Effect of compensation error in drift-flux parameters on predictions of thermal-hydraulic parameters in nuclear safety system analysis codes-Reference-Cited by-同舟云学术

Effect of compensation error in drift-flux parameters on predictions of thermal-hydraulic parameters in nuclear safety system analysis codes

Published:2016-04 Issue: Volume:88 Page:398-411
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Ozaki Tetsuhiro^ORCID,Tsukamoto Naofumi,Nakamura Ryosuke,Miyaji Takamasa,Suzuki Riichiro,Hibiki Takashi

Publisher

Elsevier BV

Subject

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

Reference32 articles.

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

2. BWR Refill-Reflood Program; Task4.7-Constitutive Correlations for Shear and Heat Transfer for the BWR Version of TRAC;Andersen,1981

3. BWR Refill-Reflood Program; Task4.7-Model Development, Basic Models for the BWR Version of TRAC;Andersen,1983

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

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

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Sensitivity of two-fluid model calculations to two-group drift-flux correlations used in the prediction of interfacial drag;Experimental and Computational Multiphase Flow;2021-06-14

2. Code performance with improved two-group interfacial area concentration correlation for one-dimensional forced convective two-phase flow simulation;Journal of Nuclear Science and Technology;2018-03-27