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SMR Core Depletion and Spent Fuel Characterization with Nodal Code Ants

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

Numerous emerging small modular pressurized water reactors rely on compensating core excess reactivity with control rods instead of soluble boron. The spent fuel characterization for these reactors requires detailed modeling of the irradiation due to the distortion of power and neutron spectrum in the vicinity of deeply inserted control rods. This paper presents a micro-depletion-based method implemented in nodal code Ants for calculating spent fuel inventory. The technique utilizes the Kraken reactor simulator framework developed at VTT Technical Research Centre of Finland for preparing group constant data and running coupled fuel cycle simulations. The work is based on calculating LDR lite first fuel cycle with Ants-Kharon-SuperFINIX coupling scheme where group constant data and homogenized microscopic cross sections are prepared with Serpent. Results from the fuel cycle are compared to a reference Serpent solution. The comparison shows that the microscopic depletion model in Ants can produce satisfactory inventory estimates on a core level. Further work contains assessing the advantages of the micro-depletion method over conventional methods and expanding the analysis to higher burnups.
Original languageEnglish
Title of host publicationProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
PublisherAmerican Nuclear Society (ANS)
Pages222-230
ISBN (Electronic)978-0-89448-222-9
Publication statusPublished - 2025
MoE publication typeA4 Article in a conference publication
EventInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2025
: Elevating Peak Performance
- The Westin Denver Downtown, Denver, United States
Duration: 27 Apr 202530 Apr 2025
https://www.ans.org/meetings/mc2025/

Conference

ConferenceInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2025
Country/TerritoryUnited States
CityDenver
Period27/04/2530/04/25
Internet address

Funding

This work has received funding from the NOTCO project under the Finnish National Nuclear Safety and Waste Management Research Programme 2023-2028 SAFER2028.

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