TY - GEN

T1 - UNCERTAINTY CALCULATIONS WITH OPENMOC FOR LATTICE REACTOR PHYSICS

AU - Hashemi, M.

AU - Reifarth, R.

AU - Macian-Juan, R.

AU - Hernandez-Solis, A.

N1 - Publisher Copyright:
© 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.

PY - 2022

Y1 - 2022

N2 - OpenMOC is a deterministic neutron transport code using the method of characteristics (MOC) for full-core 3D reactor physics analysis developed at Massachusetts Institute of Technology. OpenMOC relies on user input for macroscopic cross-sections data and currently does not perform self-shielding of the multi-group macroscopic cross-sections and any burnup calculations. This work aims to add perturbation methods to OpenMOC concerning cross-section uncertainties and lattice perturbations. Typical measurement uncertainties of the thermal neutron flux in commercial LWRs are about 3 to 5% at the positions of measurement (fuel assembly guide tubes). In this work, a total 100 different input files were prepared for OpenMOC based on covariance information from the ENDF/B-VII. The final objective is to estimate the impact that covariance data have in the multi-group flux obtained by OpenMOC at a PWR lattice configuration domain. In the end, this project has successfully demonstrated how the total Monte Carlo method can in principle be used in conjunction with OpenMOC.

AB - OpenMOC is a deterministic neutron transport code using the method of characteristics (MOC) for full-core 3D reactor physics analysis developed at Massachusetts Institute of Technology. OpenMOC relies on user input for macroscopic cross-sections data and currently does not perform self-shielding of the multi-group macroscopic cross-sections and any burnup calculations. This work aims to add perturbation methods to OpenMOC concerning cross-section uncertainties and lattice perturbations. Typical measurement uncertainties of the thermal neutron flux in commercial LWRs are about 3 to 5% at the positions of measurement (fuel assembly guide tubes). In this work, a total 100 different input files were prepared for OpenMOC based on covariance information from the ENDF/B-VII. The final objective is to estimate the impact that covariance data have in the multi-group flux obtained by OpenMOC at a PWR lattice configuration domain. In the end, this project has successfully demonstrated how the total Monte Carlo method can in principle be used in conjunction with OpenMOC.

KW - Method Of Characteristics (MOC)

KW - NJOY

KW - OpenMOC

KW - Uncertainty Calculations

UR - http://www.scopus.com/inward/record.url?scp=85184960290&partnerID=8YFLogxK

U2 - 10.13182/PHYSOR22-37584

DO - 10.13182/PHYSOR22-37584

M3 - Conference contribution

AN - SCOPUS:85184960290

T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022

SP - 3541

EP - 3549

BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022

PB - American Nuclear Society

T2 - 2022 International Conference on Physics of Reactors, PHYSOR 2022

Y2 - 15 May 2022 through 20 May 2022

ER -