A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor

Author:

Lee Kwi Lim,Ha Kwi-Seok,Jeong Jae-Ho,Choi Chi-Woong,Jeong Taekyeong,Ahn Sang June,Lee Seung Won,Chang Won-Pyo,Kang Seok Hun,Yoo Jaewoon

Funder

Ministry of Science, ICT and Future Planning (MSIP)

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference7 articles.

1. New design options free from a potential sodium freezing issue for a passive DHR system of KALIMER;Eoh;Nucl. Tech,2010

2. Thermal-Hydraulic Model in MARS-LMR, Rep. No. KAERI/TR-4297;Jeong,2011

3. Decay Heat Power in Light Water Reactors, ANSI/ANS-5.1;American Nuclear Society,1979

4. Development of the MATRA-LMR-FB for flow blockage analysis in a LMR;Ha;Nucl. Eng. Tech,2009

5. 4S Safety Analysis, Toshiba Technical Report;Toshiba Corporation,2009

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