SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis

Bostelmann, Friederike; Celik, Cihangir; Kile, Robert F.; Wieselquist, William

doi:10.2172/1854475

Cited by 10 publications

(18 citation statements)

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“…The work presented in this report focuses on the application of SCALE for SFR analysis. This work follows previous studies in which SCALE was used for the simulation of heat pipe reactors (HPRs) [26], high-temperature gas-cooled reactors (HTGRs) [17], fluoride salt-cooled high-temperature reactors (FHRs) [1], and molten salt reactors (MSRs) [12]. The corresponding MELCOR studies are found in separate reports [24,23,25].…”

Section: Introductionmentioning

confidence: 75%

“…As an example of the capabilities to determine nuclide-specific decay heat contributions, Figure 12b shows the decay heat of the top 10 contributing nuclides over the first 100 days, Figure 12c shows a shorter time 1 TRITON full-core depletion calculations resulted in fuel inventory for ∼2000 nuclides at EOEC, stored in binary ORIGEN concentration (f71) file. Used in previous non-LWR analysis as a part of the NRC task, the SCALE OBIWAN formatting utility allows for the conversion of these inventories into a JSON-formatted inventory interface file (ii.json), which can then be converted via a Python script into a MELCOR DCH decay heat input file.…”

Section: Decay Heat Summarymentioning

confidence: 99%

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SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor

Shaw,

Bostelmann,

Hartanto

et al. 2023

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Various reactivity calculations were performed with SCALE for the ABTR and, where possible, compared with results available in the open literature. Additionally, SCALE was used to perform a full-core depletion calculation over the 4 month cycle to obtain the nuclide inventory at the end of equilibrium cycle (EOEC). These nuclide inventories, decay heat, power profiles, and reactivity feedback coefficients at EOEC represent the initial conditions for analyzing severe accident scenarios with MELCOR.

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Section: Introductionmentioning

confidence: 75%

Section: Decay Heat Summarymentioning

confidence: 99%

SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor

Shaw,

Bostelmann,

Hartanto

et al. 2023

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“…Based on a SCALE full core model initially developed for a different project (Bostelmann et al, 2021a), the sensitivity and uncertainty analyses for the equilibrium core of the UCB PB-FHR were performed with Sampler and KENO-VI in MG mode for the following quantities of interest. The temperature increases and the density multiplier were chosen to obtain statistically distinguishable results with the Monte Carlo approach, but they do not correspond to actual changes during reactor operation.…”

Section: Ucb Pb-fhrmentioning

confidence: 99%

Key nuclear data for non-LWR reactivity analysis

2023

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An assessment of nuclear data performance for non-light-water reactor (non-LWR) reactivity calculations was performed at Oak Ridge National Laboratory that involved a thorough literature review to collect related observations made across different research institutions, an interrogation of the latest ENDF/B evaluated nuclear data libraries, and propagation of nuclear data uncertainties to key figures of merit associated with reactor safety for six non-LWR benchmarks. The outcome of this comprehensive study was published in a technical report issued by the US Nuclear Regulatory Commission. This paper provides a summary of the study’s key observations and conclusions and demonstrates with two examples how the various methods available in the SCALE code system were used to identify key cross section uncertainties for non-LWR reactivity analyses.

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“…In the latter, the lattice pitch is set to yield the target TRISO particle (or pebble) packing fraction. The choice to prohibit clipping should be preferred over allowing clipping because (1) clipping can cause an unknown fuel mass to be included in the parent unit and (2) clipping can have an impact on moderation since a larger number of partial fuel kernels is directly surrounded by graphite moderator (this effect becomes especially pronounced in systems with thin layers of TRISO particles [7]).…”

Section: User Modeling Strategiesmentioning

confidence: 99%