An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors-Reference-Cited by-同舟云学术

An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors

Published:2020-03-02 Issue:10 Volume:206 Page:1465-1480
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Lu Cihang¹,Wu Zeyun¹^ORCID,Morgan Sarah¹,Schneider James²,Anderson Mark²,Xu Liangyu³,Baglietto Emilio³,Bucknor Matthew⁴,Weathered Matthew⁴,Bilbao y Leon Sama⁵

Affiliation:

1. Virginia Commonwealth University, Department of Mechanical and Nuclear Engineering, Richmond, Virginia 23219

2. University of Wisconsin – Madison, Department of Engineering Physics, Madison, Wisconsin 53706

3. Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, Cambridge, Massachusetts 02139

4. Argonne National Laboratory, Nuclear Science and Engineering Division, Lemont, Illinois, 60439

5. OECD Nuclear Energy Agency, 2, rue André Pascal, 75775 Paris, France

Funder

U.S. Department of Energy

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2020.1719799

Reference23 articles.

1. Sodium thermal-hydraulics in the pool LMFBR primary vessel

2. T. H. FANNING, A. J. BRUNETT, and T. SUMNER, “The SAS4A/SASSYS-1 Safety Analysis Code System, Version 5,” ANL/NE-16/19, Argonne National Laboratory (2017); https://doi.org/10.2172/1352187.

3. Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project

4. Development of Natural Circulation Analytical Model in Super-COPD Code and Evaluation of Core Cooling Capability in Monju During a Station Blackout

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