Published June 2015
| Version v1
Journal article
Simulation and verification of the control system of the reactor primary loop in load following operation
Creators
- 1. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin (China)
Description
With the deepening of the study on the load following operation of nuclear power plant, it is necessary to develop a model aiming at load follow operation. This paper takes the main system of the primary loop of CNP600 PWR nuclear power plant as the study object. The model is built based on RELAP5/MOD3.4 code, on which the control system is simulated, It was verified by operation of typical '12-3-6-3' load following operation mode, step load change and linear change. The results show that the trend and range of parameter variation are the same as operational parameters of nuclear power plant. It reflected the process of load follow operation of CNP600 NPP. The simulation model could be adopted by following safety analysis. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 35
- Journal Issue
- 2
- Journal Page Range
- p. 200-206
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 49047385
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTROL SYSTEMS; NUCLEAR POWER; NUCLEAR POWER PLANTS; OPERATION; PWR TYPE REACTORS; SAFETY ANALYSIS; SIMULATION; VARIATIONS; VERIFICATION
- Descriptors DEC
- ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 14 figs., 1 tab., 5 refs.