Application of the BISON Fuel Performance Code to the FUMEX-III Coordinated Research Project

Williamson, R.L.; Novascone, Stephen

doi:10.2172/1046062

Cited by 2 publications

(2 citation statements)

References 11 publications

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“…Relevant physical models such as thermal expansion, creep, swelling, and FGR have been implemented in BISON for a variety of fuels and claddings [17]. The validation of BISON has been addressed in several published manuscripts, which demonstrated its good predictive capabilities [19][20][21].…”

Section: Bison Fission Gas Release Modelmentioning

confidence: 99%

Evaluation of BISON's Transient Fission Gas Release Model on High-Burnup UO<sub>2</sub> MiniFuel

Cheniour,

Capps,

Pastore

2021

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BISON's fission gas release (FGR) model was evaluated and tested over several hypothetical temperature transient conditions at high burnup and validated against FGR experimental data from an annealing test on high-burnup fuel. Diffusioncontrolled FGR is accounted for in the model by including several physical mechanisms such as the diffusion of fission gas to grain faces, grain boundary sweeping, grain growth, and intergranular bubble growth. Under temperature variations, the development of microcracks at grain faces increases FGR. Nevertheless, a fraction of the FGR during temperature transients such as loss-ofcoolant accident (LOCA) can be a result of different mechanisms (in particular, fuel fragmentation) and present an important dependency on local burnup and high burnup structure formation. This report documents a systematic study conducted to investigate the performance and necessary developments of the existing BISON fission gas release model for the analysis of LOCA-type transients. The model is applied to a UO2 Miniature Fuel (MiniFuel) example and shows an overall good qualitative agreement with experimental observations on FGR during annealing tests under different temperature conditions. It also accounts well for microstructural effects on FGR. When quantitatively compared with FGR data from previously irradiated 103 MWd/kgU UO2 discs under thermal annealing, the model shows a less satisfactory agreement with the experimental data. Finally, a UO2 MiniFuel test matrix is proposed to help to improve and validate the current FGR model in BISON.

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Section: Bison Fission Gas Release Modelmentioning

confidence: 99%

Evaluation of BISON's Transient Fission Gas Release Model on High-Burnup UO<sub>2</sub> MiniFuel

Cheniour,

Capps,

Pastore

2021

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“…Numerical simulations provide an effective method for performance analyses of nuclear materials in extreme environments. Bison, a three-dimensional finite element analysis program developed by the National Laboratory of Idaho, USA, has been used to simulate the thermal mechanical behavior of fuel rods in the reactor [7]. Alcyone, a three-dimensional finite element analysis program developed by the CEA of France, has been used to study the high burnup performance of fuel [8].…”

Section: Introductionmentioning

confidence: 99%

Coupled Thermomechanical Responses of Zirconium Alloy System Claddings under Neutron Irradiation

et al. 2021

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Zirconium (Zr) alloy is a promising fuel cladding material used widely in nuclear reactors. Usually, it is in service for a long time under the effects of neutron radiation with high temperature and high pressure, which results in thermomechanical coupling behavior during the service process. Focusing on the UO2/Zr fuel elements, the macroscopic thermomechanical coupling responses of pure Zr, Zr-Sn, and Zr-Nb binary system alloys, as well as Zr-Sn-Nb ternary system alloy as cladding materials, were studied under neutron irradiation. As a heat source, the thermal conductivity and thermal expansion coefficient models of the UO2 core were established, and an irradiation growth model of a pure Zr and Zr alloy multisystem was built. Based on the user material subroutine (UMAT) with ABAQUS, the current theoretical model was implemented into the finite element framework, and the consequent thermomechanical coupling behavior under irradiation was calculated. The distribution of temperature, the stress field of the fuel cladding, and their evolution over time were analyzed. It was found that the stress and displacement of the cladding were sensitive to alloying elements due to irradiated growth.

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Application of the BISON Fuel Performance Code to the FUMEX-III Coordinated Research Project

Cited by 2 publications

References 11 publications

Evaluation of BISON's Transient Fission Gas Release Model on High-Burnup UO<sub>2</sub> MiniFuel

Evaluation of BISON's Transient Fission Gas Release Model on High-Burnup UO<sub>2</sub> MiniFuel

Coupled Thermomechanical Responses of Zirconium Alloy System Claddings under Neutron Irradiation

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