Boiling transition predictions for BWR fuel bundles by the subchannel analysis program MENUETT-Reference-Cited by-同舟云学术

Boiling transition predictions for BWR fuel bundles by the subchannel analysis program MENUETT

Published:1987-02 Issue: Volume:99 Page:239-246
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Bessho Yasunori,Uchikawa Sadao

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

Reference16 articles.

1. The Thermal-Hydraulics of a Boiling Water Nuclear Reactor;Lahey,1977

2. General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Applications,1973

3. Subchannel analysis of BWR fuel bundles based on five conservation equations for two-phase flow;Bessho;Trans. ANS,1984

4. Subchannel analysis program for BWR fuel bundles based on five conservation equations of two-phase flow;Bessho;Nucl. Technol.,1985

5. Average volumetric concentration in two-phase flow systems;Zuber;J. Heat Transfer,1965

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3. CRITICAL POWER EXPERIMENTS OF TIGHT FUEL-ROD LATTICE FOR LIGHT-WATER REACTORS;J NUCL SCI TECHNOL;1993

4. Critical Power Experiments of Tight Fuel Rod Lattice for Light Water Reactors;Journal of Nuclear Science and Technology;1993-11

5. PREDICTION OF TRANSIENT BOILING TRANSITION IN BWR FUEL-ROD BUNDLES BY SUBCHANNEL ANALYSIS PROGRAM MENUETT;J NUCL SCI TECHNOL;1988