An estimation of an operator's action time by using the MARS code in a small break LOCA without a HPSI for a PWR-Reference-Cited by-同舟云学术

An estimation of an operator's action time by using the MARS code in a small break LOCA without a HPSI for a PWR

Published:2007-04 Issue:7 Volume:237 Page:749-760
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Han Seok-Jung,Lim Ho-Gon,Yang Joon-Eon

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference22 articles.

1. ASME, 2002. Standard for probabilistic risk assessment for nuclear power plant applications, draft report, the American society of mechanical engineers, ASME RA-S-2002.

2. Thermal hydraulic behavior of a steam generator tube rupture accident with a total loss of the high pressure safety injection;Han,2004

3. Thermal hydraulic analysis of aggressive secondary cooldown in a small break loss of coolant accident with a total loss of high pressure safety injection;Han,2003

4. Han, S.H. et al., 1998. A private supporting report in level 1 PSA for Ulchin unit 3 & 4, KAERI.

5. Thermal-hydraulic analyses of steam generator tube rupture accident for the KORI nuclear unit 1 pressurized thermal shock study;Hong;Nucl. Technol.,2002

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