LOCA steam condensation loads in BWR Mark II pressure suppression containment system-Reference-Cited by-同舟云学术

LOCA steam condensation loads in BWR Mark II pressure suppression containment system

Published:1987-06 Issue:2 Volume:102 Page:225-228
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kukita Y.,Namatame K.,Takeshita I.,Shiba M.

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. Full-scale Mark II CRT program: test data reports No. 1–12;Kukita;JAERI-M 8598, 8761, 8762, 8763, 8764, 8765, 8887, 8961, 9403, 9404, 9405,1979

2. The noncondensable gas effects on loss-of-coolant accident steam condensation loads in boiling water reactor pressure suppression pool;Kukita;Nucl. Technol.,1983

3. Mark II containment program and acceptance criteria;Anderson;USNRC Report, NUREG-0808,1981

4. A regime map for direct contact condensation;Chan;Int. J. Multiphase Flow,1982

5. Statistical evaluation of steam condensation loads in pressure suppression pool;Kukita;JAERI-M 83-186,1983

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