Development status of the reactor core physics analyses code in COSINE project - 15287
- 1. State Nuclear Power Software Development Center - SNPRI, South Zone of the Future Science and Technology Park, Beijing, 102209 (China)
Description
The COSINE (Core and System Integrated Engine for design and analysis) project is being developed by the State Nuclear Power Software Development Center in China. It is an integrated package including reactor physics codes, thermal hydraulics codes, severe accident analysis codes, probability safety analyses software, humanistic interface etc, which is also the first integrated nuclear engineering code in China. The reactor core physics analyses code (CORE) is one of the package which is used for the physics design. The CORE code employs the node expansion method for diffusion calculation and some additional functions are developed to meet the requirements of AP1000 and CAP1400 design. In this paper, the theory of the CORE code is introduced in detail and some application results are presented. The results show that the CORE code has high accuracy and is suitable for the AP1000 and CAP1400 plant's physics design. (authors)
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- ICAPP 2015 Proceedings
- Imprint Pagination
- 3390 p.
- Journal Page Range
- p. 1845-1849
Conference
- Title
- Nuclear Innovations for a low-carbon future
- Acronym
- ICAPP 2015
- Dates
- 3-6 May 2015
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49004978
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; C CODES; COMPUTERIZED SIMULATION; MULTIGROUP THEORY; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; VALIDATION
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; NEUTRON TRANSPORT THEORY; POWER REACTORS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs.; This record replaces 48095373