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Title: Deuterium Depth Profile in Neutron-Irradiated Tungsten Exposed to Plasma

Abstract

The effect of radiation damage has been mainly simulated using high-energy ion bombardment. The ions, however, are limited in range to only a few microns into the surface. Hence, some uncertainty remains about the increase of trapping at radiation damage produced by 14 MeV fusion neutrons, which penetrate much farther into the bulk material. With the Japan-US joint research project: Tritium, Irradiations, and Thermofluids for America and Nippon (TITAN), the tungsten samples (99.99 % pure from A.L.M.T., 6mm in diameter, 0.2mm in thickness) were irradiated to high flux neutrons at 50 C and to 0.025 dpa in the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL). Subsequently, the neutron-irradiated tungsten samples were exposed to a high-flux deuterium plasma (ion flux: 1021-1022 m-2s-1, ion fluence: 1025-1026 m-2) in the Tritium Plasma Experiment (TPE) at the Idaho National Laboratory (INL). First results of deuterium retention in neutron-irradiated tungsten exposed in TPE have been reported previously. This paper presents the latest results in our on-going work of deuterium depth profiling in neutron-irradiated tungsten via nuclear reaction analysis. The experimental data is compared with the result from non neutron-irradiated tungsten, and is analyzed with the Tritium Migration Analysis Program (TMAP)more » to elucidate the hydrogen isotope behavior such as retention and depth distribution in neutron-irradiated and non neutron-irradiated tungsten.« less

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - SC
OSTI Identifier:
1027892
Report Number(s):
INL/CON-10-20601
Journal ID: ISSN 0031--8949; TRN: US1105293
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Journal Volume: T145; Conference: 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications,Rosenheim, Germany,05/09/2011,05/13/2011
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DEPTH; DEUTERIUM; HFIR REACTOR; HYDROGEN ISOTOPES; NEUTRONS; NUCLEAR REACTION ANALYSIS; ORNL; PLASMA; RADIATIONS; RETENTION; SPATIAL DISTRIBUTION; THICKNESS; TRAPPING; TRITIUM; TUNGSTEN; deuterium retention; neutron-irradiated tungsten

Citation Formats

Masashi Shimada, G. Cao, Y. Hatano, T. Oda, Y. Oya, M. Hara, and P. Calderoni. Deuterium Depth Profile in Neutron-Irradiated Tungsten Exposed to Plasma. United States: N. p., 2011. Web. doi:10.1088/0031-8949/2011/T145/014051.
Masashi Shimada, G. Cao, Y. Hatano, T. Oda, Y. Oya, M. Hara, & P. Calderoni. Deuterium Depth Profile in Neutron-Irradiated Tungsten Exposed to Plasma. United States. doi:10.1088/0031-8949/2011/T145/014051.
Masashi Shimada, G. Cao, Y. Hatano, T. Oda, Y. Oya, M. Hara, and P. Calderoni. Sun . "Deuterium Depth Profile in Neutron-Irradiated Tungsten Exposed to Plasma". United States. doi:10.1088/0031-8949/2011/T145/014051. https://www.osti.gov/servlets/purl/1027892.
@article{osti_1027892,
title = {Deuterium Depth Profile in Neutron-Irradiated Tungsten Exposed to Plasma},
author = {Masashi Shimada and G. Cao and Y. Hatano and T. Oda and Y. Oya and M. Hara and P. Calderoni},
abstractNote = {The effect of radiation damage has been mainly simulated using high-energy ion bombardment. The ions, however, are limited in range to only a few microns into the surface. Hence, some uncertainty remains about the increase of trapping at radiation damage produced by 14 MeV fusion neutrons, which penetrate much farther into the bulk material. With the Japan-US joint research project: Tritium, Irradiations, and Thermofluids for America and Nippon (TITAN), the tungsten samples (99.99 % pure from A.L.M.T., 6mm in diameter, 0.2mm in thickness) were irradiated to high flux neutrons at 50 C and to 0.025 dpa in the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL). Subsequently, the neutron-irradiated tungsten samples were exposed to a high-flux deuterium plasma (ion flux: 1021-1022 m-2s-1, ion fluence: 1025-1026 m-2) in the Tritium Plasma Experiment (TPE) at the Idaho National Laboratory (INL). First results of deuterium retention in neutron-irradiated tungsten exposed in TPE have been reported previously. This paper presents the latest results in our on-going work of deuterium depth profiling in neutron-irradiated tungsten via nuclear reaction analysis. The experimental data is compared with the result from non neutron-irradiated tungsten, and is analyzed with the Tritium Migration Analysis Program (TMAP) to elucidate the hydrogen isotope behavior such as retention and depth distribution in neutron-irradiated and non neutron-irradiated tungsten.},
doi = {10.1088/0031-8949/2011/T145/014051},
journal = {},
issn = {0031--8949},
number = ,
volume = T145,
place = {United States},
year = {2011},
month = {5}
}

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