Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions

Date

2017-04-01

Author

Aydoğan Güngör, Eda
Gigax, J. G.
Chen, D.
Wang, X.
Dzhumaev, P. S.
Emelyanova, O. V.
Ganchenkova, M. G.
Kalin, B. A.
Leontiva-Smirnova, M.
Valiev, R. Z.
Enikeev, N. A.
Abramova, M. M.
Wu, Y.
Lo, W. V.
Yang, Y.
Short, M.
Maloy, S. A.
Garner, F. A.
Shao, L.

Metadata

Show full item record

This work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.

Item Usage Stats

137
views

0
downloads

EK-181 is a low-activation ferriticimartensitic steel that is an attractive candidate for in-core component materials for both fast reactors and fusion reactors. To assess the effect of microstructural engineering on radiation response, two variants of EK-181 were studied: one in an annealed condition and the other subject to severe plastic deformation. These specimens were irradiated with 3.5 MeV Fe self-ions up to 400 peak displacements per atom (dpa) at temperatures ranging from 400 degrees C to 500 degrees C. The deformation did not suppress swelling over the whole irradiated region. Instead, deformed samples showed higher swelling in the near-surface region. Void swelling was found to be correlated with grain boundary instability. Significant grain growth occurred when steady-state void growth started. (C) 2017 Elsevier B.V. All rights reserved.

Subject Keywords

Nuclear and High Energy Physics, General Materials Science, Nuclear Energy and Engineering

URI

https://hdl.handle.net/11511/69890

Journal

JOURNAL OF NUCLEAR MATERIALS

DOI

https://doi.org/10.1016/j.jnucmat.2017.02.006

Collections

Department of Metallurgical and Materials Engineering, Article

Suggestions

OpenMETU
Core

Effect of High-Density Nanoparticles on Recrystallization and Texture Evolution in Ferritic Alloys Aydoğan Güngör, Eda; Carvajal-Nunez, Ursula; Vogel, Sven C.; Li, Meimei; Maloy, Stuart A. (MDPI AG, 2019-03-01) Ferritic alloys are important for nuclear reactor applications due to their microstructural stability, corrosion resistance, and favorable mechanical properties. Nanostructured ferritic alloys having a high density of Y-Ti-O rich nano-oxides (NOs < 5 nm) are found to be extremely stable at high temperatures up to similar to 1100 degrees C. This study serves to understand the effect of a high density of nano-particles on texture evolution and recrystallization mechanisms in ferritic alloys of 14YWT (14Cr-3W-...
Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9 Gigax, Jonathan G.; Kim, Hyosim; Aydoğan Güngör, Eda; Price, L. M.; Wang, X.; Maloy, S. A.; Garner, F. A.; Shao, L. (Elsevier BV, 2019-04-01) Accelerator-based ion irradiation is commonly used to simulate neutron damage, in lieu of neutron irradiation due to limited availability of fast flux facilities and little to no activation of the samples. Neutron atypical effects, however, must be recognized and their impact minimized in order to achieve the most accurate microstructural evolution under ion bombardment. Mechanical property changes, which arise from the synergy of numerous radiation-induced changes, are especially susceptible to these neutr...
Nanohardness measurements of heavy ion irradiated coarse- and nanocrystalline-grained tungsten at room and high temperature El-Atwani, O.; Weaver, J. S.; Esquivel, E.; Efe, Mert; Chancey, M. R.; Wang, Y. Q.; Maloy, S. A.; Mara, N. (Elsevier BV, 2018-10-01) Heavy ion irradiation was performed on coarse and nanocrystalline-grained tungsten (CGW and NGW, respectively) at room temperature (RT) and 1050 K from 0.25 to 4 dpa to simulate radiation damage for fusion energy applications. TEM and nanohardness measurements of irradiated samples were made to quantify the radiation tolerance of these two candidate materials. In this case, TEM is used to quantify the defect morphology at low dpa values and determine the barrier strength coefficients of the different defect...
Monte Carlo calculation of the de-excitation of fission fragments of Cf-252(sf) within multimodal random neck rupture model Buyukmumcu, Z.; Kildir, M. (American Physical Society (APS), 2006-11-01) The multimodal random neck rupture model has been employed to study the energy distribution in nuclear fission. Monte Carlo calculations have been carried out on the de-excitation of fission fragments of Cf-252(sf) using this model. In this study special attention has been paid to the law of conservation of energy. Results for the neutron multiplicities and kinetic energies, average gamma energies are in good agreement with the experimental data. Mass and charge distributions of secondary fission fragments ...
Measurement of the intrinsic radiopurity of (CS)-C-137/U-235/U-238/Th-232 in CsI(Tl) crystal scintillators Zhu, YF; Lin, ST; Singh, V; Chang, WC; Deniz, M; Lai, WP; Li, HB; Li, J; Li, Y; Liao, HY; Lee, FS; Wong, HT; Wu, SC; Yue, Q; Zhou, ZY (Elsevier BV, 2006-02-15) The inorganic crystal scintillator CsI(TI) has been used for low energy neutrino and Dark Matter experiments, where the intrinsic radiopurity is an issue of major importance. Low-background data were taken with a Csl(TI) crystal array at the Kuo-Sheng Reactor Neutrino Laboratory. The pulse shape discrimination capabilities of the crystal, as well as the temporal and spatial correlations of the events, provide powerful means of measuring the intrinsic radiopurity of Cs-137 as well as the U-215, U-238 and Th-...

Citation Formats

E. Aydoğan Güngör et al., “Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions,” JOURNAL OF NUCLEAR MATERIALS, pp. 96–104, 2017, Accessed: 00, 2021. [Online]. Available: https://hdl.handle.net/11511/69890.