Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

Author:

Fukano Yoshitaka1

Affiliation:

1. Japan Atomic Energy Agency, 1 Shiraki, Tsuruga-shi 919-1279, Fukui, Japan e-mail:

Abstract

Local subassembly faults (LFs) have been considered to be of greater importance in safety evaluation in sodium-cooled fast reactors (SFRs) because fuel elements were generally densely arranged in the subassemblies (SAs) in this type of reactors, and because power densities were higher compared with those in light water reactors. A hypothetical total instantaneous flow blockage (HTIB) at the coolant inlet of an SA gives most severe consequences among a variety of LFs. Although an evaluation on the consequences of HTIB using SAS4A code was performed in the past study, SAS4A code was further developed by implementing analytical model of power control system in this study. An evaluation on the consequences of HTIB in an SFR by this developed SAS4A code was also performed in this study. It was clarified by the analyses considering power control system that the reactor would be safely shut down by the reactor protection system triggered by either of 116% over power or delayed neutron detector (DND) trip signals. Therefore, the conclusion in the past study that the consequences of HTIB would be much less severe than that of unprotected-loss-of-flow (ULOF) was strongly supported by this study. Furthermore, SAS4A code was newly validated using four in-pile experiments which simulated HTIB events. The validity of SAS4A application to safety evaluation on the consequence of HTIB was further enhanced in this study. Thus, the methodology of HTIB evaluation was established in this study together with the past study and is applicable to HTIB evaluations in other SFRs.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference31 articles.

1. Development of Safety Assessment Methodology on Fuel Element Failure Propagation in SFR and Its Application to Monju;J. Nucl. Sci. Technol,2015

2. Vaughan, G. J., 1985, “Event Tree Analysis of the Subassembly Accident,” International Topical Meeting on Fast Reactor Safety, Guernsey, UK, May 12–16, pp. 457–463.

3. Schleisiek, K., 1985, “Risk Oriented Analysis of Subassembly Accidents,” International Topical Meeting on Fast Reactor Safety, Guernsey, UK, pp. 141–149.

4. Updating of Adventitious Fuel Pin Failure Frequency in Sodium-Cooled Fast Reactors and Probabilistic Risk Assessment on Consequent Severe Accident in Monju;J. Nucl. Sci. Technol,2015

5. Updating of Local Blockage Frequency in the Reactor Core of SFR and PRA on Consequent Severe Accident in Monju;J. Nucl. Sci. Technol.,2017

Cited by 4 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3