Published 2019
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Calculations of thermohydraulic safety parameters for assemblies and core of a BWR-5 using a sub-channel type code
Description
Thermohydraulic and neutronic codes are used to study the behaviour of nuclear reactor power plants. This kind of codes are usually coupled together to produce a faith full result of the simulation of fission reactions inside the core. It is proposed in this work the use at great scale of the sub-channel code SUBCHANFLOW to simulate a nuclear reactor core, and to analyze the thermohydraulic safety parameters due to its rapidity and compared to a CFD code. (author)
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55056087.pdf
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Additional details
Additional titles
- Original title (Spanish)
- Cálculos de parámetros termohidráulicos de seguridad para ensambles y núcleo de un BWR-5 usando un código del tipo sub-canal
Publishing Information
- Imprint Pagination
- 92 p.
- Report number
- INIS-MX--3744
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 55056087
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; FISSION; NEUTRON TRANSPORT; PARTICLE RAPIDITY; POWER PLANTS; REACTOR CORES; REACTOR SAFETY; THERMAL HYDRAULICS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EVALUATION; FLUID MECHANICS; HYDRAULICS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR REACTIONS; PARTICLE PROPERTIES; POWER REACTORS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS