Evaluation of temperature and flow area variations through the fuel degradation and relocation of the SFD Test 1

Evaluation of temperature and flow area variations through the fuel degradation and relocation of the SFD Test 1–4

Published:2022-06 Issue: Volume:392 Page:111746
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Nishida Koji,Sano Naoki,Kusunoki Takayoshi,Murase Michio

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

Reference26 articles.

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3. Electric Power Research Institute, Use of Modular Accident Analysis Program (MAAP) in Support of Post-Fukushima Applications, 3002001785.

4. Gauntt, R.O., et al., The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box, NUREG/CR-4671 (1989).

5. Comparison and Interpretation Report of the OECD International Standard Problem No. 45 Exercise (QUENCH06), KFZA 6722;Hering;Forschungszentrum Karlsruhe,2002

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