R&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR-Reference-Cited by-同舟云学术

R&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR

Published:2014-05 Issue: Volume:271 Page:309-313
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ueta Shohei,Sumita Junya,Shibata Taiju,Aihara Jun,Fujita Ichiro,Ohashi Jun,Nagaishi Yoshihide,Muto Takenori,Sawa Kazuhiro,Sakaba Nariaki

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

Reference3 articles.

1. Concept of an inherently-safe high temperature gas-cooled reactor;Ohashi,2011

2. Design of High Temperature Engineering Test Reactor (HTTR), JAERI-1332;Saito,1994

3. Thermodynamic analysis of behavior of HTGR fuel and fission products under accidental air or water ingress conditions, response of fuel, fuel elements and gas-cooled reactor cores under accidental air or water ingress conditions;Minato,1995

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3. Evaluation of Oxidation Performance of TRISO Fuel Particles for Postulated Air-Ingress Accident of HTGR;Journal of Chemistry;2020-05-22

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