Effect of error propagation of nuclide number densities on Monte Carlo burn-up calculations
- 1. Chuden CTI Co., Ltd., 1-4-6 Masaki, Naka-ku, Nagoya 460-8690 (Japan)
- 2. Department of Material Science and Energy Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603 (Japan)
- 3. Chubu Electric Power Co., Inc., 20-1 Kitasekiyama, Odaka-cho, Midori-ku, Nagoya 459-8522 (Japan)
Description
As a result of improvements in computer technology, the continuous energy Monte Carlo burn-up calculation has received attention as a good candidate for an assembly calculation method. However, the results of Monte Carlo calculations contain the statistical errors. The results of Monte Carlo burn-up calculations, in particular, include propagated statistical errors through the variance of the nuclide number densities. Therefore, if statistical error alone is evaluated, the errors in Monte Carlo burn-up calculations may be underestimated. To make clear this effect of error propagation on Monte Carlo burn-up calculations, we here proposed an equation that can predict the variance of nuclide number densities after burn-up calculations, and we verified this equation using enormous numbers of the Monte Carlo burn-up calculations by changing only the initial random numbers. We also verified the effect of the number of burn-up calculation points on Monte Carlo burn-up calculations. From these verifications, we estimated the errors in Monte Carlo burn-up calculations including both statistical and propagated errors. Finally, we made clear the effects of error propagation on Monte Carlo burn-up calculations by comparing statistical errors alone versus both statistical and propagated errors. The results revealed that the effects of error propagation on the Monte Carlo burn-up calculations of 8 x 8 BWR fuel assembly are low up to 60 GWd/t
Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2006.09.010;
- PII
- S0306-4549(06)00191-5;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 33
- Journal Issue
- 17-18
- Journal Page Range
- p. 1424-1436
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38086140
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPUTERS; EQUATIONS; ERRORS; FUEL ASSEMBLIES; MONTE CARLO METHOD; VERIFICATION
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2006 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.