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Published: 2016-12-30
Abstract Views: 132
Views PDF: 54
DOI: https://doi.org/10.53747/jnst.v6i4.171
Issue
Vol. 6 No. 4 (2016)
Section
Articles
How to Cite
Bui , T. H., Hoang , T. H., & Hoang , M. G. (2016). Safety Analyses of VVER-1200/V491 reactor for longterm station blackout along with small LOCAs. Nuclear Science and Technology, 6(4), 8-17. https://doi.org/10.53747/jnst.v6i4.171

Safety Analyses of VVER-1200/V491 reactor for longterm station blackout along with small LOCAs

Bui Thi Hoa1, Hoang Tan Hung1, Hoang Minh Giang1
1 Nuclear Safety Center, Institute for Nuclear Science and Technology

Main Article Content

Abstract

Performance of  Passive Heat Removal through Steam Generator (PHRS-SG) of VVER-1200/V491 reactor presented in Safety Analysis Report for Ninh Thuan 1 shows that in case of long term station black out (SBO),  VVER-1200/V491 reactor can be cooldown and remained in safety mode at least 24 hours based on PHRS-SG performance. Anyway, long term station blackout along with small break in main coolant pipe of VVER-1200/V491 is assumed to be happening as an extension design condition that needs to be investigated. This study focuses on investigation of SBO along with different size of small break of LOCAs with expectation of finding the range of break size that the reactor is still kept in safety mode during 24 hours. During the investigation, some indicators for fuel damage such as the timing of HA1 actuation or mass of coolant inventory discharged are introduced as necessary information contributed to Severe Accident Management Guideline (SAMG).

Article Details

Keywords

VVER, SBO, RELAP5, SBLOCAs, passive system

References

[1].V.O. Kukhtecvick, V.V.Bezlepkin, S.V.Svetlov, V.G.Sidorov, S.B.Alekseev, V.A.Ilyin and N.V.Lyapin, “Experimental studies of thermohydraulic processes for the Passive heat removal system at the Leningradskaya nuclear power plant”, Atomic Energy, Vol.108, No.5, 2010.
[2]. Ninh Thuan Nuclear Power Project Management Board, NINH THUAN 1 NUCLEAR POWER PLANT PROJECT, Feasibility Study, PART 1, Feasibility Study Description, VOLUME 3, Specialized reports, Report 1, Feasibility Study Safety Analysis, Section 7.5 Deterministic analysis Subsection 7.5.7 Consideration of design capability for beyond design basis accidents. NT1.0-3.101-FS-01.03.01.07.05.07.00.
[3]. Ninh Thuan Nuclear Power Project Management Board, NINH THUAN 1 NUCLEAR POWER PLANT PROJECT, Feasibility Study, PART 1, Feasibility Study Description, Vol. 3, Specialized reports, Report 1, Feasibility Study Safety Analysis, Chapter 7 Safety analysis Section 7.5 Deterministic analysis, Subsections 7.5.1, 7.5.2, 7.5.3, 7.5.4, 7.5.5. pp. 13-23.
[4]. Ninh Thuan Nuclear Power Project Management Board, NINH THUAN 1 NUCLEAR POWER PLANT PROJECT, Feasibility Study, PART 1, Feasibility Study Description, Vol. 3, Specialized reports, Report 1, Feasibility Study Safety Analysis, Section 6.4 Engineered safety features. NT1.0-3.101-FS-01.03.01.06.04-rev02. pp. 94-101.
[5]. Ninh Thuan Nuclear Power Project Management Board, NINH THUAN 1 NUCLEAR POWER PLANT PROJECT, Feasibility Study, PART 1, Feasibility Study Description, Vol. 3, Specialized reports, Report 1, Feasibility Study Safety Analysis, Chapter 6 Description and conformance to the design of plant systems. Section 6.2 Reactor. NT1.0-3.101-FS-01.03.01.06.02-rev02. pp. 123, 22.
[6]. Ninh Thuan Nuclear Power Project Management Board, NINH THUAN 1 NUCLEAR POWER PLANT PROJECT, Feasibility Study, PART 1, Feasibility Study Description, Vol. 3, Specialized reports, Report 1, Feasibility Study Safety Analysis, Chapter 7 Safety analysis Section 7.5 Deterministic analysis, Subsection 7.5.7 Consideration of design capability for beyond design basis accidents. NT1.0-3.101-FS-01.03.01.07.05.07.00. pp. 17.
[7]. Ninh Thuan Nuclear Power Project Management Board, NINH THUAN 1 NUCLEAR POWER PLANT PROJECT, Feasibility Study, PART 1, Feasibility Study Description, Vol. 3, Specialized reports, Report 1, Feasibility Study Safety Analysis, Chapter 7 Safety analysis Section 7.5 Deterministic analysis, Subsection 7.5.6 Anticipated operational occurrences and design basis accidents. pp. 183 – 184.