Published November 2019
| Version v1
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Development of Multi-physics High-resolution Safety Analysis Technology for Nuclear Reactor Major Components
Description
For the multidimensional safety analysis, a component scale thermal hydraulics code for a nuclear reactor core is developed and validated. In this development, 3 dimensional thermal hydraulics models for reactor core, downcomer, and lower- and upper-plenum are implemented. In addition, two-dimensional nuclear fuel analysis code is coupled with the core thermal hydraulics code, that is applicable to DBA and DEC accident analysis. With wall condensation and hydrogen transport models, precise analysis for the passive systems of containment and severe accident resistance technology is investigated.
Availability note (English)
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51120143.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 155 p.
- Report number
- KAERI/RR--4489/2019
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 51120143
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ATOM TRANSPORT; COMPUTER CODES; DESIGN-BASIS ACCIDENTS; HYDROGEN; NUCLEAR FUELS; REACTOR COMPONENTS; SAFETY ANALYSIS; SEVERE ACCIDENTS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ELEMENTS; ENERGY SOURCES; FLUID MECHANICS; FUELS; HYDRAULICS; MATERIALS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; NONMETALS; RADIATION TRANSPORT; REACTOR MATERIALS
Optional Information
- Notes
- 14 refs, 156 figs, 37 tabs