THERMAL-HYDRAULIC STABILITY ANALYSIS OF SUPERCRITICAL WATER-COOLED FAST REACTORS
This paper summarizes the analysis methods and results of the thermal-hydraulic stability of asupercritical water-cooled fast reactor (SWFR). The stability analysis codes in the frequency domainare developed to study the thermal-hydraulic stability of SWFR which is a fast spectrum SCWRstudied by the University of Tokyo. The stability of SWFR for full-power and partial-poweroperation is investigated. The stability criterion can be satisfied at normal operation through settingan appropriate orifice pressure drop coefficient.
Jiejin Cai Yuki Ishiwatari Satoshi Ikejiri Yoshiaki Oka
Sun Yat-sen University,Guangzhou,China The University of Tokyo,Tokyo,Tokyo,Japan Waseda University,Tokyo,Tokyo,Japan
国际会议
3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors(第三届中国-加拿大超临界水堆研讨会 (CCSC-2012)
西安
英文
1-12
2012-04-18(万方平台首次上网日期,不代表论文的发表时间)