Evaluation of core material energy change during the in-vessel phase of Fukushima Daiichi Unit 3 based on observed pressure data utilizing GOTHIC code analysis

Author:

Sato Ikken1,Arai Yuta2,Yoshikawa Shinji1

Affiliation:

1. Oarai Research and Development Institute, Japan Atomic Energy Agency, Ibaraki, Japan

2. Engineering Department, CSA of Japan Co., Ltd, Tokyo, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference27 articles.

1. Tokyo Electric Power Company Holdings, Inc. Unit 3 Primary Containment Vessel Internal Investigation. [cited 2020 Jun 12] Available from: https://www.tepco.co.jp/en/nu/fukushima-np/handouts/2017/images/handouts_171130_03-e.pdf, 2017 Nov. 30.

2. Humphries LL, Beeny BA et al. MELCOR Computer Code Manuals. SAND2017-0455 O; 2017. Albuquerque, NM: Sadia National Laboratories.

3. Development of Severe Accident Analysis Code SAMPSON in IMPACT Project

4. Allison C, Hohorst J Role of RELAP/SCDAPSIM in Nuclear Safety. Hindawi Publishing Corporation. Science and Technology of Nuclear Installations. Article ID 425658; 2010 Jan 10.

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