Burnup Adaptation Model in STREAM/RASTK Code System
- 1. Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)
Description
It is impossible to quantify the effects and have them considered in the calculations. This will result in the departure of the prediction data from the actual (operation) data and will cause error/bias for the following modeling and operation of the plant. The idea of BUA is that the computed power distribution is sensitive to the spatial distribution of assembly reactivity errors, which is sensitive to the distribution of the assembly burnups. In addition, the change of the plant operating condition will cause a change in the power distribution, which will then cause a change in the burnup distribution. Therefore, by adjusting the assembly burnups, it is possible to produce a better agreement between the calculated and reference power distributions, which is a compensation of the unknown operation condition change in the modeling. The numerical results of a typical OPR1000 core successfully demonstrate the capability of this burnup adaptation technique. Further investigation will be conducted on the optimization problem, like the simultaneous optimization of the factors for all the sub-batches instead of the current sequential process, and the possible automatic sub-batch grouping using machine learning instead of the current manual grouping.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [4 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059223
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; LEARNING; NUCLEAR POWER PLANTS; OPTIMIZATION; POWER DISTRIBUTION; REACTOR CORES; REACTOR OPERATION; S CODES; SPATIAL DISTRIBUTION
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; THERMAL POWER PLANTS
Optional Information
- Notes
- 4 refs, 10 figs