A comparison of constant power depletion algorithms
Creators
- 1. Bettis Atomic Power Laboratory, P.O. Box 79, West Mifflin, PA 15122 (United States)
Description
The depletion capability of the Common Monte Carlo Design Tool (CMCDT), under joint development at the Bettis and Knolls Atomic Power Laboratories, has been extended to include 'constant power' depletion calculations. CMCDT couples the Monte Carlo transport code MC21 and depletion routines that use the VODE variable-coefficient ordinary differential equation solver. Three predictor-corrector 'constant power' methods were implemented - the cell2 and monteburns algorithms, which rely on constant flux computations, and a linear rate method that allows selected components of the coefficient matrix to change linearly during the depletion interval. Comparisons are made of these three coarse step methods against a reference depletion calculation of a 17 x 17 PWR assembly containing Gd-UO2 fuel rods. The linear rate method gave consistently more accurate results, regardless of the size of the coarse time steps and the level of spatial detail within the Gd-UO2 fuel rods. All three methods have difficulty in modeling the fast rate of 157Gd depletion with the cell2 method having the most trouble. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-069-0
- Imprint Pagination
- 21 p.
Conference
- Title
- 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics
- Acronym
- M and C 2009
- Dates
- 3-7 May 2009
- Place
- Saratoga Springs, NY (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42060930
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; C CODES; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DIFFERENTIAL EQUATIONS; FUEL RODS; GADOLINIUM; GADOLINIUM 157; MATHEMATICAL MODELS; MATRICES; MONTE CARLO METHOD; PWR TYPE REACTORS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; EQUATIONS; EVALUATION; EVEN-ODD NUCLEI; FUEL ELEMENTS; GADOLINIUM ISOTOPES; INTERMEDIATE MASS NUCLEI; ISOTOPES; MATHEMATICAL LOGIC; METALS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RARE EARTH NUCLEI; RARE EARTHS; REACTOR COMPONENTS; REACTORS; SIMULATION; STABLE ISOTOPES; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.