Reference health
Chromia-Doped Uo2 Fuel: An Engineering Model for Chromium Solubility and Fission Gas Diffusivity
37/37 checkable references clean · checked 2026-09-15
Every reference with a DOI in the deposited reference list resolved to a known work in Crossref or DataCite at the dated check, and none carried a retraction, withdrawal, or removal notice.
14 without a DOI — not checked. A reference deposited without a DOI is never matched by title or guessed at; it stays outside the checked set, and this line discloses that.
The 37 checked references that resolve
resolves10.1016/j.jnucmat.2023.154536
Simulation of radioactive fission gas release from defective PWR fuel rod using the MFPR/R mechanistic code
resolves10.1016/j.jnucmat.2016.08.010
Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels
resolves10.1016/j.jnucmat.2017.01.053
A semi-empirical model for the formation and depletion of the high burnup structure in UO2
resolves10.1016/S0022-3115(97)00356-5
Effect of additives (Cr2O3, Al2O3, SiO2, MgO) on diffusional release of from UO2 fuels
resolves10.1016/j.jnucmat.2021.153053
An evaluation of tri-valent oxide (Cr2O3) as a grain enlarging dopant for UO2 nuclear fuels fabricated under reducing environment
resolves10.1016/S0022-3115(01)00626-2
Factors governing microstructure development of Cr2O3-doped UO2 during sintering
resolves10.1016/j.jnucmat.2023.154250
Enrichment of Chromium at Grain Boundaries in Chromia Doped UO2
resolves10.1016/j.jnucmat.2016.07.056
Experimental evidence of oxygen thermo-migration in PWR UO2 fuels during power ramps using in-situ oxido-reduction indicators
resolves10.1016/j.jnucmat.2020.152140
Oxygen potential calculations for conventional and Cr-doped UO2 fuels based on solid solution thermodynamics
resolves10.1038/s41467-023-38109-0
Deconvoluting Cr states in Cr-doped UO2 nuclear fuels via bulk and single crystal spectroscopic studies
resolves10.1016/j.jnucmat.2020.152042
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes
resolves10.1016/j.anucene.2023.109891
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F
resolves10.1016/j.jnucmat.2011.06.042
A model for evolution of oxygen potential and stoichiometry deviation in irradiated UO2 fuel
resolves10.1016/j.jnucmat.2007.01.081
Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating
resolves10.1016/j.jnucmat.2020.152590
Fission gas diffusion and release for Cr
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O
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-doped UO
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: From the atomic to the engineering scale
resolves10.1016/j.jnucmat.2018.07.030
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution
resolves10.13182/NSE69-A20676
A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation
resolves10.1016/j.nucengdes.2012.12.002
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis
resolves10.1016/0022-3115(82)90419-6
The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide
resolves10.1016/j.jnucmat.2014.09.077
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling
resolves10.1016/j.jnucmat.2012.11.053
An experimental study of grain growth in mixed oxide samples with various microstructures and plutonium concentrations
resolves10.1016/j.nucengdes.2018.07.015
Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code
resolves10.1016/S0029-5493(00)00295-8
Calculation method for diffusional gas release with grain boundary resolution
resolves10.1016/j.jnucmat.2018.02.024
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools
resolves10.1016/j.jnucmat.2016.10.051
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS
The 14 references without a DOI — listed, not checked
no DOI — not checkedref1
no DOI — not checkedref2
no DOI — not checkedref11
no DOI — not checkedAdvanced fuel pellet materials and designs for water cooled reactors
no DOI — not checkedThermodynamic Reassessment of the Cr-O System in the Framework of Solid Oxide Fuel Cell (SOFC) Research
no DOI — not checkedFission Gas Behavior during Postirradiation Annealing of Large Grained UO 2 Fuels Irradiated to 23 GWd/t
no DOI — not checkedref33
no DOI — not checkedref34
no DOI — not checkedref36
no DOI — not checkedref39
no DOI — not checkedref41
no DOI — not checkedref44
no DOI — not checkedref45
no DOI — not checkedref50
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