Simulation of a NuScale core design with the CASL VERA code

Suk, Pavel; Chvála, O.; Maldonado, G. Ivan; Frýbort, Jan

doi:10.1016/j.nucengdes.2020.110956

Cited by 11 publications

(2 citation statements)

References 3 publications

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“…The NuScale SMR is relatively small compared to traditional LWRs, with an active core height of 2.00 m and a diameter of 1.50 m [43]. There are 37 fuel assemblies with SPND strings interstitially located in 12 of these fuel assemblies, with fuel enrichment levels as [44] shown in Fig. 2.…”

Section: Reactor Descriptionsmentioning

confidence: 99%

Towards Realistic and High Fidelity Models for Nuclear Reactor Power Synthesis Simulation with Self-Powered Neutron Detectors

Birri,

Goetz,

Sweeney

et al. 2023

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As presented in this report, a weighting function-based inferencing method is being applied to synthesize the power distribution in next-generation and university research reactors based on simulated self power neutron detector (SPND) responses. The overall goal is to assess the impacts of sensor uncertainty and true power distribution perturbations on the error in the synthesized power distribution. Regarding sensor

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Section: Reactor Descriptionsmentioning

confidence: 99%

Towards Realistic and High Fidelity Models for Nuclear Reactor Power Synthesis Simulation with Self-Powered Neutron Detectors

Birri,

Goetz,

Sweeney

et al. 2023

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show abstract

“…The next logical step would be a full core analysis using the framework described above. The CASL challenge problems [63] or the NuScale core design [64] would be ideal cases to test the codes.…”

Section: Expand Multi-physics Scopementioning

confidence: 99%

Development of a Single-Phase, Transient, Subchannel Code, within the MOOSE Multi-Physics Computational Framework

2022

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Subchannel codes have been widely used for thermal-hydraulics analyses in nuclear reactors. This paper details the development of a novel subchannel code within the Idaho National Laboratory’s (INL) Multi-physics Object Oriented Simulation Environment (MOOSE). MOOSE is a parallel computational framework targeted at the solution of systems of coupled, nonlinear partial differential equations, that often arise in the simulation of nuclear processes. As such, it includes codes/modules able to solve the multiple linear and nonlinear physics that describe a nuclear reactor, under normal operation conditions or accidents. This includes thermal-hydraulics, fuel performance, and neutronics codes, between others. A MOOSE-based subchannel code is a new addition to the fleet of INL-developed codes, based on the MOOSE framework. In this work, we present the derivation of the subchannel equations for a single-phase fluid, we proceed with the description of the algorithm that is used to solve these equations and describe how this algorithm was implemented within MOOSE. We also present how this code can be coupled to the BISON fuel performance code. Next, we verify the friction model and the turbulent mixing model. We calibrate the turbulent modeling parameters for momentum mixing and enthalpy mixing, CT,β. We validate the code using experimental results and last demonstrate the coupling capabilities using a simple example.

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Researches on thermal hydraulics and fuel performance of ATFs during extreme steam generator tube failure without ECCS and DHRS in NuScale

Cai

Qiu

et al. 2022

Annals of Nuclear Energy

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Simulation of a NuScale core design with the CASL VERA code

Cited by 11 publications

References 3 publications

Towards Realistic and High Fidelity Models for Nuclear Reactor Power Synthesis Simulation with Self-Powered Neutron Detectors

Towards Realistic and High Fidelity Models for Nuclear Reactor Power Synthesis Simulation with Self-Powered Neutron Detectors

Development of a Single-Phase, Transient, Subchannel Code, within the MOOSE Multi-Physics Computational Framework

Researches on thermal hydraulics and fuel performance of ATFs during extreme steam generator tube failure without ECCS and DHRS in NuScale

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