Power distributions in a nuclear reactor core under various operating conditions and their safety implications
Creators
- 1. Korea Advanced Inst. of Science and Technology, Seoul (Republic of Korea)
Description
A nonlinear reactor model has been developed considering typical feedback effects such as the moderator and fuel temperatures, xenon, and soluble boron. The resulting equation belongs to a class of nonlinear boundary value problems, and it was numerically shown using the arc-length continuation method that the nonlinear feedback equation may have multiple steady-state solutions due to existence of branch points for a range of parameters and feedback coefficients which are determined by various design and operating conditions. Solution diagrams of three distinct types were obtained depending on the values of feedback constants and stability was characterized for each solution. The starting point of instability (first limit point) in the solution diagram decreases as the temperature coefficients become large or the boron concentration increases, which means decrease of stability. When solution diagrams which are divided into stable and unstable regions are obtained for a wide range of feedback coefficients, we can choose the range of the reactor design and operating conditions such that the reactor does not encounter unstable situations
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- Proceedings of the International ENS/ANS Conference on thermal reactor safety. Volume 4
- Imprint Pagination
- 399 p.
- Journal Page Range
- p. 1314-1323.
Conference
- Title
- International ENS/ANS Conference on thermal reactor safety.
- Dates
- 2-7 Oct 1988.
- Place
- Avignon (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 21047156
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FEEDBACK; MATHEMATICAL MODELS; NONLINEAR PROBLEMS; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES
- Descriptors DEC
- DISTRIBUTION; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS