Abstract
Serpent has historically applied leakage correction as a post-neutron-transport step based on solving a group of deterministic equations using homogenized multi-group data tallied during the neutron transport. A new Monte Carlo approach was developed and implemented for applying leakage correction already during the neutron transport. This new approach solves the fundamental mode (FM) leakage correction equations using continuous energy Monte Carlo and automatically applies the leakage correction to all result variables. The results of the new approach agree well with the deterministic fundamental mode approach, although the scoring of the cumulative migration method diffusion coefficient estimators needed to be scored in a slightly modified manner.
| Original language | English |
|---|---|
| Title of host publication | Mathematics & Computation (M&C) 2021 |
| Publisher | American Nuclear Society (ANS) |
| Pages | 540-548 |
| ISBN (Electronic) | 978-1-71388-631-0 |
| Publication status | Published - 2021 |
| MoE publication type | A4 Article in a conference publication |
| Event | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2021 - Virtual, Raleigh, United States Duration: 11 Apr 2021 → 15 Apr 2021 |
Publication series
| Series | Transactions of the American Nuclear Society |
|---|---|
| Number | 3141 |
| ISSN | 0003-018X |
Conference
| Conference | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2021 |
|---|---|
| Country/Territory | United States |
| City | Raleigh |
| Period | 11/04/21 → 15/04/21 |
Funding
This work has been funded from the LONKERO project under the Finnish National Research Programme on Nuclear Power Plant Safety, SAFIR2022.
Keywords
- critical spectrum
- fundamental mode
- leakage correction
- Monte Carlo
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