Detailed evaluation of safety injection tank effects on in-vessel severe accident progression in a small break LOCA without safety injection-Reference-Cited by-同舟云学术

Detailed evaluation of safety injection tank effects on in-vessel severe accident progression in a small break LOCA without safety injection

Published:2013-08 Issue: Volume:58 Page:54-59
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Park Rae-Joon,Ha Kwang-Soon,Kim Hwan-Yeol,Song Jin-Ho

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference8 articles.

1. Allison, C.M., et al. 1984. SCDAP/MOD1/V0: A Computer Code for the Analysis of LWR Vessel Behavior During Severe Accident Transients. IS-SAAM-83-002.

2. Bayless, P.D., et al. 1987. Feedwater Transient and Small Break Loss of Coolant Accident Analysis for the Bellefonte Nuclear Plant. NUREG/CR-4741.

3. Bayless, P.D., et al. 1988. Analysis of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5. NUREG/CR-5214.

4. Information and instrumentation availability for accident management: application to YGN 3&4;Kim;J. KNS,1996

5. Lemmon, E.C., 1980. COUPLE/FLUID: A Two Dimensional Finite Element Thermal Conduction and Advection Code. EGG-ISD-SCD-80-1.

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