Modeling of thermo-mechanical and irradiation behavior of mixed oxide fuel for sodium fast reactors

Karahan, Aydın; Buongiorno, Jacopo

doi:10.1016/j.jnucmat.2009.11.021

Cited by 29 publications

(21 citation statements)

References 28 publications

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“…The speed of this process is a highly uncertain quantity and has been the subject of considerable study. 128,[144][145][146][147][148][149][150] Reference 151 describes how BISON is used to solve these equations. The following section includes a result from that paper concerning quantification of the effects of void offset.…”

Section: Central Void Formation In Moxmentioning

confidence: 99%

BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms

et al. 2021

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BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented Simulation Environment (MOOSE) finite element library. One of its major goals is to have a great amount of flexibility in how it is used, including in the types of fuel it can analyze, the geometry of the fuel being modeled, the modeling approach employed, and the dimensionality and size of the models. Fuel forms that can be modeled include standard light water reactor fuel, emerging light water reactor fuels, tri-structural isotropic fuel particles, and metallic fuels. BISON is a platform for research in nuclear fuel performance modeling while simultaneously serving as a tool for the analysis of nuclear fuel designs. Recent research in BISON includes techniques such as the extended finite element method for fuel cracking, exploration of high-burnup light water reactor fuel behavior, swelling behavior of metallic fuels, and central void formation in mixed-oxide fuel. BISON includes integrated documentation for each of its capabilities, follows rigorous software quality assurance procedures, and has a growing set of rigorous verification and validation tests.

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Section: Central Void Formation In Moxmentioning

confidence: 99%

BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms

et al. 2021

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“…The irradiated thermal conductivity for UO2 and MOX are also provided. The correlations taken from references (Karahan (2017(Karahan ( , 2009; Savage (1968); Maeda and Asaga (2004); Billone (1986); Popov et al (2000); Fanning (2017)) were combined to allow for complete density, thermal conductivity, and heat capacity correlations. In the table below, the coefficients used for the heat capacity calculations of UO2 and MOX are provided.…”

Section: Fuel Property Modelingmentioning

confidence: 99%

SAM Theory Manual

Hu¹,

Zou²,

Hu³

et al. 2021

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The System Analysis Module (SAM) is an advanced and modern system analysis tool under development at Argonne National Laboratory for advanced non-LWR reactor safety analysis. It aims to provide fast-running, modest-fidelity, whole-plant transient analyses capabilities, which are essential for fast turnaround design scoping and engineering analyses of advanced reactor concepts. While SAM is being developed as a system-level modeling and simulation tool, advanced modeling techniques being implemented include a reduced-order three-dimensional module, pseudo 3-D conjugate heat transfer modeling in reactor core, flexible and multi-scale modeling of heat transfer between fluid and structures, in addition to the advances in software environments and design, and numerical methods.SAM aims to be a generic system-level safety analysis tool for advanced non-LWRs, including Liquid-Metal-cooled fast Reactors (LMR), Molten Salt Reactors (MSR), Fluoride-salt-cooled Hightemperature Reactors (FHR), and High-Temperature Gas-cooled Reactors (HTGR). SAM takes advantage of advances in physical modeling, numerical methods, and software engineering to enhance its user experience and usability. It utilizes an object-oriented computational framework (MOOSE), and its underlying meshing and finite-element library and linear and non-linear solvers, to leverage the modern advanced software environments and numerical methods.This document provides the theoretical and technical basis of the code to help users understand the underlying physical models (such as governing equations, closure models, and component models), system modeling approaches, numerical discretization and solution methods, and the overall capabilities in SAM. As new code capabilities and features are added, the SAM Theory Manual will be updated periodically to keep it consistent with the state of the development.

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“…The bubble radius can be simply calculated as a function of the total number of fissions, 15) where k B is the Boltzmann constant, T is the temperature (K), γ = 0.8 is the surface tension of the fuel (J/m 2 ) [25], Y gas = 0.3017 is the gaseous fission product yield,Ḟ is the fission rate density, t is time, and N is the number density of bubbles (bubbles/m 3 ). Given the radius, the total eigenstrain can be calculated as,…”

Section: Fuel Volumetric Swelling Modelmentioning

confidence: 99%