SCALE capabilities for high temperature gas-cooled reactor analysis

Friederike Bostelmann; Cihangir Celik; Mark L. Williams; Ronald J. Ellis; Germina Ilas; William A. Wieselquist

doi:10.1016/j.anucene.2020.107673

SCALE capabilities for high temperature gas-cooled reactor analysis

Friederike Bostelmann, Cihangir Celik, Mark L. Williams, Ronald J. Ellis, Germina Ilas, William A. Wieselquist

Research output: Contribution to journal › Article › peer-review

22 Scopus citations

Abstract

The SCALE code system's ability to address stochastic distributions of fuel particles within a graphite matrix has been revisited in both multigroup (MG) features and continuous-energy (CE) Monte Carlo methods. This paper describes current and emergent SCALE capabilities within the CSAS sequence to address double-heterogeneous systems and presents verification and validation studies of these methods and data. Good agreement was obtained for a high temperature gas-cooled reactor (HTGR) fuel pebble model between CSAS MG eigenvalue calculations and corresponding CE reference solutions. Code-to-code comparisons for this HTGR pebble model showed good agreement of CSAS-KENO and CSAS-Shift CE calculations and the Serpent and MCNP codes in terms of eigenvalues and reaction rate ratios. Validation studies based on two HTGR experiments resulted in good agreement between MG and CE results, as well as between experiment and calculation, although the level of agreement was significantly influenced by the applied ENDF/B nuclear data library.

Original language	English
Article number	107673
Journal	Annals of Nuclear Energy
Volume	147
DOIs	https://doi.org/10.1016/j.anucene.2020.107673
State	Published - Nov 2020

Funding

This work was funded by the US Nuclear Regulatory Commission (NRC). The authors would like to thank Richard Lee and Don Algama of the NRC, as well as to Brad Rearden and Steve Bowman, former SCALE managers, for their support over the years of the development of HTGR analysis capabilities in SCALE. This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ).

Keywords

Double-heterogeneity
HTR-10
HTTR
Pebble-bed reactor
SCALE
Validation

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title = "SCALE capabilities for high temperature gas-cooled reactor analysis",

abstract = "The SCALE code system's ability to address stochastic distributions of fuel particles within a graphite matrix has been revisited in both multigroup (MG) features and continuous-energy (CE) Monte Carlo methods. This paper describes current and emergent SCALE capabilities within the CSAS sequence to address double-heterogeneous systems and presents verification and validation studies of these methods and data. Good agreement was obtained for a high temperature gas-cooled reactor (HTGR) fuel pebble model between CSAS MG eigenvalue calculations and corresponding CE reference solutions. Code-to-code comparisons for this HTGR pebble model showed good agreement of CSAS-KENO and CSAS-Shift CE calculations and the Serpent and MCNP codes in terms of eigenvalues and reaction rate ratios. Validation studies based on two HTGR experiments resulted in good agreement between MG and CE results, as well as between experiment and calculation, although the level of agreement was significantly influenced by the applied ENDF/B nuclear data library.",

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AU - Celik, Cihangir

AU - Williams, Mark L.

AU - Ellis, Ronald J.

AU - Ilas, Germina

AU - Wieselquist, William A.

PY - 2020/11

Y1 - 2020/11

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SCALE capabilities for high temperature gas-cooled reactor analysis

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Keywords

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