Conceptual study of an experimental HTGR upgraded from HTTR

Goto, Minoru; Fukaya, Yuji; Mizuta, Naoki; Inaba, Yoshitomo; Ohashi, Hirofumi; Yan, X.

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 6 Pages, 2018/10

The HTTR (High Temperature engineering Test Reactor) constructed at JAEA-Oarai R&D center is a block-type experimental HTGR (High Temperature Gas-cooled Reactor) with 30 MW thermal power. It attained the first criticality at 1998 and has yielded very useful data for future HTGR design. Although the HTTR was designed very conservatively because the HTTR is the first HTGR for Japan, future HTGRs can be designed with a reasonable conservativeness based on the HTTR data. Additionally, it is possible to enhance the performance of the reactor core by improving the design and introducing new technologies. This paper describes a concept of an experimental HTGR that is upgraded from the HTTR by the reasonable conservativeness, the design improvement and the new technology introduction.

A New IAEA coordinated research project on sodium properties and safe operation of experimental facilities in support of the development and deployment of sodium-cooled fast reactors

Monti, S.*; Latge, C.*; Long, B.*; Azpitarte, O. E.*; Chellapandi, P.*; Stieglitz, R.*; Eckert, S.*; Ohira, Hiroaki; Lee, J.*; Roelofs, F.*; et al.

Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.474 - 481, 2014/04

Experimental study on accelerator driven subcritical reactor, JAERI's nuclear research promotion program, H12-031 (Contract research)

Shiroya, Seiji*; Misawa, Tsuyoshi*; Unesaki, Hironobu*; Ichihara, Chihiro*; Kobayashi, Keiji*; Nakamura, Hiroshi*; Shin, Kazuo*; Imanishi, Nobutsugu*; Kanazawa, Satoshi*; Mori, Takamasa

JAERI-Tech 2004-025, 93 Pages, 2004/03

JAERI-Tech-2004-025.pdf:6.69MB

In view of the future plan of Research Reactor Institute, Kyoto University, the present study consisted of (1) the transmission experiments of high energy neutrons through materials, (2) experimental simulation of ADSR using the Kyoto University Critical Assembly(KUCA), and (3) conceptual neutronics design study on KUR type ADSR using the MCNP-X code. Through the present study, valuable knowledge on the basic nuclear characteristics of ADSR, which is indispensable to promote the study on ADSR, was obtained both theoretically and experimentally. For the realization of ADSR, it is considered to be necessary to accumulate results of research steadily. For this purpose, it is inevitable (1) to compile the more precise nuclear data for the wide energy range, (2) to establish experimental techniques for reactor physics study on ADSR including subcriticality measurement and absolute neutron flux measurement, and (3) to develop neutronics calculation tools which take into account the neutron generation process by the spallation reaction and the delayed neutron behavior.

A New optical fiber system with hybrid functions of power delivery and real-time remote observation for YAG laser welding

Oka, Kiyoshi

Reza Kenkyu, 31(9), p.612 - 617, 2003/09

https://doi.org/10.2184/lsj.31.612

no abstracts in English

Design and validation test of seismic isolation for ITER

Nakahira, Masataka; Takeda, Nobukazu; Takahashi, Hiroyuki*; Yagenchi, Akira*; Akutsu, Yoichi; Tada, Eisuke; Yabana, Shuichi*

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

no abstracts in English

Assembly tool design

*; Nakahira, Masataka; Okawa, Yoshinao; Tada, Eisuke; Seki, Masahiro

JAERI-Tech 96-023, 30 Pages, 1996/06

JAERI-Tech-96-023.pdf:1.03MB

no abstracts in English

Design development of shieldingblanket for fusion experimental reactors

Furuya, Kazuyuki; *; Miura, H.*; *; Kurasawa, Toshimasa; Kuroda, Toshimasa*; *; Sato, Satoshi; Hatano, Toshihisa; Takatsu, Hideyuki; et al.

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.256 - 259, 1996/00

no abstracts in English

Integration of test modules in the main blanket and vacuum vessel design

Nakahira, Masataka; Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 95-035, 20 Pages, 1995/07

JAERI-Tech-95-035.pdf:0.64MB

no abstracts in English

Design and R&D activities on ceramic breeder blanket for fusion experimental reactors in JAERI

Kurasawa, Toshimasa; Takatsu, Hideyuki; Sato, Satoshi; Nakahira, Masataka; Furuya, Kazuyuki; Hashimoto, T.*; Kawamura, Hiroshi; Kuroda, Toshimasa*; Tsunematsu, Toshihide; Seki, Masahiro

Fusion Technology 1994, Vol.2, 0, p.1233 - 1236, 1995/00

no abstracts in English

Critical element development of standard components for pipe welding/cutting by CO laser

Oka, Kiyoshi; Kakudate, Satoshi; Nakahira, Masataka; Tada, Eisuke; Obara, Kenjiro; *; *; *; Shibanuma, Kiyoshi; Seki, Masahiro

JAERI-Tech 94-033, 20 Pages, 1994/11

JAERI-Tech-94-033.pdf:1.25MB

no abstracts in English