Thermal-hydraulic modeling of reactivity accidents in MTR reactors | Zendy

H. A. Khater | Zendy; Talal Abu-El-Maty | Zendy; El-Din El-Morshdy | Zendy

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Thermal-hydraulic modeling of reactivity accidents in MTR reactors

Author(s) -

H. A. Khater,

Talal Abu-El-Maty,

El-Din El-Morshdy

Publication year - 2006

Publication title -

nuclear technology and radiation protection

Language(s) - English

Resource type - Journals

SCImago Journal Rank - 0.31

H-Index - 16

eISSN - 1452-8185

pISSN - 1451-3994

DOI - 10.2298/ntrp0602021k

Subject(s) - scram , thermal hydraulics , control rod , nuclear engineering , transient (computer programming) , benchmark (surveying) , fortran , delayed neutron , nuclear reactor core , reactivity (psychology) , hydraulics , core model , research reactor , nuclear reactor , computer science , environmental science , thermodynamics , engineering , heat transfer , mechanical engineering , nuclear physics , neutron , physics , neutron temperature , mathematics , medicine , mathematical analysis , alternative medicine , geodesy , pathology , geography , operating system

This paper describes the development of a dynamic model for the thermal-hydraulic analysis of MTR research reactors during a reactivity insertion accident. The model is formulated for coupling reactor kinetics with feedback reactivity and reactor core thermal-hydraulics. To represent the reactor core, two types of channels are considered, average and hot channels. The developed computer program is compiled and executed on a personal computer, using the FORTRAN language. The model is validated by safety-related benchmark calculations for MTR-TYPE reactors of IAEA 10 MW generic reactor for both slow and fast reactivity insertion transients. A good agreement is shown between the present model and the benchmark calculations. Then, the model is used for simulating the uncontrolled withdrawal of a control rod of an ETRR-2 reactor in transient with over power scram trip. The model results for ETRR-2 are analyzed and discussed

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