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.

Development of flow visualization technique for measurement of exchange flow rates under LOVA condition and results of the preliminary flow visualization experiment

Kunugi, Tomoaki; Takase, Kazuyuki; Ogawa, Masuro; Shibata, Mitsuhiko

JAERI-Tech 96-012, 91 Pages, 1996/03

JAERI-Tech-96-012.pdf:3.51MB

no abstracts in English

The Three-dimensional thermal analysis for the stand-pipe room of HTTR by the STREAM code

Takeda, Takeshi; Kunitomi, Kazuhiko; Baba, Osamu

Proc. 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 1; NURETH6, 0, p.1483 - 1488, 1994/00

no abstracts in English