☆ 4.7 Article

Determination of the residual stress tensor in textured zirconium alloy by neutron diffraction

JOURNAL OF NUCLEAR MATERIALS (2012)

期刊

JOURNAL OF NUCLEAR MATERIALS

卷 421, 期 1-3, 页码 64-72

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ELSEVIER

DOI: 10.1016/j.jnucmat.2011.11.053

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Materials Science, Multidisciplinary Nuclear Science & Technology

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JINR
ISTC [3074.2]

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Results of neutron diffraction studies of crystallographic texture and residual stress tensor components in cold-worked and annealed cylindrical components made from E-110 zirconium alloy are presented. Those components are used as plugs in the fuel elements of the VVER-type reactors; the resident residual stresses influence the durability and safety of the fuel elements. The experiments were carried out on the neutron diffractometers at Dubna (the IBR-2 pulsed reactor) and Berlin Helmholtz-Zentrum (the BER II research reactor). It is shown that the samples have fiber texture that is changed considerably with annealing. The type I residual stress tensors for both samples were calculated by the BulkPathGEO model. The cold worked component has 136-166 MPa tensile residual stress in the radial direction and zero stress along the axial direction. Residual stress values in the annealed component are close to zero. (c) 2011 Elsevier B.V. All rights reserved.

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Theoretical estimation of multiple hydrogen isotope content in metal layers slowly co-deposited from plasmas

S. Krat, A. Prishvitsyn, Yu. Gasparyan

Summary: This study proposes a probabilistic and diffusion-based model to describe the co-deposition of multiple hydrogen isotopes with slowly grown metal layers. The model calculates the relative concentrations of different hydrogen isotopes in the co-deposited metal layers. It is found that if hydrogen isotopes have different detrapping energies, only the isotope with the highest detrapping energy shows a monotonic decrease in concentration with deposition temperature. Furthermore, the study evaluates the uncertainty of tritium concentration in the co-deposited layer based on the uncertainty in detrapping energy of tritium and deuterium, predicting a >10% tritium concentration uncertainty for a 0.01 eV difference.

JOURNAL OF NUCLEAR MATERIALS (2024)

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Article Materials Science, Multidisciplinary

Computational study of thermophysical properties of cerium doped UO2: Effect of oxidation states

Tijo Vazhappilly, Arup Kumar Pathak

Summary: This study investigates the effect of Ce atom substitution in UO2 on its thermophysical properties using density functional theory. The results show that the Ce substitution levels and the oxidation state of Ce/U atoms strongly influence the band structure and specific heat capacity of the UO2 lattice. These findings provide important insights into the fuel properties of UO2 under reactor conditions.

JOURNAL OF NUCLEAR MATERIALS (2024)

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