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MARS Code Applicability Assessments for the HTGR RCCS  

Kang Doo-Hyuk (Department of Nuclear & Energy Engineering, Cheju National University)
Kim Hyung-Seok (Korea Science and Engineering Foundation)
Chung Bum-Jin (Department of Nuclear & Energy Engineering, Cheju National University)
Publication Information
Journal of Energy Engineering / v.14, no.4, 2005 , pp. 232-240 More about this Journal
Abstract
In this study, the IAEA Benchmark problems far HTR-10 and HTTR RCCS were assessed in order to assess the applicability of MARS code, a thermal-hydraulic safety analysis code developed for water reactors. The calculated results were compared with those or THERMIX, THANPACST2 code, and available experimental data. The calculated results showed generally good agreements with those obtained by the THERMIX code and THANPACST2 code. Deviations were analyzed to be originated from the simplification of complicated geometry and from the modeling capability of heat transfer characteristics in the HTGR components such as water cooler and air tooler. Especially, it was found that the radiation heat transfer in the reactor cavity played an important role in the after heat removal in the RCCS. Thus, it is concluded that MARS code can be successfully applied to the calculation of the RCCS cooling capability of the HTGR in this study.
Keywords
HTGR; RCCS; Thermal hydraulics; MARS;
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1 Jang, J.H.; et al. 'Basic study on high temperature gas cooled reactor technology for hydrogen produc­tion', KAERI (Korea Atomic Energy Research Institute)/RR-2435/2003, Korea, 2003
2 Lee, W.-J.; et al. 'Development of realistic thermal­-hydraulic system analysis code', KAERI/RR-2235, Korea, 2002
3 IAEA (International Atomic Energy Agency), 'Heat transport and afterheat removal for gas cooled reactors under accident conditions', TECDOC-1163, Vienna, 2000, 64-103
4 TAC Technology. 'Net energy verification and deter­mination analyzer', NEVADA Software Package User's Manual, 1997
5 이승욱. '비응축가스 거동 모사를 위한 RELAP5 전산코드 수정', 서울대학교 공학석사학위논문, 2003, 9
6 IAEA (Intemational Atomic Energy Agency), 'Design and evaluation of heat utilization systems for the high temperature engineering test reactor', TECDOC-1236, Vienna, 2001
7 Lee, W.J.; et al, 'Progress of accident analysis codes development for gas-cooled reactors', BE-2004, ANS 2004 Embedded Meeting, to be published, Korea, 2004
8 Frank P. Incropera; David P. DeWitt. 'Fundamentals of heat and mass transfer', Fourth Edition, Chapter 13, Radiation Exchange Between Surfaces