PARFUME Theory and Model basis Report

Miller, Gregory K.; Petti, David A.; Maki, John T.; Knudson, D. L.

doi:10.2172/968587

Cited by 6 publications

(2 citation statements)

References 29 publications

(194 reference statements)

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“…The main result to be highlighted from this analysis is that the residual stresses in the layers are not predicted to be negligible, as so often assumed in literature [39][40][41][42]. In fact, they may be comparable to the Fig.…”

Section: Debonding Hypothesissupporting

confidence: 58%

“…Numerical models have also been popular, especially with the recent increases in computational power available for research. Several have been developed for incorporation into finite element fuel performance codes such as BISON and PARFUME from INL [23,26,40], or ATLAS from CEA (Commissariat à l' Énergie Atomique et aux Énergies Alternatives) [23,26],. Simulations with these codes have been trying to represent many of the scenarios TRISO particles are required to withstand in a reactor, such as high neutron fluences [38,39,41], or the thermomechanical interaction of neighbouring TRISO particles inside a pebble or prismatic compact matrix [42].…”

Section: Introductionmentioning

confidence: 99%

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Residual Stresses in As-manufactured TRISO Coated Particle Fuel (CPF)

Battistini¹,

Haynes²,

Shepherd³

et al. 2023

Preprint

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TRistructural ISOtropic coated particle fuels (TRISO CPF) have been developed as a possible fuel solution for high temperature nuclear reactors, which offer the possibility of nuclear cogeneration-powered industrial facilities and hydrogen production. A finite element model was developed to simulate the fabrication process of TRISO particles. Understanding the initial stress and bonding state of the layers is crucial in predicting performance and failure in service, however this factor has not received an in depth consideration in the available literature. The simulations of a fully bonded model of TRISO (layers perfectly attached to each other) revealed the presence of high values of tensile hoop stresses in the inner fuel kernel (up to 250 MPa, sufficient to cause fracture in UO 2 ) and even higher compressive stresses (up to 600 MPa) in the silicon carbide layer. Simulations conducted without bonding between kernel and buffer found the residual stress state to be consistently more relaxed with respect to the fully bonded model. This was most evident in the radial stress, which drops to less than 10 MPa (tensile or compressive) throughout the particle. In the hoop direction, compression of 150 MPa remained in the SiC layer. Such results are consistent with the empirical evidence of the occurrence of kernelbuffer debonding during the fabrication of TRISO particles. Finally, a brief investigation of the effect of ovality on the model with kernel-buffer debonding showed an overall increase in the magnitude of the hoop stress in the SiC and PyC layers in a flat spot caused by reduced buffer material.

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Section: Debonding Hypothesissupporting

confidence: 58%

Section: Introductionmentioning

confidence: 99%

Residual Stresses in As-manufactured TRISO Coated Particle Fuel (CPF)

Battistini¹,

Haynes²,

Shepherd³

et al. 2023

Preprint

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show abstract

Comparison of silver, cesium, and strontium release predictions using PARFUME with results from the AGR-1 irradiation experiment

Collin

Petti

Demkowicz

et al. 2015

Journal of Nuclear Materials

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The PARFUME (PARticle FUel ModEl) code was used to predict the release of fission products silver, cesium, and strontium from tristructural isotropic coated fuel particles and compacts during the first irradiation experiment (AGR-1) of the Advanced Gas Reactor Fuel Development and Qualification program. The PARFUME model for the AGR-1 experiment used the fuel compact volume average temperature for each of the 620 days of irradiation to calculate the release of silver, cesium, and strontium from a representative particle for a select number of AGR-1 compacts. Post-irradiation examination measurements provided data on release of these fission products from fuel compacts and fuel particles, and retention of silver in the compacts outside of the silicon carbide (SiC) layer. PARFUME-predicted fractional release of silver, cesium, and strontium was determined and compared to the PIE measurements. For silver, comparisons show a trend of over-prediction at low burnup and under-prediction at high burnup. PARFUME has limitations in the modeling of the temporal and spatial distributions of the temperature and burnup across the compacts, which affects the accuracy of its predictions. Nevertheless, the comparisons on silver release lie in the same order of magnitude. Results show an overall over-prediction of the fractional release of cesium by PARFUME. For particles with failed SiC layers, the over-prediction is by a factor of up to 3, corresponding to a potential over-estimation of the diffusivity in uranium oxycarbide (UCO) by a factor of up to 250. For intact particles, whose release is much lower, the over-prediction is by a factor of up to 100, which could be attributed to an overestimated diffusivity in SiC by about 40% on average. The release of strontium from intact particles is also over-predicted by PARFUME, which also points towards an overestimated diffusivity of strontium in either SiC or UCO, or possibly both. The measured strontium fractional release from intact particles varied considerably from compact to compact, making it difficult to assess the effective over-estimation of the diffusivities. Furthermore, the release of strontium from particles with failed SiC is difficult to observe experimentally due to the release from intact particles, preventing any conclusions to be made on the accuracy or validity of the PARFUME predictions and the modeled diffusivity of strontium in UCO.

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AGR-1 Safety Test Predictions using the PARFUME code

Collin¹

2012

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The PARFUME modeling code was used to predict failure probability of TRISO-coated fuel particles and diffusion of fission products through these particles during safety tests following the first irradiation test (AGR-1) of the Advanced Gas Reactor program.These calculations support AGR-1 Safety Testing, which is part of the post-irradiation examination effort on AGR-1. Modeling of the AGR-1 Safety Test Predictions includes 620 days of irradiation followed by 300 hours of safety testing for selected AGR-1 compacts. Results include fuel failure probability, palladium penetration, and fractional release of fission products.

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PARFUME Theory and Model basis Report

Cited by 6 publications

References 29 publications

Residual Stresses in As-manufactured TRISO Coated Particle Fuel (CPF)

Residual Stresses in As-manufactured TRISO Coated Particle Fuel (CPF)

Comparison of silver, cesium, and strontium release predictions using PARFUME with results from the AGR-1 irradiation experiment

AGR-1 Safety Test Predictions using the PARFUME code

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