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

Vu, Thanh Mai; Hartanto, Donny; Chu, Thoi Nam; Pham, Nhu Viet Ha; Bui, Thi Hong

doi:10.1016/j.anucene.2021.108912

Cited by 4 publications

(1 citation statement)

References 9 publications

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“…Interest in them is due to the fact that the most studied nuclear fuels are UO 2 and PuO 2 oxide fuel, as well as their physicochemical, structural and mechanical properties and small sections of thermal neutron capture. Among the variety of oxide ceramics, great interest is shown in zirconium dioxide (ZrO 2 ), the distinctive features of which are high chemical stability, mechanical and strength properties, as well as high compatibility, both with heat carriers and materials of fuel element shells [16,17]. However, despite the great prospects for the use of ZrO 2 ceramics, there is one significant drawback, which lies in polymorphic phase transformations resulting both from elevated temperatures and from irradiation [18,19].…”

Section: Introductionmentioning

confidence: 99%

Research of Structural, Strength and Thermal Properties of ZrO2—CeO2 Ceramics Doped with Yttrium

et al. 2022

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In this work, using a mechanochemical solid-phase synthesis method, ZrO2—CeO2 ceramics doped with yttrium were obtained, which have great prospects for use as a basis for dispersed nuclear fuel materials or inert nuclear fuel matrices. The purpose of this work was to study the formation of the ZrO2—CeO2 phase composition, depending on the concentration of yttrium dopant, as well as to study their structural and strength properties. The relevance of this study is in obtaining new data on the properties of composite ceramics based on oxides having a cermet structure, as well as the effect of doping with yttrium on increasing the resistance of ceramics to deformation and thermal properties. During the studies, the dynamics of the phase transformations depending on the concentration of the dopant, as well as changes in the structural characteristics and dislocation density, were established. It was found that at a dopant concentration of 0.25 mol, the main phase in the structure was Ce3ZrO8–triclinic P1 (1), the formation of which led to an increase in the mechanical and strength properties of the ceramics as well as a 1.5-fold increase in the thermal conductivity coefficient.

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Section: Introductionmentioning

confidence: 99%

Research of Structural, Strength and Thermal Properties of ZrO2—CeO2 Ceramics Doped with Yttrium

et al. 2022

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Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

Pinem,

Hong,

Luthfi

et al. 2024

Nuclear Science and Engineering

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Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

Vu,

Tran,

Bui

et al. 2024

Journal of Nuclear Engineering and Radiation Science

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A small modular lead-cooled fast spectrum core concept called ALMANAR designed to produce 45 MWth power for 22 years operating without refuelling was proposed in a previous study. The neutronics investigation showed its excellent inherent safety features. It could be considered as a candidate for future electricity source for the near future. It is noteworthy that the target accuracy for eigenvalue calculation for keff regardless of spectrum is set to 300 pcm. However, findings in this analysis revealed that the keff uncertainty was larger for the recently released nuclear data libraries (about 800 pcm), mostly from 235U capture cross section (624 pcm) in the case of ENDF/B-VIII.0 and 238U inelastic scattering cross section (437 pcm) in the case of JENDL-5. Selected kinetic parameters of the ALMANAR core and their uncertainty were also evaluated and analysed. No major impact on the total ßeff, leffeff and λeff simulation results was found. In order to improve the reliability of criticality calculations of the lead-cooled small fast reactor, the accuracy of capture and fission cross section of 235,238U, the capture cross section of 10B and the elastic scattering cross section of 208Pb at the fast energy range of ENDF/B-VIII.0 should be improved. Furthermore, the inelastic scattering and capture cross section of 238U, fission and capture cross section of 235U and the capture cross section of 10B of JENDL-5 should also be improved.

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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

Cited by 4 publications

References 9 publications

Research of Structural, Strength and Thermal Properties of ZrO2—CeO2 Ceramics Doped with Yttrium

Research of Structural, Strength and Thermal Properties of ZrO2—CeO2 Ceramics Doped with Yttrium

Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

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