Research on calculation method for successive layer coupling core power distribution expanding
Creators
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
This paper introduces the theoretic model for the successive layer coupling method for the cure power distribution expanding and the solution method for the successive over relaxation equation. The calculation code EXP for the core power distribution expanding, which is based on these methods, has been programmed in FORTRAN90 computer language. The theoretic and metrical data of the unit 1, cycle 11 of Daya Bay NPP are used for analyzing the sensitivity and validity of the expanding calculation results. The results show that, this expanding method uses the theoretic data to build the coupling connection of assemblies in the core and uses the metrical data to calculate the power of all assemblies, and then the expanding calculation is conducted. The method is correct and effective, and has a good adaptability for the invalidation of the measure points. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 36
- Journal Issue
- 2
- Journal Page Range
- p. 1-5
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48083755
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CALCULATION METHODS; COUPLING; DAYA BAY-1 REACTOR; E CODES; EQUATIONS; FUEL ASSEMBLIES; ITERATIVE METHODS; NUCLEAR POWER PLANTS; POWER DISTRIBUTION; PROGRAMMING LANGUAGES; REACTOR CORES; RELAXATION; SENSITIVITY; SENSITIVITY ANALYSIS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 figs., 4 tabs., 6 refs.