Absolute determination of power density in the VVER-1000 mock-up on the LR-0 research reactor

“…Second, experimental measurements of the power distribution obtained from a specific fuel assembly near the flux trap are used to validate the results obtained from the model. In this study, the power distribution is inferred from the gamma emission intensity of the fission products along the FA [36][37][38][39]. The underlying concept of the experimental measurements is based on the proportionality between the fission power density experienced by the fuel and the concentration of fission products in it.…”

Section: Methodsmentioning

confidence: 99%

High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core

Abuzlf,

Castagna,

Makmal

et al. 2023

International Journal of Energy Research

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In this study, a high-fidelity Monte Carlo model was utilized to investigate the localized behavior of the power peaking factor in a reactor core. The model considered the effect of water gaps, also known as flux traps, on the local power peaking. The model, developed using the Serpent code, employs a fine spatial mesh to accurately describe the fission power and burnup distribution. The results obtained from the model were validated through comparison with experimental measurements of the power distribution obtained from the IRR1 facility. The study found that the local accumulation of thermal flux caused by enhanced neutron moderation in the flux trap leads to a highly localized increase in power density, affecting the power peaking factor. The quantification of this effect was a key finding of the study. The results obtained from the study were highly dependent on the model’s fidelity, with significant differences being observed between the power peaking factor calculated on a fine mesh as opposed to that calculated at the plate or assembly scale. Furthermore, the experimental validation of the model enabled the prediction of the power peaking factor in other regions within the fuel assembly, which are not accessible to measurement instrumentation, with a high degree of confidence. The study’s findings may be useful for optimizing reactor design and operation and assessing the safety margins in reactors with similar characteristics.

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“…The LR-0 reactor must have at least six fuel assemblies in a critical configuration, but it can have significantly more. For example, the VVER mini-core mockup has thirty-two ⅓-height assemblies of three different uranium enrichments [5]. Reactor criticality is controlled using the height of the water moderator, and there are a variety of instrumentation tubes and possible configurations.…”

Section: Overview Of the Lr-0 Reactormentioning

confidence: 99%

Complete Sensitivity/Uncertainty Analysis of LR-0 Reactor Experiments with MSRE FLiBe Salt and Perform Comparison with Molten Salt Cooled and Molten Salt Fueled Reactor Models

Brown

Powers

Mueller

et al. 2016

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Absolute determination of power density in the VVER-1000 mock-up on the LR-0 research reactor

Cited by 24 publications

References 6 publications

Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core

Complete Sensitivity/Uncertainty Analysis of LR-0 Reactor Experiments with MSRE FLiBe Salt and Perform Comparison with Molten Salt Cooled and Molten Salt Fueled Reactor Models

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