Development of fuel temperature calculation code for HTGRs
稲葉 良知; 西原 哲夫
Inaba, Yoshitomo; Nishihara, Tetsuo
In order to ensure the thermal integrity of fuel in High Temperature Gas-cooled Reactors (HTGRs), it is necessary that the maximum fuel temperature in normal operation is to be lower than a thermal design target. In the core thermal-hydraulic design of block-type HTGRs, the maximum fuel temperature should be evaluated considering data such as thermal power, core geometry, power density and neutron fluence distributions, and core coolant flow distribution. The fuel temperature calculation code used in the design stage of the High Temperature engineering Test Reactor (HTTR) presupposes to run on UNIX systems, and its operation and execution procedure are complicated and are not user-friendly. Therefore, a new fuel temperature calculation code named FTCC which has a user-friendly system such as a simple and easy operation and execution procedure, was developed. This paper describes calculation objects and models, basic equations, improvement points from the HTTR design code in FTCC, and the result of a validation calculation with FTCC. The calculation result obtained by FTCC provides good agreement with that of the HTTR design code, and then FTCC will be used as one of the design codes for HTGRs. In addition, the effect of cooling forms on the maximum fuel temperature is investigated by using FTCC. As a result, it was found that the effect of center hole cooling for hollow fuel compacts and gapless cooling with monolithic type fuel rods on reducing the temperature is very high.
使用言語 : English
掲載資料名 : Annals of Nuclear Energy
: 101
ページ数 : p.383 - 389
発行年月 : 2017/03
出版社名 : Elsevier
特許データ :
論文URL :
キーワード : HTGR; HTTR; Core Thermal-hydraulic Design; Maximum Fuel Temperature; Calculation Code
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 :
登録番号 : AA20160049
抄録集掲載番号 : 45000114
論文投稿番号 : 18441
Accesses  (From Jun. 2, 2014)
- Accesses
分野:Nuclear Science & Technology
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