Development of self-reliant subchannel analysis code CORTH
- 1. Nuclear Power Institute of China, Chengdu (China)
- 2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
CORTH is a subchannel code self-reliant developed by Nuclear Power Institute of China (NPIC) based on four equation model with slip ratio to perform thermal-hydraulic analysis of reactor cores or experimental facility with heating rod bundles. The development of CORTH adopted modular design and object-oriented programming method, and specially provided with graphic user interface for input deck preparing and output analysis. CORTH has been executed software testing by independent third organization to ensure the readability and standardization of coding. Testing data in NPPs, international benchmark and AP1000 nominal condition were used to carry out verifications and validations of CORTH. The results show the good accuracy of CORTH that meets the requirement of engineering design and analysis. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 38
- Journal Issue
- 6
- Journal Page Range
- p. 157-162
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 52062198
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- ACCURACY; BENCHMARKS; CHINA; COMPUTER CODES; DESIGN; ENGINEERING; EQUATIONS; FUEL ELEMENT CLUSTERS; HEATING; INTERFACES; NUCLEAR POWER; NUCLEAR POWER PLANTS; PROGRAMMING; REACTOR CORES; SLIP RATIO; STANDARDIZATION; THERMAL HYDRAULICS; VALIDATION; VERIFICATION
- Descriptors DEC
- ASIA; DIMENSIONLESS NUMBERS; FLUID MECHANICS; FUEL ASSEMBLIES; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER; POWER PLANTS; REACTOR COMPONENTS; TESTING; THERMAL POWER PLANTS
Optional Information
- Notes
- 7 figs., 2 tabs., 10 refs.