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Research Papers

Research and Development of Validation and Drill System for Full Scope of Severe Accident Management Guideline

[+] Author and Article Information
Zhifei Yang

China Nuclear Power Technology Research
Institute (CNPRI),
Shenzhen 518031, Guangdong Province, China
e-mail: yangzhifei163@163.com

Yali Chen

China Guangdong Nuclear Power
Group (CGNPC),
Shenzhen 518038, Guangdong Province, China
e-mail: chenyali.1989@163.com

Hu Luo

GSE Systems, Inc.,
Sykesville, MD 21874-8424
e-mail: tigerluohu@gmail.com

1Corresponding author.

Manuscript received September 23, 2016; final manuscript received May 14, 2017; published online July 31, 2017. Assoc. Editor: Jovica R. Riznic.

ASME J of Nuclear Rad Sci 3(4), 041011 (Jul 31, 2017) (9 pages) Paper No: NERS-16-1109; doi: 10.1115/1.4036892 History: Received September 23, 2016; Revised May 14, 2017

To respond to the urgent needs of verification, training, and drill for full scope severe accident management guidelines (FSSAMG) among nuclear regulators, utilities, and research institutes, the FSSAMG verification and drill system is developed. The FSSAMG includes comprehensive scenarios under power condition, shutdown condition, spent fuel pool (SFP) condition, and refueling conditions. This article summarized the research and development of validation and drill system for FSSAMG by using the severe accident analysis computer code modular accident analysis program 5 (MAAP5). Realistic accident scenarios can be verified and exercised in the developed system to support FSSAMG training, drill, examination, and verification.

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Figures

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Fig. 1

The structure of platform

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Fig. 2

A schematic of the plant systems

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Fig. 3

Containment compartment nodalization

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Fig. 4

The structure of GUI

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Fig. 8

Pressure of the primary reactor coolant system in SBO#1 scenario

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Fig. 9

Pressure of the containment in SBO#1 scenario

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Fig. 10

Core level in SBO#1 scenario

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Fig. 11

Core coolant temperature in SBO#1 scenario

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Fig. 12

Pressure of the primary reactor coolant system in LBLOCA scenario

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Fig. 13

Pressure of the containment in LBLOCA scenario

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Fig. 14

Core level in LBLOCA scenario

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Fig. 15

Core coolant temperature in LBLOCA scenario

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Fig. 16

SFP water temperature in SFP-SBO#8 + LOCA scenario

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Fig. 17

SFP water temperature in SFP-SBO#8 + LOCA scenario

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