Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten

Yasuhisa Oya, Masashi Shimada, Makoto Kobayashi, Takuji Oda, Masanori Hara, Hideo Watanabe, Yuji Hatano, Pattrick Calderoni, Kenji Okuno

Research output: Contribution to journalArticle

43 Citations (Scopus)

Abstract

The behavior of D retention for Fe 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 2 thermal desorption spectroscopy (TDS) spectra for Fe 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 550 K increased as the displacement damage increased due to Fe 2+ irradiation increasing. In addition, the first desorption stage at 450 K was found only for damaged samples. Therefore, the second stage would be based on intrinsic defects or vacancy produced by Fe 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 2 TDS spectra for Fe 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.

Original languageEnglish
Article number014050
JournalPhysica Scripta T
VolumeT145
DOIs
Publication statusPublished - Dec 1 2011

Fingerprint

Desorption
Neutron
deuterium
tungsten
desorption
neutrons
Vacancy
ions
Irradiation
Spectroscopy
Trapping
Damage
trapping
spectroscopy
damage
irradiation
neutron irradiation
Activation Energy
Voids
Dislocation

All Science Journal Classification (ASJC) codes

  • Atomic and Molecular Physics, and Optics
  • Mathematical Physics
  • Condensed Matter Physics
  • Physics and Astronomy(all)

Cite this

Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten. / Oya, Yasuhisa; Shimada, Masashi; Kobayashi, Makoto; Oda, Takuji; Hara, Masanori; Watanabe, Hideo; Hatano, Yuji; Calderoni, Pattrick; Okuno, Kenji.

In: Physica Scripta T, Vol. T145, 014050, 01.12.2011.

Research output: Contribution to journalArticle

Oya, Y, Shimada, M, Kobayashi, M, Oda, T, Hara, M, Watanabe, H, Hatano, Y, Calderoni, P & Okuno, K 2011, 'Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten', Physica Scripta T, vol. T145, 014050. https://doi.org/10.1088/0031-8949/2011/T145/014050
Oya, Yasuhisa ; Shimada, Masashi ; Kobayashi, Makoto ; Oda, Takuji ; Hara, Masanori ; Watanabe, Hideo ; Hatano, Yuji ; Calderoni, Pattrick ; Okuno, Kenji. / Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten. In: Physica Scripta T. 2011 ; Vol. T145.
@article{391a6d672c2a428996b9650078f74b04,
title = "Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten",
abstract = "The behavior of D retention for Fe 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 2 thermal desorption spectroscopy (TDS) spectra for Fe 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 550 K increased as the displacement damage increased due to Fe 2+ irradiation increasing. In addition, the first desorption stage at 450 K was found only for damaged samples. Therefore, the second stage would be based on intrinsic defects or vacancy produced by Fe 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 2 TDS spectra for Fe 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.",
author = "Yasuhisa Oya and Masashi Shimada and Makoto Kobayashi and Takuji Oda and Masanori Hara and Hideo Watanabe and Yuji Hatano and Pattrick Calderoni and Kenji Okuno",
year = "2011",
month = "12",
day = "1",
doi = "10.1088/0031-8949/2011/T145/014050",
language = "English",
volume = "T145",
journal = "Physica Scripta",
issn = "0031-8949",
publisher = "IOP Publishing Ltd.",

}

TY - JOUR

T1 - Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten

AU - Oya, Yasuhisa

AU - Shimada, Masashi

AU - Kobayashi, Makoto

AU - Oda, Takuji

AU - Hara, Masanori

AU - Watanabe, Hideo

AU - Hatano, Yuji

AU - Calderoni, Pattrick

AU - Okuno, Kenji

PY - 2011/12/1

Y1 - 2011/12/1

N2 - The behavior of D retention for Fe 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 2 thermal desorption spectroscopy (TDS) spectra for Fe 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 550 K increased as the displacement damage increased due to Fe 2+ irradiation increasing. In addition, the first desorption stage at 450 K was found only for damaged samples. Therefore, the second stage would be based on intrinsic defects or vacancy produced by Fe 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 2 TDS spectra for Fe 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.

AB - The behavior of D retention for Fe 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 2 thermal desorption spectroscopy (TDS) spectra for Fe 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 550 K increased as the displacement damage increased due to Fe 2+ irradiation increasing. In addition, the first desorption stage at 450 K was found only for damaged samples. Therefore, the second stage would be based on intrinsic defects or vacancy produced by Fe 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 2 TDS spectra for Fe 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.

UR - http://www.scopus.com/inward/record.url?scp=84857604242&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84857604242&partnerID=8YFLogxK

U2 - 10.1088/0031-8949/2011/T145/014050

DO - 10.1088/0031-8949/2011/T145/014050

M3 - Article

AN - SCOPUS:84857604242

VL - T145

JO - Physica Scripta

JF - Physica Scripta

SN - 0031-8949

M1 - 014050

ER -