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Nuclear Thermal Hydraulic and Two Phase Flow

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Front. Energy Res. | doi: 10.3389/fenrg.2018.00003

Review on Core Degradation and Material Migration Research in Light Water Reactors

 Jun Wang1*,  Chen Wang2, Kaiyi Shi1 and  Guanghui Su3*
  • 1College of Engineering, University of Wisconsin-Madison, United States
  • 2Department of Engineering Physics, Tsinghua University, China
  • 3Institite of Nuclear Science and Technology, Xi'an Jiaotong University, China

Core Degradation and material migration research is one of the key steps in severe accident research. A review of core degradation and melting materials immigration research in light water reactor is important to encourage relevant research. Relevant experiments and numerical analyses are reviewed in this paper. There have only been a few experiments on severe accidents performed due to their high cost. They focus on different aspects of core degradation and material migration, including early stage and late stage accidents in both PWRs and BWRs. All the current experimental data should be fully utilized due to the limited data available. On the other hand, the data available from numerical analyses for severe accidents is very extensive. There are already many systemic severe accident codes developed by different organizations. They provide severe accident sequences analysis, severe accident prediction and are also important in security policy formulation. At the end of this paper, relevant work in Xi’an Jiaotong University are introduced and these works are expected to reveal parts of severe accident relevant research in China.

Keywords: review, Core degradation, Melting Materials Immigration, experiment, Numerical Analysis

Received: 10 Oct 2017; Accepted: 24 Jan 2018.

Edited by:

ARUN K. NAYAK, Bhabha Atomic Research Centre, India

Reviewed by:

Han Zhang, Karlsruher Institut für Technologie, Germany
Zeyong Wang, Rensselaer Polytechnic Institute, United States  

Copyright: © 2018 Wang, Wang, Shi and Su. This is an open-access article distributed under the terms of the Creative Commons Attribution License (CC BY). The use, distribution or reproduction in other forums is permitted, provided the original author(s) and the copyright owner are credited and that the original publication in this journal is cited, in accordance with accepted academic practice. No use, distribution or reproduction is permitted which does not comply with these terms.

* Correspondence:
Dr. Jun Wang, University of Wisconsin-Madison, College of Engineering, Madison, United States,
Dr. Guanghui Su, Xi'an Jiaotong University, Institite of Nuclear Science and Technology, Xi'an, China,