2021
DOI: 10.1080/00295450.2021.1943122
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Modeling of the Molten Salt Reactor Experiment with SCALE

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Cited by 17 publications
(12 citation statements)
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“…An MCNP-ADDER model of MSRE was developed with the same parameters and as many similarities as possible as the MSRE "slice" model developed by ORNL recently in TRITON [12,13]. The TRITON slice model is noted as a slice through the center of the MSRE core.…”
Section: Code-to-code Benchmarkingmentioning
confidence: 99%
See 1 more Smart Citation
“…An MCNP-ADDER model of MSRE was developed with the same parameters and as many similarities as possible as the MSRE "slice" model developed by ORNL recently in TRITON [12,13]. The TRITON slice model is noted as a slice through the center of the MSRE core.…”
Section: Code-to-code Benchmarkingmentioning
confidence: 99%
“…Additionally, Samples 6-17, 7-10, and 14-63FV were not included in the comparison analysis below. The details of the power history leading up to the first sample (6)(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17) were difficult to ascertain from MSRP reports [10,11] and it was not possible to obtain a cumulative MWhr amount that was within 10% of the reported value. Finally, ADDER burn steps that would correspond to Samples 7-10 and 14-63FV (dated 7/6/66 and 2/27/68, respectively) were accidentally excluded during the run.…”
Section: Comparison To Experimental Datamentioning
confidence: 99%
“…Simulation of the spatially dependent composition of the fuel salt as it passes through the core and primary loop was realized by application of SCALE's depletion solver ORIGEN [18]. Based on the described MSRE IRPhEP benchmark, SCALE was recently used for criticality calculations and an assessment of the impact of different nuclear data libraries and cross section uncertainties on the MSRE's criticality [19]. The SCALE full-core MSRE model developed for this study, as illustrated in Figures 1 through 3, provides the basis for the modeling work described in this report.…”
Section: Previous Msr Simulation Effortsmentioning
confidence: 99%
“…To determine the spatial distribution of the neutron flux and the power in the core, a TRITON-KENO 3D core model was developed. As mentioned above, a model developed based on the MSRE IRPhEP benchmark [19] was used as basis for the model in this work. While TRITON supports the calculation of the neutron flux and the fission rate in a user-defined mesh superimposed over any geometry, the calculation of the power profile requires discretization of the model into individual regions with individual mixtures to obtain mixture-dependent power levels.…”
Section: Full Core Triton-keno Model For Power and Flux Distributions...mentioning
confidence: 99%
“…It is also discussed in a reactor physics benchmark of the MSRE [30]. Recently, SCALE tools were demonstrated in modeling the MSRE [31,32], and fuel depletion results were benchmarked against an analogous model in MCNP and ADDER [33]. The composition utilized in these depletion models represents not only the initial fuel salt that is loaded into the reactor but also corrosion products and impurities (See Section 2.4.2) as these studies are not "multiphysics" fuel depletion simulations (See Section 2.5.1).…”
Section: Initial Fuel Salt Compositionmentioning
confidence: 99%