Assessment of ASSERT-PV for prediction of critical heat flux in CANDU bundles-Reference-Cited by-同舟云学术

Assessment of ASSERT-PV for prediction of critical heat flux in CANDU bundles

Published:2014-09 Issue: Volume:276 Page:216-227
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Rao Y.F.^ORCID,Cheng Z.,Waddington 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

Reference14 articles.

1. Simulation of flow and phase distribution in vertical and horizontal bundles using the ASSERT-4 subchannel code;Carver;Nucl. Eng. Des.,1990

2. Two-phase turbulent mixing and buoyancy drift in rod bundles;Carlucci;Nucl. Eng. Des.,2004

3. Assessment of subchannel code ASSERT-PV for prediction of post-dryout heat transfer in CANDU bundles;Cheng,2014

4. Full scale water CHF testing of the CANFLEX bundle;Dimmick,1999

5. Some aspects of critical-heat-flux enhancement in tubes;Doerffer,2000

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3. The effect of the advanced drift-flux model of ASSERT-PV on critical heat flux, flow and void distributions in CANDU bundle subchannels;Annals of Nuclear Energy;2017-06

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