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Volumn 118, Issue 2, 1997, Pages 89-96

Advanced vessel cooling system concept for high-temperature gas-cooled reactors

Author keywords

Advanced vessel cooling system; HTGR

Indexed keywords

ACCIDENT PREVENTION; COOLING SYSTEMS; CORE DISRUPTIVE ACCIDENTS; EXPERIMENTAL REACTORS; FAILURE ANALYSIS; HIGH TEMPERATURE REACTORS;

EID: 0031142606     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT97-A35370     Document Type: Article
Times cited : (9)

References (8)
  • 3
    • 84889527573 scopus 로고    scopus 로고
    • Passive Heat Removal by Vessel Cooling System of HTTR during No Forced Cooling Accidents
    • to be published
    • K. KUNITOMI, N. SHIGEAKI, and M. SHINOZAKI, "Passive Heat Removal by Vessel Cooling System of HTTR During No Forced Cooling Accidents," Nucl. Eng. Des. (to be published).
    • Nucl. Eng. Des.
    • Kunitomi, K.1    Shigeaki, N.2    Shinozaki, M.3
  • 5
    • 0002915828 scopus 로고    scopus 로고
    • Japan Society of Mechanical Engineers (in Japanese)
    • Heat Transfer, 4th ed., Japan Society of Mechanical Engineers (in Japanese).
    • Heat Transfer, 4th Ed.
  • 8
    • 84889546032 scopus 로고
    • Upgrading of High Temperature Engineering Test Reactor (HTTR)'s Core Performance by Axial Shuffling of Fuel Blocks
    • Japan Society of Mechanical Engineers/American Society of Mechanical Engineering
    • K. YAMASHITA, S. MARUYAMA, and S. SHIOZAWA, "Upgrading of High Temperature Engineering Test Reactor (HTTR)'s Core Performance by Axial Shuffling of Fuel Blocks," Proc. 3rd Int. Conf. Nuclear Engineering, Japan Society of Mechanical Engineers/American Society of Mechanical Engineering (1995).
    • (1995) Proc. 3rd Int. Conf. Nuclear Engineering
    • Yamashita, K.1    Maruyama, S.2    Shiozawa, S.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.