Published 1997
| Version v1
Miscellaneous
Numerical analysis of thermal hydraulics in secondary side steam generator
Description
The author presents the analysis on the possibility for COBRA-TF to model thermal-hydraulics of SG (Steam Generator) secondary side, numerically analyzes the thermal-hydraulic processes of heater section of SG secondary side of Qinshan Nuclear Power Plant, the results are compared with those from ALBERTINE-2
Additional details
Publishing Information
- Imprint Title
- Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety
- Imprint Pagination
- 1493 p.
- Journal Page Range
- p. LL4.1-LL4.6
Conference
- Title
- 5. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 14-18 Apr 1997
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 29048989
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BOUNDARY CONDITIONS; C CODES; COMPARATIVE EVALUATIONS; FLOW MODELS; FLOW RATE; HEAT TRANSFER; HEATERS; HYDRAULICS; NUCLEAR POWER PLANTS; NUMERICAL SOLUTION; QINSHAN-1 REACTOR; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; VAPORS; VOID FRACTION
- Descriptors DEC
- BOILERS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; FLUIDS; GASES; MATHEMATICAL MODELS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS