Published March 2018
| Version v1
Journal article
Comparative analysis of coolant average temperature control schemes for PWR nuclear power plant
Creators
- 1. National Energy Pressurized Water Reactor Technology Research Center, Chengdu (China)
- 2. Science and Technology Laboratory on Reactor System Design, Nuclear Power Institute of China, Chengdu (China)
Description
The coolant average temperature control system is the core control system of PWR nuclear power plant. The paper gives a comparative analysis among different coolant average temperature control schemes, through which it makes clear that the coolant average temperature control scheme based on practical engineering is mature, and override the other three schemes. The reason is that the simulation results of the other three are insufficient or only approaching to the first scheme. It is greatly encouraged to discuss the coolant average temperature control scheme from different angles. Although such discussion cannot obtain the immediate results overriding the current scheme, it will bring aspirations even breakthroughs in this field. (author)
Additional details
Identifiers
Publishing Information
- Journal Title
- China Nuclear Power
- Journal Volume
- 11
- Journal Issue
- 1
- Journal Page Range
- p. 99-104
- ISSN
- 1674-1617
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 54110589
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTROL SYSTEMS; COOLANTS; NUCLEAR POWER PLANTS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SIMULATION; TEMPERATURE CONTROL
- Descriptors DEC
- CONTROL; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 14 figs., 21 refs.; http://dx.doi.org/10.12058/zghd.2018.01.099