Development of Unstructured Mesh-Based Numerical Method for Sodium-Water Reaction Phenomenon-Reference-Cited by-同舟云学术

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Development of Unstructured Mesh-Based Numerical Method for Sodium-Water Reaction Phenomenon

Published:2018-08-10 Issue:1-2 Volume:205 Page:119-127
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Uchibori A.¹,Watanabe A.²,Takata T.¹,Ohshima H.¹

Affiliation:

1. Japan Atomic Energy Agency, Fast Reactor Cycle System Research and Development Center, 4002 Narita, O-arai, Ibaraki 311-1393, Japan

2. NDD Corporation, Fast Reactor Cycle System Research and Development Center, 1-1-6 Jonan, Mito, Ibaraki 310-0803, Japan

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2018.1499323

Reference10 articles.

1. Numerical Approach to the Safety Evaluation of Sodium—Water Reaction

2. Numerical Methodology of Sodium-Water Reaction with Multiphase Flow Analysis

3. Computational Methodology of Sodium-Water Reaction Phenomenon in Steam Generator of Sodium-Cooled Fast Reactor

4. Numerical analysis of supersonic gas jets into liquid pools with or without chemical reaction using the SERAPHIM program

5. An Empirical Equation for Thermodynamic Properties of Light Hydrocarbons and Their Mixtures I. Methane, Ethane, Propane andn‐Butane

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1. Highly underexpanded helium jet and its effect on dust resuspension under in-vessel loss of coolant accident of fusion reactor;Nuclear Fusion;2022-08-24

2. Numerical analysis of the Sodium–Water Reaction in a minichannel to evaluate the safety of a Printed Circuit Steam Generator;Journal of Nuclear Science and Technology;2022-03-10

3. Key technologies for future sodium-cooled fast reactors;Sodium-cooled Fast Reactors;2022

4. 3D transient CFD simulation of an in-vessel Loss-Of-Coolant Accident in the EU DEMO fusion reactor;Nuclear Fusion;2020-08-05

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