Fission gas diffusion and release for Cr<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si1.svg"><mml:msub><mml:mrow/><mml:mn>2</mml:mn></mml:msub></mml:math>O<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si11.svg"><mml:msub><mml:mrow/><mml:mn>3</mml:mn></mml:msub></mml:math>-doped UO<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si1.svg"><mml:msub><mml:mrow/><mml:mn>2</mml:mn></mml:msub></mml:math>: From the atomic to the engineering scale

Cooper, M.W.D.; Pastore, Giovanni; Che, Yifeng; Matthews, Christopher; Forslund, Axel; Stanek, Christopher R.; Shirvan, Koroush; Tverberg, Terje; Gamble, Kyle; Mays, Brian; Andersson, David

doi:10.1016/j.jnucmat.2020.152590

Cited by 44 publications

(12 citation statements)

References 50 publications

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“…The shape of the BISON FGR simulation is different from the measurement data. Thus, the original data have convergence problems for the MCMC (Markov Chain (Kim et al, 1996 (Notley et al, 1980;Kogai, 1997;Bernard et al, 2002;van Uffelen et al, 2002;Matsson et al, 2007;Kim et al, 2008;Viswanathan et al, 2009;Koo et al, 2010;Koo et al, 2010Koo et al, , 2019Khvostov et al, 2011;Pastore et al, 2013;Liu et al, 2015;Liu et al, 2016;Rest et al, 2019;Che et al, 2021;Cooper et al, 2021). (G-J) Fission gas release vs. time in the UO 2 fuel (Evans, 1996;Kogai, 1997;Zacharie et al, 1998;Khvostov et al, 2011;Pastore et al, 2013;Andersson et al, 2014;Wu et al, 2018;Verdolin et al, 2020).…”

Section: Single Fission Gas Behaviormentioning

confidence: 99%

“…However, within the vacancy cluster, large clusters of U and O vacancies contain the Xe atoms in a set of DFT data, and low migration barriers are exhibited by many large clusters, whose concentrations have little contribution to D 1 diffusion. The role of defect production on D 2 diffusion is considered by using DFT data for the system's free energy in a developed cluster dynamics model (Cooper et al, 2021).…”

Section: Grain Growthmentioning

confidence: 99%

“…The FGR predictions agree well with the theoretical model and experimental data, which are better than existing empirical models, and the close connection makes physical diffusion mechanisms more transferable. Cooper et al (2021) studied UO 2 mixed with Cr 2 O 3 , which increases grain size during fabrication. It is expected that FGR is reduced by large grain size as the rate-limiting intragranular diffusion step extends.…”

Section: Burnup (Mwdmentioning

confidence: 99%

See 2 more Smart Citations

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Guo¹,

Lai²,

Zhou

et al. 2022

Front. Energy Res.

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Reactor structural integrity and nuclear safety are seriously affected by the fission gas behaviors and relevant physical phenomena in nuclear fuels. In this review, the fission gas behavior and relevant phenomena in different fuels for both models and experiments have been comprehensively overviewed, including fission gas release, gap/plenum pressure, grain growth, swelling, fission gas diffusion coefficients, and fuel cladding mechanical and chemical interactions under irradiations. The fission gas behaviors can be classified into single fission gas behavior and combined fission gas behavior with more interacting physics together. In addition, fission gas behaviors are also profoundly influenced by fuel performance, which is different in different kinds of fuels. The data of different nuclear fuels are collected, for example, UO2, MOX, metallic, U3Si2, UN, UC, and TRISO fuels. The models and experiments on fission gas behaviors are summarized into figures and tables for better comparisons. The fission gas behaviors are mainly subjected to burnup, time, and temperature, which profoundly impact these behaviors. The burnup will motivate the fission gas release and other fission gas behaviors. With the fuel temperature increase, the extent of some fission gas behaviors will be more strengthened, including fission gas release, gap/plenum pressure, grain growth, swelling, and fuel cladding mechanical and chemical interactions. The predicted data are consistent with the measured data, and the modeling results generally agree well with the experimental data. In addition, the observation of enhanced gas release at high burnups is unexpected. However, the modeling approaches on fission gas release behaviors still have certain uncertainties. Therefore, it still has considerable space to be improved and is worth studying in future work.

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Section: Single Fission Gas Behaviormentioning

confidence: 99%

Section: Grain Growthmentioning

confidence: 99%

Section: Burnup (Mwdmentioning

confidence: 99%

See 1 more Smart Citation

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Guo¹,

Lai²,

Zhou

et al. 2022

Front. Energy Res.

