SCALE capabilities for high temperature gas-cooled reactor analysis

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

doi:10.1016/j.anucene.2020.107673

SCALE capabilities for high temperature gas-cooled reactor analysis

Journal Article · Tue Jul 07 00:00:00 EDT 2020 · Annals of Nuclear Energy (Oxford)

DOI:https://doi.org/10.1016/j.anucene.2020.107673· OSTI ID:1649629

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Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

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. Furthermore, 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.

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1649629

Journal Information:: Annals of Nuclear Energy (Oxford), Journal Name: Annals of Nuclear Energy (Oxford) Journal Issue: 1 Vol. 147; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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