Estimation of fission product source terms for the ISLOCA of a reference PWR plant using MELCOR and MAAP5-Reference-Cited by-同舟云学术

Estimation of fission product source terms for the ISLOCA of a reference PWR plant using MELCOR and MAAP5

Published:2020-12 Issue: Volume:370 Page:110932
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ahn Kwang-Il,Lee Keo-hyoung,Lee Su-won,Hwang Seok-Won,Lee Hyun-Gyo

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference39 articles.

1. The KHNP SOARCA Project: Development Strategy;Ahn,2017

2. Decay Heat Power in Light Water Reactors;ANS,2014

3. Bixler, N.E., 1998. VICTORIA 2.0: A Mechanistic Model for Radionuclide Behavior in a Nuclear Reactor Coolant System under Sever Accident Conditions. SAND93-2301, Sadia National Laboratories, Albuquerque, NM.

4. Cardoni, J.A., 2014. Radionuclide Inventory and Decay Heat Quantification Methodology for Severe Accident Simulations. SAND2014-17667, Sadia National Laboratories, Albuquerque, NM.

5. Castelo, A. de los Reyes, Capitão, J. A., and De Santi, G., 1999. International Standard Problem 40 Aerosol Deposition and Resuspension: Final Comparison Report. NEA/CSNI/R(99)4, OECD Nuclear Energy Agency (NEA).

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. The APR1400 SOARCA study: Insights into the evolution of severe accidents and fission product source term analysis results;Progress in Nuclear Energy;2023-04

2. Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident;International Journal of Energy Research;2022-08-29

3. Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5;Annals of Nuclear Energy;2022-06

4. Best-practice severe accident analysis for the OPR1000 short-term SBO sequence using MELCOR2.2 and MAAP5;Annals of Nuclear Energy;2021-09