Preservation of kinetics parameters generated by Monte Carlo calculations in two-step deterministic calculations

Takasugi, Cole; Martin, Nicolas Pierre; Labouré, Vincent M.; Ortensi, Javier; Ivanov, Kostadin; Avramova, Maria

doi:10.1051/epjn/2022056

Title: Preservation of kinetics parameters generated by Monte Carlo calculations in two-step deterministic calculations

Journal Article · Mon Feb 27 00:00:00 EST 2023 · EPJ Nuclear Sciences and Technologies

DOI:https://doi.org/10.1051/epjn/2022056· OSTI ID:1963475

Takasugi, Cole ^[1];

^[2];

^[2]; Ivanov, Kostadin ^[1]; Avramova, Maria ^[1]

North Carolina State Univ., Raleigh, NC (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

The generation of accurate kinetic parameters such as mean generation time Λ and effective delayed neutron fraction β_eff via Monte Carlo codes is established. Employing these in downstream deterministic codes warrants another step to ensure no additional error is introduced by the low-order transport operator when computing forward and adjoint fluxes for bilinear weighting of these parameters. Another complexity stems from applying superhomogenization (SPH) equivalence in non-fundamental mode approximations, where reference and low-order calculations rely on a 3D full core model. In these cases, SPH factors can optionally be computed for only part of the geometry while preserving reaction rates and K-effective, but the impact of such approximations on kinetics parameters has not been thoroughly studied. This paper aims at studying the preservation of bilinearly-weighted quantities in the Serpent–Griffin calculation procedure. Diffusion and transport evaluations of IPEN/MB-01, Godiva, and Flattop were carried out with the Griffin reactor physics code, testing available modeling options using Serpent-generated multigroup cross sections and equivalence data. Verifying Griffin against Serpent indicates sensitivities to multigroup energy grid selection and regional application of SPH equivalence, introducing significant errors; these were demonstrated to be reduced through the use of a transport method together with a finer energy grid.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1963475

Report Number(s):: INL/JOU-21-65377-Rev000; TRN: US2313147

Journal Information:: EPJ Nuclear Sciences and Technologies, Vol. 9, Issue 15; ISSN 2491-9292

Publisher:: EDP SciencesCopyright Statement

Country of Publication:: United States

Language:: English

References (15)

Multiphysics reactor-core simulations using the improved quasi-static method Prince, Zachary M.; Ragusa, Jean C. Annals of Nuclear Energy, Vol. 125 https://doi.org/10.1016/j.anucene.2018.10.056	journal	March 2019
The Evaluation of the Effective Kinetic Parameters and Reactivity of the IPEN/MB-01 Reactor for the International Reactor Physics Experiment Evaluation Project Santos, Adimir dos; Diniz, Ricardo Nuclear Science and Engineering, Vol. 178, Issue 4 https://doi.org/10.13182/NSE14-10	journal	December 2014
Benchmarking ENDF/B-VII.0 van der Marck, Steven C. Nuclear Data Sheets, Vol. 107, Issue 12 https://doi.org/10.1016/j.nds.2006.11.002	journal	December 2006
Modeling of SFR cores with Serpent–DYN3D codes sequence Fridman, E.; Shwageraus, E. Annals of Nuclear Energy, Vol. 53 https://doi.org/10.1016/j.anucene.2012.08.006	journal	March 2013
A general presentation of the SPH equivalence technique in non-fundamental mode cases Hébert, Alain Annals of Nuclear Energy, Vol. 141 https://doi.org/10.1016/j.anucene.2020.107323	journal	June 2020
Computing adjoint-weighted kinetics parameters in Tripoli-4® by the Iterated Fission Probability method Truchet, Guillaume; Leconte, Pierre; Santamarina, Alain Annals of Nuclear Energy, Vol. 85 https://doi.org/10.1016/j.anucene.2015.04.025	journal	November 2015
Proposal of Direct Calculation of Kinetic Parameters β_effand Based on Continuous Energy Monte Carlo Method Nauchi, Yasushi; Kameyama, Takanori Journal of Nuclear Science and Technology, Vol. 42, Issue 6 https://doi.org/10.1080/18811248.2004.9726417	journal	June 2005
Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method Nauchi, Yasushi; Kameyama, Takanori Journal of Nuclear Science and Technology, Vol. 47, Issue 11 https://doi.org/10.1080/18811248.2010.9711662	journal	November 2010
Improvements to the Modeling of the Treat Reactor and Experiments Ortensi, J.; Wang, Y.; Labouré, V. EPJ Web of Conferences, Vol. 247 https://doi.org/10.1051/epjconf/202124706025	journal	January 2021
Validation of the Griffin application for TREAT transient modeling and simulation Ortensi, Javier; Baker, Benjamin A.; Johnson, Matthew P. Nuclear Engineering and Design, Vol. 385 https://doi.org/10.1016/j.nucengdes.2021.111478	journal	December 2021
Validation of the MORET 5 Monte Carlo Transport Code on Reactor Physics Experiments Leclaire, Nicolas; Duhamel, Isabelle Journal of Nuclear Engineering, Vol. 2, Issue 1 https://doi.org/10.3390/jne2010007	journal	March 2021
Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code Leppänen, Jaakko; Aufiero, Manuele; Fridman, Emil Annals of Nuclear Energy, Vol. 65 https://doi.org/10.1016/j.anucene.2013.10.032	journal	March 2014
Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion Labouré, Vincent; Wang, Yaqi; Ortensi, Javier Annals of Nuclear Energy, Vol. 128 https://doi.org/10.1016/j.anucene.2019.01.003	journal	June 2019
Calculating the Effective Delayed Neutron Fraction with Monte Carlo Meulekamp, Robin Klein; van der Marck, Steven C. Nuclear Science and Engineering, Vol. 152, Issue 2 https://doi.org/10.13182/NSE03-107	journal	February 2006
Validation of Pin-Resolved Reaction Rates, Kinetics Parameters, and Linear Source MOC in MPACT Liu, Yuxuan; Vaughn, Kyle; Kochunas, Brendan Nuclear Science and Engineering, Vol. 195, Issue 1 https://doi.org/10.1080/00295639.2020.1780853	journal	August 2020

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