Power control system modification and simulation of CPR1000 - 181
Creators
- 1. Department of nuclear science and technology Xi'an Jiaotong University No.28, Xianning West Road, Xi'an, Shaanxi, 710049, P.R. (China)
Description
Due to development of electric power system, the proportion of nuclear power and its needs for load follow operation have become large. Then there would be higher requirements to the power control ability of the nuclear power system. The axial power distribution may change a lot in the operation process and be affected by many factors. In particular, as the power change is performed within a load follow maneuver, several modifications occur in the core from a neutronic view point: the fuel and moderator temperature change, the xenon concentration and distribution are modified, the power distribution skewed axially, etc. These changes need to be adequately counterbalanced to keep both the core critical and the power distribution acceptable. The traditional approach in pressurized water reactors (PWRs) is compensating for the reactivity change due to the power variation by adjusting the soluble boron concentration and moving a limited number of control banks. However, dilution/boronation strategy becomes expensive for short time changes and leads to large volume of liquid effluent, so it is eager about a capability to perform load follow operation without changing soluble boron concentration. CPR1000, one of the main reactor types in China national development, is taken an example in this paper. It adopts a control method called Mode G, using G banks, N banks, R bank and soluble boron to perform the load follow control. According to the analysis of the physics and thermal principle, a two-node dynamic function model was built, putting the coupling coefficient and mutual influence into consideration. By the calculation of these transient parameter values which are acquired by the steady-state calculation of single channel, the core system model of CPR1000 is established. In order to carry out the load follow operation without the boron adjustment, named as BTP mode, the control banks were regrouped to control the average temperature by M banks and axial offset by AO bank. After that, the average temperature control system (M banks control system) and the axial offset control system (AO bank control system) are built. When the optimal control system is connected to the core model simulation platform, the BTP mode load follow operation of the modified CPR1000 is simulated in the end of the paper. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 16 p.
Conference
- Title
- 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
- Acronym
- NPIC and HIMIT 2017
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52075685
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON; COMPUTERIZED SIMULATION; CONCENTRATION RATIO; COUPLING; MODERATORS; OPTIMAL CONTROL; POWER DISTRIBUTION; POWER SYSTEMS; PWR TYPE REACTORS; REACTIVITY; REACTOR CONTROL SYSTEMS; REACTOR INSTRUMENTATION; REACTOR OPERATION; STEADY-STATE CONDITIONS; TEMPERATURE CONTROL; TRANSIENTS; XENON
- Descriptors DEC
- CONTROL; CONTROL SYSTEMS; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUIDS; GASES; NONMETALS; OPERATION; POWER REACTORS; RARE GASES; REACTOR LIFE CYCLE; REACTORS; SEMIMETALS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)