A review of sub-channel thermal hydraulic codes for nuclear reactor core and future directions-Reference-Cited by-同舟云学术

A review of sub-channel thermal hydraulic codes for nuclear reactor core and future directions

Published:2018-06 Issue: Volume:332 Page:329-344
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Moorthi A.,Kumar Sharma Anil^ORCID,Velusamy K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference280 articles.

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3. Basehore, K.L., Todreas, N.E., 1980, SUPERENERGY-2: A Multi assembly, Steady-State Computer Code For LMFBR Core Thermal-Hydraulic Analysis, PNL-3379, C00-2245-57TR, August 1980.

4. Basile D., Chierici R., Beghi M., Salina E., Brega E., COBRA-EN, an Updated Version of the COBRA-3C/MIT Code for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores, Report 1010/1 (revised 1.9.99), ENEL-CRTN Compartimento di Milano.

5. Baumann, W., MISTRAL-II, Thermohydraulische Mischströmungsalgorithmen für Stabbündel. KfK 1605, Juni 1972 (in German).

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