel cycle based on actinide management towards sustainable use of nuclear energy, 4; Cycle concept with ACM

Konishi, Yuki*; Shimada, Takashi*; Ishida, Hitomi*; Nishimura, Keisuke*; Ban, Yasutoshi; Tsubata, Yasuhiro; Sato, Takehiko; Nakase, Masahiko*; Hibi, Koki*; Gima, Hiromichi*; et al.

no journal, , 

Oral presentation

An Evaluation of the analysis precision in the shielding design of advanced fast reactors, 1; The JASPER experiment analyses with the JENDL-4.0 (Bulk configuration)

Gima, Hiromichi*; Tada, Keiko*; Kanazawa, Mitsuhiro*; Oki, Shigeo

no journal, , 

no abstracts in English

7 (Records 1-7 displayed on this page)
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