Fuel temperature analysis method for channel-blockage accident in HTTR-Reference-Cited by-同舟云学术

Fuel temperature analysis method for channel-blockage accident in HTTR

Published:1994-09 Issue:1 Volume:150 Page:69-80
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Maruyama So,Fujimoto Nozomu,Sudo Yukio,Kiso Yoshihiro,Hayakawa Hitoshi

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

Reference9 articles.

1. Assessment of fuel integrity of the high temperature engineering test reactor (HTTR) and its permissible design limit;Hayashi;JAERI-M 89–162,1989

2. Experimental studies on thermal and hydraulic performance of fuel stack of VHTR (II);Hino;J. Atom. Energy Soc. Jpn.,1986

3. trump3-jr: A finite difference computer program for nonlinear heat conduction problems;Ikushima;JAERI-M 84-017,1985

4. Present status of HTGR research and development in JAERI;JAERI,1988

5. Evaluation guide for safety assessment of light water nuclear power plant;Japanese Nuclear Safety Commission,1978

Cited by 6 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. ONE-DIMENSIONAL NETWORK MODELLING OF A VHTR PRISMATIC BLOCK FUEL ASSEMBLY;Proceeding of International Heat Transfer Conference 17;2023

2. CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors;Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment;2019

3. Risk averse decision making under catastrophic risk;European Journal of Operational Research;2014-11

4. DEVELOPMENT OF A CORE THERMO-FLUID ANALYSIS CODE FOR PRISMATIC GAS COOLED REACTORS;Nuclear Engineering and Technology;2014-10

5. Thermal analysis of prismatic gas-cooled reactor core under coolant channel blockage accidents;Annals of Nuclear Energy;2014-09