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Comparison of Deuterium Retention for Ion-irradiated and Neutron-irradiated Tungsten

Journal Article · · Physica Scripta
OSTI ID:1035584
The behavior of D retention for Fe{sup 2+}-irradiated tungsten with a damage of 0.025-3 dpa was compared with that for neutron-irradiated tungsten with 0.025 dpa. The D{sub 2} thermal desorption spectroscopy (TDS) spectra for Fe{sup 2+}-irradiated tungsten consisted of two desorption stages at 450 and 550 K, while that for neutron-irradiated tungsten was composed of three stages and an addition desorption stage was found at 750 K. The desorption rate of the major desorption stage at 550K increased as the displacement damage increased due to Fe{sup 2+} irradiation increasing. In addition, the first desorption stage at 450K was found only for damaged samples. Therefore, the second stage would be based on intrinsic defects or vacancy produced by Fe{sup 2+} irradiation, and the first stage should be the accumulation of D in mono-vacancy and the activation energy would be relatively reduced, where the dislocation loop and vacancy is produced. The third one was found only for neutron irradiation, showing the D trapping by a void or vacancy cluster, and the diffusion effect is also contributed to by the high full-width at half-maximum of the TDS spectrum. Therefore, it can be said that the D{sub 2} TDS spectra for Fe{sup 2+}-irradiated tungsten cannot represent that for the neutron-irradiated one, indicating that the deuterium trapping and desorption mechanism for neutron-irradiated tungsten is different from that for the ion-irradiated one.
Research Organization:
Idaho National Laboratory (INL)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC07-05ID14517
OSTI ID:
1035584
Report Number(s):
INL/JOU-11-24944
Journal Information:
Physica Scripta, Journal Name: Physica Scripta Journal Issue: T145 Vol. 2011; ISSN 0031-8949; ISSN PHSTBO
Country of Publication:
United States
Language:
English

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