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RAMONA-3B, a code for BWR plant transients

D.J. Diamond, Carlo Rüger, D.I. Garber, S.V. Lekach

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Abstract

RAMONA-3B is a code for calculating boiling water reactor (BWR) transients. It is unique in that it can calculate the core with three-dimensional neutronics while calculating the remainder of the nuclear steam supply system (NSSS). An overview of the code is presented in which the neutronics and thermal hydraulics are summarized. Applications of the code are discussed as is the code assessment effort.

About this research paper

What this paper is about

RAMONA-3B is a code for calculating boiling water reactor (BWR) transients. It is unique in that it can calculate the core with three-dimensional neutronics while calculating the remainder of the nuclear steam supply system (NSSS). An overview of the code is presented in which the neutronics and thermal hydraulics are summarized. Applications of the code are discussed as is the code assessment effort.

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Key contribution

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Available abstract

RAMONA-3B is a code for calculating boiling water reactor (BWR) transients. It is unique in that it can calculate the core with three-dimensional neutronics while calculating the remainder of the nuclear steam supply system (NSSS). An overview of the code is presented in which the neutronics and thermal hydraulics are summarized. Applications of the code are discussed as is the code assessment effort.

Key concepts: Neutron transport, Boiling water reactor, Nuclear engineering, Code (set theory), Thermal hydraulics, Remainder, Hydraulics, Boiling

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