Automatic or Semiautomatic Planning of Boiling Water Reactor Core Loading and Operation
Creators
- 1. VTT Energy, Nuclear Energy, P.O.B. 1604, FIN-02044 VTT (Finland)
Description
An automatic process for designing reload and control rod patterns for boiling water reactors has been developed. Starting from a good initial guess, the computer code CORFU suggests improvements in the patterns, which are then tested by a core simulator. The results of the simulation provide feedback to CORFU for the next iteration. A semiautomatic application of the method is, however, often more powerful, i.e. if the obtained solution does not yet fulfil all requirements after some 10 - 100 loading patterns have been tried, then the user should consider modifying the inputs in some suitable way. The code tries to maintain high end of cycle (EOC) reactivity while improving the linear heat generation rates, the critical power ratios and the shutdown margins through fuel bundle moves that increase the burnup at locations where problems have arisen. Control rod patterns are chosen to yield the correct keff for a favourable power distribution in the core. (author)
Additional details
Publishing Information
- Publisher
- Senda Editorial S.A.
- Imprint Place
- Madrid (Spain)
- ISBN
- 84-699-0942-8
- Imprint Title
- M and C'99 - Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
- Imprint Pagination
- 2249 p.
- Journal Page Range
- p. 1667-1673
Conference
- Title
- Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
- Acronym
- M and C'99
- Dates
- 27-30 Sep 1999
- Place
- Madrid (Spain)
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- France
- INIS RN
- 54117069
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; FUEL ELEMENT CLUSTERS; HEAT; POWER DISTRIBUTION; REACTIVITY; REACTOR CORES; REACTOR DESIGN; REACTOR OPERATION; SHUTDOWN; SIMULATORS
- Descriptors DEC
- ANALOG SYSTEMS; DESIGN; ENERGY; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUNCTIONAL MODELS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses