Neutronics study on small power ADS loaded with recycled inert matrix fuel for transuranic elements transmutation using Serpent code

Vu, Thanh Mai; Hartanto, Donny; Ha, Pham Nhu Viet

doi:10.1016/j.net.2021.01.004

Cited by 5 publications

(3 citation statements)

References 9 publications

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“…There are two highly preferred heterogeneous forms [ 3 , 5 , 6 ]: CERCER, which is strengthened with ceramic particles in a

metallic matrix, and CERMET, which is reinforced with the same inclusions in a MgO matrix. In previous research by the Experimental Feasibility of Targets for Transmutation (EFTTRA) group [ 4 , 7 , 8 ], uranium dioxide (

) was consistently used as the particle material in CERCER targets, while MgO was an appropriate matrix choice thanks to its irradiation stability [ 9 , 10 ].…”

Section: Introductionmentioning

confidence: 99%

Toward Elucidating the Influence of Hydrostatic Pressure Dependent Swelling Behavior in the CERCER Composite

2023

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A ceramic–ceramic (CERCER) fuel with minor actinide-enriched ceramic fuel particles dispersed in a MgO ceramic matrix is chosen as a promising composite target for accelerator-driven systems (ADS). Fission swelling is a complex irradiation-induced phenomenon that involves recrystallization, resolution, and hydrostatic pressure under extreme conditions of high temperature and significant fission flux. In this study, a multiscale computational framework was developed to integrate simulations of continuum-scale thermo-mechanical behavior in the CERCER composite with a grain-scale hydrostatic pressure-dependent fission gas swelling model. Hydrostatic pressure-dependent fission welling is taken into account in the stress update algorithms for UO2 particles. Accordingly, we programmed the user subroutines to define the thermo-mechanical constitutive relations in the finite element simulations. The obtained results indicate that (1) the proposed method accurately predicts the swelling deformation at various burnup levels while taking into account hydrostatic pressure and (2) prior to recrystallization, the particle swelling is primarily influenced by temperature variation, whereas after recrystallization, the presence of hydrostatic pressure favorably suppresses the swelling deformation. This work effectively captures the swelling behavior influenced by hydrostatic pressure within the dispersed-type CERCER composite fuel in ADSs.

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“…There are two highly preferred heterogeneous forms [ 3 , 5 , 6 ]: CERCER, which is strengthened with ceramic particles in a

) was consistently used as the particle material in CERCER targets, while MgO was an appropriate matrix choice thanks to its irradiation stability [ 9 , 10 ].…”

Section: Introductionmentioning

confidence: 99%

Toward Elucidating the Influence of Hydrostatic Pressure Dependent Swelling Behavior in the CERCER Composite

2023

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“…The accelerator driven system (ADS) 9 and solid fuel critical fast reactors (sodium cooled fast reactor (SFR), 10 lead cooled fast reactor (LFR), 11 gas cooled fast reactor (GFR), 12 etc.) are two main transmutation approaches.…”

Section: Introductionmentioning

confidence: 99%

“…However, because nuclide fission has an energy spectrum threshold for majority of actinides, a hard/fast neutron spectrum is required during the design of a transmutation system to boost the fission capture ratio of TRUs and improve the transmutation capabilities. 8 The accelerator driven system (ADS) 9 and solid fuel critical fast reactors (sodium cooled fast reactor (SFR), 10 lead cooled fast reactor (LFR), 11 gas cooled fast reactor (GFR), 12 etc.) are two main transmutation approaches.…”

Section: Introductionmentioning

confidence: 99%

Potential of transuranics transmutation in a thorium‐based chloride salt fast reactor

Cui

et al. 2022

Intl J of Energy Research

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A thorium-based chloride salt fast reactor (TCLFR) for transuranics (TRUs) transmutation is proposed to decrease radioactive nuclear waste. The TCLFR core uses two types of fuel: liquid nuclear fuel with TRUs and thorium being dissolved in chloride and solid transmutation rod with only TRUs fuel. The transmutation capability of TCLFR with a core power of 2500 MWth is investigated utilizing three different reactor core configurations, namely ThCore, GdCore, and TcCore, and compared to the standard Molten Chloride Fast Reactor (MCFR) while maintaining most of the geometric parameters. Important burnup parameters such as transmutation rate (TRE) and transmutation ratio (TRO) are extracted and analyzed. Besides, the neutron spectrum shift and the relevant safety parameters, including power peak factor, temperature coefficient of reactivity (TCR) and effective delayed neutron fraction (β eff ) are all explored. The results demonstrate that all the TCLFR cores can transmute TRUs effectively. TRUs have a high online refueling amount of TRUs in TcCore and GdCore due to their low conversion ratio (CR). The TRE in the TcCore and GdCore is 292.77 kg/GWth/year and 258.31 kg/GWth/year, respectively, which is significantly higher than the TRE in the MCFR, which is 171.21 kg/GWth/year. As a result of the production of U-233 compensates for the consumption of TRUs, the refueling amount of TRUs decreases, and the TRE in the ThCore is only 96.29 kg/GWth/year, which is approximately 44% lower than that in the MCFR.

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Sensitivity and uncertainty analysis of neutronic and kinetic parameters for CERCER and CERMET fueled ADS using SERPENT 2 and ENDF/B-VIII.0

Hartanto

Chu

et al. 2022

Annals of Nuclear Energy

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Neutronics study on small power ADS loaded with recycled inert matrix fuel for transuranic elements transmutation using Serpent code

Cited by 5 publications

References 9 publications

Toward Elucidating the Influence of Hydrostatic Pressure Dependent Swelling Behavior in the CERCER Composite

Toward Elucidating the Influence of Hydrostatic Pressure Dependent Swelling Behavior in the CERCER Composite

Potential of transuranics transmutation in a thorium‐based chloride salt fast reactor

Sensitivity and uncertainty analysis of neutronic and kinetic parameters for CERCER and CERMET fueled ADS using SERPENT 2 and ENDF/B-VIII.0

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