Applicability confirmation test of optimum decay heat evaluation method for HTGR with HTTR (Non-nuclear heating test); Validation of residual heat evaluation model

Honda, Yuki; Inaba, Yoshitomo; Nakagawa, Shigeaki; Yamazaki, Kazunori; Kobayashi, Shoichi; Aono, Tetsuya; Shibata, Taiju; Ishitsuka, Etsuo

JAEA-Technology 2017-013, 20 Pages, 2017/06

JAEA-Technology-2017-013.pdf:2.52MB

Decay heat is one of an important factor for a safety evaluation of depressurized loss-of-forced cooling accident, a representative high consequence accident, in high temperature gas-cooled reactor (HTGR). Traditionally, a conservative decay heat curve is used for safety analysis according to the regulatory standards. On the other hand, there is growing interest in obtaining test data related to decay heat for the use of uncertainty analysis. However, such data has not been obtained for prismatic-type HTGR. Therefore, we have launched a test program to obtain the decay heat data from the HTTR. As an initial step, an applicability confirmation test of decay heat evaluation method for HTGR was conducted in February 2017 without non-nuclear heating condition. This report introduces an estimation method for the decay heat based on test data using HTTR and shows the results of validation of the reactor residual heat evaluation method which will be used to obtain the decay heat data based on test data.

Status and subjects of thermal-hydraulic analysis for next-generation LWRs with passive safety systems

Aritomi, Masanori*; Onuki, Akira; Arai, Kenji*; ; Yonomoto, Taisuke; Araya, Fumimasa; Akimoto, Hajime

Nihon Genshiryoku Gakkai-Shi, 41(7), p.738 - 757, 1999/00

https://doi.org/10.3327/jaesj.41.738

no abstracts in English

Status and subjects of thermal-hydraulic analyses for next-generation LWRs with passive safety system

Onuki, Akira

Dai-1-Kai Oganaizudo Konsoryu Foramu Koen Rombunshu, p.73 - 82, 1997/00

no abstracts in English

Application of PSA methodology to design improvement of JAERI passive safety reactor (JPSR)

Iwamura, Takamichi; Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.316 - 326, 1996/04

https://doi.org/10.3327/jnst.33.316

no abstracts in English

Study of combined NBI and ICRF enhancement of the D-He fusion yield with a Fokker-Planck code

Yamagiwa, Mitsuru; Kishimoto, Yasuaki; Fujii, Tsuneyuki; Kimura, Haruyuki

Nuclear Fusion, 33(3), p.493 - 500, 1993/00

https://doi.org/10.1088/0029-5515/33/3/I11

no abstracts in English