Real-time simulation of response to load variation for a ship reactor based on point-reactor double regions and lumped parameter model
Creators
- 1. Department of Nuclear Energy Science and Engineering, Naval University of Engineering, Wuhan 430033 (China)
Description
Research highlights: → We calculate the variation of main parameters of the reactor core by the Simulink. → The Simulink calculation software (SCS) can deal well with the stiff problem. → The high calculation precision is reached with less time, and the results can be easily displayed. → The quick calculation of ship reactor transient can be achieved by this method. - Abstract: Based on the point-reactor double regions and lumped parameter model, while the nuclear power plant second loop load is increased or decreased quickly, the Simulink calculation software (SCS) is adopted to calculate the variation of main physical and thermal-hydraulic parameters of the reactor core. The calculation results are compared with those of three-dimensional simulation program. It is indicated that the SCS can deal well with the stiff problem of the point-reactor kinetics equations and the coupled problem of neutronics and thermal-hydraulics. The high calculation precision can be reached with less time, and the quick calculation of parameters of response to load disturbance for the ship reactor can be achieved. The clear image of the calculation results can also be displayed quickly by the SCS, which is very significant and important to guarantee the reactor safety operation.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2010.12.007Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2010.12.007;
- PII
- S0306-4549(10)00420-2;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 38
- Journal Issue
- 5
- Journal Page Range
- p. 1156-1160
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43031336
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- ACCURACY; COMPUTER CODES; DISTURBANCES; NUCLEAR POWER PLANTS; OPERATION; REACTOR CORES; REACTOR KINETICS EQUATIONS; REACTOR SAFETY; SHIPS; SIMULATION; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; VARIATIONS
- Descriptors DEC
- EQUATIONS; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.