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1993•Transactions of the American Nuclear SocietyRequires access

Simulation of safety related transients in an AP600-like reactor using RELAP5/MOD2

E. Elias, Y. Nekhamkin, D. Hasan

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Abstract

This paper presents a simulation model for accident analysis in reactors conceptually similar to a Westinghouse 600 MWe PWR type (AP600) reactor. The model utilizes the IBM version of the RELAP5/MOD2/CYCLE 36 code.

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What this paper is about

This paper presents a simulation model for accident analysis in reactors conceptually similar to a Westinghouse 600 MWe PWR type (AP600) reactor. The model utilizes the IBM version of the RELAP5/MOD2/CYCLE 36 code.

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Available abstract

This paper presents a simulation model for accident analysis in reactors conceptually similar to a Westinghouse 600 MWe PWR type (AP600) reactor. The model utilizes the IBM version of the RELAP5/MOD2/CYCLE 36 code.

Key concepts: Nuclear engineering, Fuel cycle, Pressurized water reactor, IBM, Computer science, Engineering, Environmental science, Materials science

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