Kraken: An upcoming Finnish reactor analysis framework

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

Abstract

This article gives an overview of the development plans and goals for the upcoming Finnish reactor analysis framework Kraken, developed at VTT Technical Research Centre of Finland Ltd. We describe the motivation behind this new code development project, the currently available in-house solver modules used in the framework as well as the coupling approach used for multi-physics simulations. After touching briefly on the development goals, we offer a simple demonstration of a multi-physics problem solved using either continuous energy Monte Carlo neutronics or nodal diffusion neutronics, while keeping
the modules providing thermal hydraulic and fuel behavior feedback same in each case. In the demonstration case, we show how the continuous energy neutron transport solution can serve as an initial computational verification for the reduced order neutronics and how some of the sources of discrepancy between the two can be identified.
Original languageEnglish
Title of host publicationInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
PublisherAmerican Nuclear Society ANS
Pages786-795
Number of pages10
ISBN (Electronic)978-0-89448-769-9
Publication statusPublished - 2019
MoE publication typeA4 Article in a conference publication
EventInternational Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering - Portland, United States
Duration: 25 Aug 201929 Aug 2019

Conference

ConferenceInternational Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering
CountryUnited States
CityPortland
Period25/08/1929/08/19

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  • Cite this

    Valtavirta, V., Hovi, V., Loukusa, H., Rintala, A., Sahlberg, V., Tuominen, R., & Leppänen, J. (2019). Kraken: An upcoming Finnish reactor analysis framework. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 (pp. 786-795). American Nuclear Society ANS.