Preliminary thermal-hydraulic safety analysis of Tehran research reactor during fuel irradiation experiment-Reference-Cited by-同舟云学术

Preliminary thermal-hydraulic safety analysis of Tehran research reactor during fuel irradiation experiment

Published:2015-03 Issue: Volume:79 Page:32-39
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Safaei Arshi S.,Khalafi H.^ORCID,Mirvakili S.M.

Publisher

Elsevier BV

Subject

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

Reference19 articles.

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4. COBRA-EN, an Upgraded Version of the COBRA3CIMIT Code for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores,” Report No. 1010/l;Basile,1999

5. A theory of local-boiling burnout and its application to existing data;Bernath;Chem. Eng. Prog. Symp.,1960

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