Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor

Author:

Wang Shibao12ORCID,Zhang Dalin12ORCID,Liang Yu12,Wang Xinan12,Qiu Suizheng12,Su Guanghui12,Tian Wenxi12

Affiliation:

1. State Key Laboratory of Multiphase Flow in Power Engineering; Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology Xi'an Jiaotong University Xi'an P. R. China

2. School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an P. R. China

Funder

National Natural Science Foundation of China

Publisher

Wiley

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Reference29 articles.

1. A Simplified Interassembly Heat Transfer Model for the Analysis of Liquid-Metal Fast Breeder Reactor Core Restraint Systems

2. The TCLUST1 transient LMFBR intersubassembly heat transfer code;Chang LK;Numer Heat Trans A Appl,1979

3. Khatib‐RahbarM CazzoliEG.TWIST: a transient two‐dimensional intra‐subassembly thermal hydraulics model for LMFBRs; 1984; Brookhaven National lab. USA.

4. A porous body model for predicting temperature distribution in wire-wrapped rod assemblies operating in combined forced and free convection

5. Transient experiments on fast reactor core thermal-hydraulics and its numerical analysis

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