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

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.

1. CAUDVAP V 3.60: a Computer Program for Flow Distribution and Pressure Drop Calculation in a MTR Type Core, INVAP S. E;Abbate,2003

2. TERMIC v. 4.1: a Program for the Calculus and Thermal-hydraulic Design of Research Reactor Cores, INVAP;Abbate,2003

3. Final Safety Analysis Report of Tehran Research Reactor;AEOI,2009

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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