Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor)-Reference-Cited by-同舟云学术

Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor)

Published:2014-05 Issue: Volume:271 Page:499-504
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Shimizu Atsushi,Kawamoto Taiki,Tochio Daisuke,Saito Kenji,Sawahata Hiroaki,Honma Fumitaka,Furusawa Takayuki,Saikusa Akio,Takada Shoji,Shinozaki Masayuki

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

Reference6 articles.

1. Achievement of reactor outlet coolant temperature of 950°C in HTTR;Fujikawa;J. Nucl. Sci. Technol.,2004

2. Replacement of the Filter for Primary Helium circulators of the HTTR, JAERI Technology 2004-024;Furusawa,2004

3. Change in Heat Exchange Performance of VCS Cooler and Its Recovery Works, JAEA Technology 2005-035;Hamamoto,2005

4. Design of high temperature engineering test reactor (HTTR);Saito;JAERI,1994

5. Result of Long-term Operation of HTTR-Rated/Parallel-loaded 30-days Operation, JAEA Technology 2009-005;Tochio,2009

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