Drift-flux model for rod bundle geometry-Reference-Cited by-同舟云学术

Drift-flux model for rod bundle geometry

Published:2015-08 Issue: Volume:83 Page:229-247
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Ozaki Tetsuhiro^ORCID,Hibiki Takashi

Funder

University of Illinois at Urbana-Champaign

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference43 articles.

1. Thermal-hydraulics Division (THD), Numerical Analysis of Two-phase Flow;Atomic Energy Society of Japan (AESJ),1993

2. Standard Method for Evaluation Using Best Estimate Code Based on Uncertainty and Scaling Analyses with Statistical Approach;Atomic Energy Society of Japan (AESJ),2008

3. The physical closure laws in the CATHARE code;Bestion;Nucl. Eng. Des.,1990

4. TRAC-BF1/MOD1 Models and Correlations;Borkowski,1992

5. Quantifying Reactor Safety Margins;Boyack,1989

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