A state-of-the-art review of the reactor lower head models employed in three representative U.S. severe accident codes-Reference-Cited by-同舟云学术

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A state-of-the-art review of the reactor lower head models employed in three representative U.S. severe accident codes

Published:2003-04 Issue:3 Volume:42 Page:361-382
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Ahn Kwang-II,Kim Dong-Ha

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference62 articles.

1. MELCOR 1.8.4 Sensitivity Analysis of Severe Accident Progressions for LOCA Scenarios in APR 1400;Ahn,2003

2. Severe Accident Code ASTEC Development and Validation;Allelein,1999

3. SCDAP/RELAP5/MOD3.1 Code Manual, Volume 11: Damage Progression Model Theory;Allison,1993

4. Latest Findings of RASPLAV;Asmolov,1998

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1. Modeling of annular gap thickness formed by interaction between corium and water in lower head of reactor vessel;Nuclear Engineering and Design;2020-12

2. Transient heat transfer in internally heated corium pool;Applied Thermal Engineering;2018-12

3. Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems;Science and Technology of Nuclear Installations;2017

4. A two dimensional approach for temperature distribution in reactor lower head during severe accident;Annals of Nuclear Energy;2015-11

5. Comparative study of the hydrogen generation during short term station blackout (STSBO) in a BWR;Annals of Nuclear Energy;2015-09

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