A Conservative Analysis Methodology for a Steam-Line-Break Accident of the SMART-P Plant-Reference-Cited by-同舟云学术

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A Conservative Analysis Methodology for a Steam-Line-Break Accident of the SMART-P Plant

Published:2006-01 Issue:1 Volume:153 Page:41-52
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Chung Young-Jong¹,Kim Hee-Kyung¹,Kim Hee-Cheol¹,Zee Sung-Quun¹

Affiliation:

1. Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon 305-600, Republic of Korea

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT06-A3688

Reference12 articles.

1. Design of advanced integral-type marine reactor, MRX

2. M. H. CHANG, “Basic Design Report of SMART,” KAERI/TR-2142/2002, Korea Atomic Energy Research Institute (2002).

3. H. Y. YOON, “Thermal Hydraulic Model Description of TASS/SMR,” KAERI/TR-1835/2001, Korea Atomic Energy Research Institute (2001).

4. S. SIM, “TASS Code Technical Report: Volume 1 TASS Code Technical Manual,” KAERI/TR-845/97, Korea Atomic Energy Research Institute (1997).

5. RELAP5 DEVELOPMENT TEAM, “RELAP5 Code Manual,” NUREG/CR-5535, Idaho National Engineering Laboratory (1998).

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1. Simulation of Loss of Coolant Accident in an Integral Pressurized Water Reactor (IPWR);Advanced Materials Research;2011-05

2. Fully-coupled transient simulation for RCS and SPCS of an integral reactor plant;Annals of Nuclear Energy;2010-03

3. Validation of the TASS/SMR and MARS Codes for a Natural-Circulation Experiment at the VISTA Facility;Nuclear Technology;2009-01

4. Experimental validation of the helical steam generator model in the TASS/SMR code;Annals of Nuclear Energy;2008-01

5. Safety analysis for an inadvertent control rod withdrawal event during a power operation of an advanced integral reactor;Nuclear Engineering and Design;2007-05

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