Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations

Shane C. Henderson; Tara M. Pandya; Shane Stimpson; Ben Collins

Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations

Shane C. Henderson, Tara M. Pandya, Shane Stimpson, Ben Collins

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

1 Scopus citations

Abstract

Throughout core life, the reactor vessel is continually bombarded with neutron flux embrittling the vessel and limiting its useful life. As a result, it is imperative to adequately predict how much flux has passed through the vessel during all stages of its life, as a means of ensuring it has adequate ductility to preclude a brittle fracture even under design accident conditions. At present many of these predictions are made either by purely deterministic or purely stochastic means, each offering their own advantages and disadvantages. This paper introduces a coupled method for calculating fluence through the VERA framework, which enables modeling incremental accumulations of fluence while simultaneously accounting for several factors as they evolve through core life. The intention of this method is to simplify the calculation process and provide better resource utilization in obtaining the required accuracy.

Original language	English
Title of host publication	International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
Publisher	American Nuclear Society
Pages	1650-1657
Number of pages	8
ISBN (Electronic)	9780894487699
State	Published - 2019
Event	2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 - Portland, United States Duration: Aug 25 2019 → Aug 29 2019

Publication series

Name	International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019

Conference

Conference	2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
Country/Territory	United States
City	Portland
Period	08/25/19 → 08/29/19

Funding

This research was supported by the Consortium for the Advanced Simulation of Light Water Reactors (www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under the U.S. Department of Energy Contract No. DE-AC05-00OR22725) This research used resources of the Compute and Data Environment for Science (CADES) at Oak Ridge National Laboratory, which is supported by the Office of Science of the U.S. Department of Energy under Contract No. DE-AC05-00OR22725.

Keywords

Deterministic
Fluence
Stochastic

Cite this

Henderson, S. C., Pandya, T. M., Stimpson, S., & Collins, B. (2019). Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 (pp. 1650-1657). (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019). American Nuclear Society.

Henderson, Shane C. ; Pandya, Tara M. ; Stimpson, Shane et al. / Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, 2019. pp. 1650-1657 (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

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abstract = "Throughout core life, the reactor vessel is continually bombarded with neutron flux embrittling the vessel and limiting its useful life. As a result, it is imperative to adequately predict how much flux has passed through the vessel during all stages of its life, as a means of ensuring it has adequate ductility to preclude a brittle fracture even under design accident conditions. At present many of these predictions are made either by purely deterministic or purely stochastic means, each offering their own advantages and disadvantages. This paper introduces a coupled method for calculating fluence through the VERA framework, which enables modeling incremental accumulations of fluence while simultaneously accounting for several factors as they evolve through core life. The intention of this method is to simplify the calculation process and provide better resource utilization in obtaining the required accuracy.",

keywords = "Deterministic, Fluence, Stochastic",

author = "Henderson, {Shane C.} and Pandya, {Tara M.} and Shane Stimpson and Ben Collins",

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Henderson, SC , Pandya, TM, Stimpson, S & Collins, B 2019, Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations. in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, American Nuclear Society, pp. 1650-1657, 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, Portland, United States, 08/25/19.

Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations. / Henderson, Shane C.; Pandya, Tara M.; Stimpson, Shane et al.
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, 2019. p. 1650-1657 (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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T1 - Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations

AU - Henderson, Shane C.

AU - Pandya, Tara M.

AU - Stimpson, Shane

AU - Collins, Ben

PY - 2019

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N2 - Throughout core life, the reactor vessel is continually bombarded with neutron flux embrittling the vessel and limiting its useful life. As a result, it is imperative to adequately predict how much flux has passed through the vessel during all stages of its life, as a means of ensuring it has adequate ductility to preclude a brittle fracture even under design accident conditions. At present many of these predictions are made either by purely deterministic or purely stochastic means, each offering their own advantages and disadvantages. This paper introduces a coupled method for calculating fluence through the VERA framework, which enables modeling incremental accumulations of fluence while simultaneously accounting for several factors as they evolve through core life. The intention of this method is to simplify the calculation process and provide better resource utilization in obtaining the required accuracy.

AB - Throughout core life, the reactor vessel is continually bombarded with neutron flux embrittling the vessel and limiting its useful life. As a result, it is imperative to adequately predict how much flux has passed through the vessel during all stages of its life, as a means of ensuring it has adequate ductility to preclude a brittle fracture even under design accident conditions. At present many of these predictions are made either by purely deterministic or purely stochastic means, each offering their own advantages and disadvantages. This paper introduces a coupled method for calculating fluence through the VERA framework, which enables modeling incremental accumulations of fluence while simultaneously accounting for several factors as they evolve through core life. The intention of this method is to simplify the calculation process and provide better resource utilization in obtaining the required accuracy.

KW - Deterministic

KW - Fluence

KW - Stochastic

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BT - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019

PB - American Nuclear Society

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Y2 - 25 August 2019 through 29 August 2019

ER -

Henderson SC , Pandya TM, Stimpson S, Collins B. Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society. 2019. p. 1650-1657. (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations

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