The sensitivity analysis for IHTS and SG due to the Large-scale Sodium-Water Reaction event in PGSFR

Author:

Ahn Sang June,Park Gun Yeop,Lee Kwi Lim,Choi ChiwoongORCID,Jeong Taekyeong,Kim Jin Tae,Lee Seung WonORCID,Jeong Jae-Ho

Funder

National Research Foundation

NRF

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Studies towards safety related to sodium in India;Chellapandi,2011

2. Interim Progress Report: Steam Generator Leak Detection System (Rep. No. ANL-KAERI-SFR-13-26);Chien,2013

3. Clinch River Breeder Reactor Project, 1980. Large Sodium-Water Reaction: Preliminary Safety Analysis Report, U.S., (Chap. 15.3-46).

4. Greene, D.A., 1984. Sodium-water reaction phenomena associated with small leaks in LMFBR steam generator, in: Proceedings of the Third International Conference, Oxford, vol. 1, pp. 13–21.

5. IAEA, 2007. Liquid Metal Cooled Reactors: Experience in Design and Operation (Rep. No. IAEATECDOC-1569), International Atomic Energy Agency, Wien (Austria).

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