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Journal Articles

Analytical study of SPERT-CDC test 859 using fuel performance codes FEMAXI-8 and RANNS

Taniguchi, Yoshinori; Udagawa, Yutaka; Amaya, Masaki

Annals of Nuclear Energy, 139, p.107188_1 - 107188_7, 2020/05

https://doi.org/10.1016/j.anucene.2019.107188
 Times Cited Count：1 Percentile：9.76(Nuclear Science & Technology)

JAEA Reports

A Study on thermal interactions between coolant and pressurizer structures during a long transient of the ROSA-V station blackout-scenario experiment

Suzuki, Mitsuhiro

JAERI-Tech 2002-071, 171 Pages, 2002/10

JAERI-Tech-2002-071.pdf:11.26MB

no abstracts in English

Journal Articles

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

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