Development of fuel temperature calculation file for high temperature gas-cooled reactors

Inaba, Yoshitomo; Isaka, Kazuyoshi; Fukaya, Yuji; Tachibana, Yukio

JAEA-Data/Code 2014-023, 64 Pages, 2015/01

JAEA-Data-Code-2014-023.pdf:7.15MB

The Japan Atomic Energy Agency has performed the conceptual designs of small-sized High Temperature Gas-cooled Reactor (HTGR) systems, aiming for the deployment of the systems to overseas such as developing countries. The small-sized HTGR systems can provide power generation by steam turbine, high temperature steam for industry process and/or low temperature steam for district heating. In the core thermal and hydraulic designs of HTGRs, it is important to evaluate the maximum fuel temperature so that the thermal integrity of the fuel is ensured. In order to calculate and evaluate the fuel temperature on personal computers (PCs) in a convenient manner, the calculation file based on the Microsoft Excel were developed. In this report, the basic equations used in the calculation file, the calculation method and procedure, and the results of the validation calculation are described.

Evaluation of hot spot factors for thermal and hydraulic design of HTTR

Maruyama, So; Yamashita, Kiyonobu; Fujimoto, Nozomu; Murata, Isao; Sudo, Yukio; Murakami, Tomoyuki*; Fujii, Sadao*

Journal of Nuclear Science and Technology, 30(11), p.1186 - 1194, 1993/11

https://doi.org/10.3327/jnst.30.1186

no abstracts in English

Experimental Study on Characteristics of the Hydraulic Behavior in the Standard Fuel Element for the Core Thermal-Hydraulic Design of the Upgraded JRR-3

Kaminaga, Masanori; ; ; Sudo, Yukio

JAERI-M 85-071, 65 Pages, 1985/06

JAERI-M-85-071.pdf:1.67MB

no abstracts in English