Thermal hydraulic aspects of the SBWR design-Reference-Cited by-同舟云学术

Thermal hydraulic aspects of the SBWR design

Published:1993-10 Issue:2 Volume:144 Page:213-222
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Shiralkar B.S.,Alamgir Md.,Andersen J.G.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

Reference20 articles.

1. SBWR passive core and containment cooling test programs;Billig,1992

2. BWR passive containment cooling system by condensation-driven natural circulation;Vierow,1991

3. Quantifying reactor safety margins - Application of code scaling applicability, and uncertainty evaluation methodology for a large-break, loss-of-coolant accident;Boyack;NUREG/CR-5249,1989

4. Evaluation of post-incident cooling systems of light water reactors;Uchida,1964

5. Behavior of steam air systems condensing in cocurrent vertical downflow;Vierow,1990

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