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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

[+] Author and Article Information
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 2(4), 041009 (Oct 12, 2016) (8 pages) Paper No: NERS-15-1217; doi: 10.1115/1.4033669 History: Received October 16, 2015; Accepted May 12, 2016

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.

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References

Figures

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Fig. 1

Nodalization of typical three loop NPP

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Fig. 2

Core nodalization sensitivity study with different node numbers

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Fig. 3

Core nodalization with four channels

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Fig. 4

T-H analyzing process for MBLOCA

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Fig. 5

PCTs for break size sensitivity analysis

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Fig. 6

Break size sensitivity study results

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Fig. 7

PCT after operator opens HHSI manually

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Fig. 8

Temperature margin of 982°C when operator opens HHSI at different times

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Fig. 9

PCT after one operator opens GCT-a manually

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Fig. 10

Temperature margin of 982°C when operator opens GCT-a at different times

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Fig. 11

Primary pressure of three cases

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Fig. 12

Secondary pressure of three cases

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Fig. 13

Reactor vessel water level of three cases

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Fig. 14

PCT of three cases

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