Safety equipment demands that the success criterion of useful equipment, operator-action time window, and the damage state of the reactor core can be defined by thermal-hydraulic (T-H) analysis, which makes a basic critical contribution to probabilistic safety assessment (PSA). PSA has been widely used in the safety evaluation and assessment of nuclear power plants (NPPs). A loss-of-coolant accident (LOCA) cannot be controlled without timely safety intervention. Low-power and shut-down (LPSD) conditions of NPPs can be divided into several plant operating states (POSs) in PSA analysis. After the Fukushima nuclear accident, the topic of station black-out (SBO) has drawn widespread concern. However, some LPSD conditions, which result in severe consequences like SBO, have not drawn widespread attention and are thus analyzed and discussed herein. This paper analyzes a medium-break LOCA (MBLOCA) under a certain LPSD condition for a typical three-loop NPP. A simplified method of simulating and selecting operator-action time of MBLOCA for PSA is developed. The proposed method calculates the time windows for both manually opening the high head safety injection system (HHSI) and secondary depressurizing of the system to keep the core undamaged, which could support building PSA model and human reliability analysis.
Skip Nav Destination
e-mail: sunjing@cnpe.cc
e-mail: yangcj@cnpe.cc
Article navigation
October 2016
Research Papers
Low-Power and Shut-Down Condition Medium-Break Loss-of-Coolant Accident Success Criterion Analysis for a Typical Three-Loop Nuclear Power Plant
Jing Sun,
e-mail: sunjing@cnpe.cc
Jing Sun
China Nuclear Power Engineering Co., Ltd.
, No. 117, West 3rd Ring Road, Haidian District, Beijing 100840
, China
e-mail: sunjing@cnpe.cc
Search for other works by this author on:
Changjiang Yang
e-mail: yangcj@cnpe.cc
Changjiang Yang
China Nuclear Power Engineering Co., Ltd.
, No. 117, West 3rd Ring Road, Haidian District, Beijing 100840
, China
e-mail: yangcj@cnpe.cc
Search for other works by this author on:
Jing Sun
China Nuclear Power Engineering Co., Ltd.
, No. 117, West 3rd Ring Road, Haidian District, Beijing 100840
, China
e-mail: sunjing@cnpe.cc
Changjiang Yang
China Nuclear Power Engineering Co., Ltd.
, No. 117, West 3rd Ring Road, Haidian District, Beijing 100840
, China
e-mail: yangcj@cnpe.cc
Manuscript received October 16, 2015; final manuscript received May 12, 2016; published online October 12, 2016. Assoc. Editor: Leon Cizelj.
ASME J of Nuclear Rad Sci. Oct 2016, 2(4): 041009 (8 pages)
Published Online: October 12, 2016
Article history
Received:
October 16, 2015
Revision Received:
May 12, 2016
Accepted:
May 12, 2016
Citation
Sun, J., and Yang, C. (October 12, 2016). "Low-Power and Shut-Down Condition Medium-Break Loss-of-Coolant Accident Success Criterion Analysis for a Typical Three-Loop Nuclear Power Plant." ASME. ASME J of Nuclear Rad Sci. October 2016; 2(4): 041009. https://doi.org/10.1115/1.4033669
Download citation file:
Get Email Alerts
Cited By
Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
ASME J of Nuclear Rad Sci (April 2025)
Impact of the Abrasive Solution Heating Process With Different Techniques on the Etching Parameters for the SSNTD (CN-85)
ASME J of Nuclear Rad Sci (April 2025)
Related Articles
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
ASME J of Nuclear Rad Sci (April,2021)
Special Section: Pressurized Heavy Water Reactors Safety
ASME J of Nuclear Rad Sci (April,2017)
Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
ASME J of Nuclear Rad Sci (April,2018)
Related Proceedings Papers
Related Chapters
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Application of Probabilistic Methods for the Evaluation of Deterministic Deviations from Technical Specifications (PSAM-0277)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)