Two-phase flow natural circulation characteristics inside BWR vessels-Reference-Cited by-同舟云学术

Two-phase flow natural circulation characteristics inside BWR vessels

Published:1994-02 Issue:1-3 Volume:146 Page:253-265
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Abe N.,Yokobori S.,Nagasaka H.,Tsunoyama S.

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

Reference11 articles.

1. Heat removal tests of isolation condenser applied as passive containment cooling system;Nagasaka,1991

2. Study on Natural Circulation BWR with passive safety;Nagasaka;Nucl. Technol.,1990

3. SBWR, A Simplified Boiling Water Reactor;Duncan;Nucl. Engrg. Des.,1988

4. Fundamental study on thermo-hydraulics during start-up in Natural Circulation Boiling Water Reactors, (I) Thermo-hydraulic instabilities;Aritomi;J. of Nucl. Sci. Technol.,1992

5. Transient behavior of natural circulation for boiling two-phase flow (2nd Report, Mechanism of Geysering);Aritomi,1991

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