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“…However, recent investigations have shown that the fission gas diffusivities may be higher in chromia (Cr2O3)-doped fuels as a result of changes to the fuel oxygen potential. [Cooper et al 2021] Despite these counteracting effects, chromia-doped fuel is still expected to have a delay and/or reduction in the gas release compared to UO2 with a standard grain size.…”

Section: Fuel Dopingmentioning

confidence: 99%

Extended Enrichment Accident Tolerant LWR Fuel Isotopic and Lattice Parameter Trends

Hall¹,

Sweet²,

Belles³

et al. 2021

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“…Selain densitas, ukuran butir pelet UO2 sinter termasuk persyaratan yang harus dipenuhi. Densitas dan ukuran butir digunakan sebagai salah satu indikator kemampuan pelet UO2 mengungkung hasil fisi karena proses swelling dan densifikasi lanjutan pada waktu pelet UO2 diiradiasi [5][6][7][8][9]. Fenomena di atas berpotensi menyebabkan terjadinya deformasi dan keretakan pada pelet UO2 yang akan meningkatkan probabilitas terlepasnya hasil fisi ke air pendingin reaktor bila kelongsong pecah/sobek.…”

Section: Pendahuluanunclassified

Pengaruh Distribusi Ukuran Serbuk Uo2 Pengayaan 2%–5% Pada Densitas Pelet Uo2

Mutiara

Hutapea

Dewayatna

et al. 2021

urania

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PENGARUH DISTRIBUSI UKURAN SERBUK UO2 PENGAYAAN 2%–5% PADA DENSITAS PELET UO2. Telah dilakukan studi fabrikasi pelet UO2 sinter menggunakan serbuk UO2 pengayaan 2%, 3%, 4% dan 5% untuk mendapatkan pelet UO2 dengan densitas yang memenuhi syarat sebagai bahan bakar PWR melalui proses kompaksi dan penyinteran. Sepanjang pengetahuan penulis, tidak ada publikasi penelitian tentang hubungan distribusi ukuran serbuk dengan densitas pelet UO2 pada rentang ukuran serbuk yang dipelajari pada penelitian ini. Untuk itu, melalui penelitian distribusi ukuran serbuk UO2 dan fraksi berat masing–masing rentang ukuran serbuk dan pengaruhnya terhadap densitas pelet UO2 akan diperoleh sifat mampu kompak dan mampu sinter masing–masing serbuk UO2 melalui pengukuran densitas pelet mentah dan pelet sinternya. Penelitian ini diawali dengan proses ayak serbuk UO2 umpan untuk mendapatkan data distribusi ukuran serbuk beserta fraksi beratnya, dilanjutkan dengan pengukuran densitas curah dan densitas ketuk. Masing–masing serbuk dengan distribusi ukuran dan fraksi beratnya langsung dikompaksi menjadi pelet mentah dengan variasi tekanan 2, 3 dan 4 ton/cm2, kemudian disinter pada temperatur 1700 °C selama 3 jam. Hasil pengayakan memberikan data bahwa serbuk UO2 pengayaan 2% dan 4% mempunyai distribusi ukuran serbuk monomodal sementara serbuk UO2 pengayaan 3% dan 5% dengan trimodal. Densitas pelet hasil kompaksi serbuk UO2 pengayaan 2%, 3%, 4% dan 5% pada tekanan kompaksi tertinggi berturut–turut sebesar 54,30%TD, 53,19%TD, 52,45%TD dan 52,33%TD. Densitas pelet sinter dari serbuk UO2 pengayaan 2% dan 5% masing–masing berada pada kisaran (91,13 – 91,70) %TD dan (75,33–77,57) %TD sementara pelet sinter pengayaan 3% dan 4% semuanya retak/pecah sehingga densitas tidak dapat diukur. Berdasarkan data densitas pelet disimpulkan bahwa serbuk UO2 pengayaan 2% dengan distribusi ukuran monomodal yang didominasi serbuk berukuran halus yang lebih kecil 75 µm mempunyai mampu kompak dan mampu sinter yang lebih baik dari serbuk lainnya. Penelitian ini perlu dilanjutkan untuk mengetahui lebih jauh berkaitan pemilihan distribusi ukuran serbuk UO2 umpan dengan fraksi beratnya sebagai umpan proses kompaksi dalam upaya mendapatkan pelet UO2 sinter dengan densitas lebih tinggi yang memenuhi persyaratan sebagai bahan bakar PLTN tipe PWR.Kata kunci: Pelet UO2 PWR, distribusi ukuran serbuk, densitas, kompaksi, penyinteran.

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Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale

Cited by 44 publications

References 50 publications

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Extended Enrichment Accident Tolerant LWR Fuel Isotopic and Lattice Parameter Trends

Pengaruh Distribusi Ukuran Serbuk Uo2 Pengayaan 2%–5% Pada Densitas Pelet Uo2

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