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Title: Tritium retention in reduced-activation ferritic/martensitic steels

Abstract

Reduced-activation ferritic/martensitic (RAFM) steels are structural material candidates for breeding blankets of future fusion reactors. Therefore, tritium (T) retention in RAFM steels is an important problem in assessing the T inventory of blankets. In this study, specimens of RAFM steels were subjected to irradiation of 20 MeV W ions to 0.54 displacements per atom (dpa), exposure to high flux D plasmas at 400 and 600 K and that to pulsed heat loads. The specimens thus prepared were exposed to DT gas at 473 K. Despite severe modification in the surface morphology, heat loads had negligible effects on T retention. Significant increase in T retention at the surface and/or subsurface was observed after D plasma exposure. However, T trapped at the surface/subsurface layer was easily removed by maintaining the specimens in the air at about 300 K. Displacement damage led to increase in T retention in the bulk due to the trapping effects of defects, and T trapped was stable at 300 K. It was therefore concluded that displacement damages had the largest influence on T retention under the present conditions.

Authors:
; ;  [1];  [1];  [2]; ; ; ; ;  [3];  [4];  [5];  [6]; ;  [7]
  1. University of Toyama, Toyama (Japan)
  2. (Germany)
  3. NRC Kurchatov Institute, Moscow (Russian Federation)
  4. Max-Planck-Insitut fuer Plasmaphysik, EURATOM Assciation, Garching (Germany)
  5. SRC RF TRINITI, Troitsk (Russian Federation)
  6. JSC, A.A. Bochvar High-Technology Research Institute of Inorganic Materials, Moscow (Russian Federation)
  7. Japan Atomic Energy Agency, Rokkasho-mura, Aomori (Japan)
Publication Date:
OSTI Identifier:
22429717
Resource Type:
Journal Article
Resource Relation:
Journal Name: Fusion Science and Technology; Journal Volume: 67; Journal Issue: 2; Conference: TRITIUM 2013: 10. International Conference on Tritium Science and Technology, Nice Acropolis (France), 21-25 Oct 2013; Other Information: Country of input: France; 12 refs.
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 36 MATERIALS SCIENCE; ATOMIC DISPLACEMENTS; BREEDING BLANKETS; DEUTERIUM; FERRITIC STEELS; MARTENSITIC STEELS; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTORS; TRITIUM; TUNGSTEN IONS

Citation Formats

Hatano, Y., Abe, S., Matsuyama, M., Alimov, V.K., Max-Planck-Insitut fuer Plasmaphysik, EURATOM Association, Garching, Spitsyn, A.V., Bobyr, N.P., Cherkez, D.I., Khripunov, B.I., Golubeva, A.V., Ogorodnikova, O.V., Klimov, N.S., Chernov, V.M., Oyaidzu, M., and Yamanishi, T. Tritium retention in reduced-activation ferritic/martensitic steels. United States: N. p., 2015. Web. doi:10.13182/FST14-T30.
Hatano, Y., Abe, S., Matsuyama, M., Alimov, V.K., Max-Planck-Insitut fuer Plasmaphysik, EURATOM Association, Garching, Spitsyn, A.V., Bobyr, N.P., Cherkez, D.I., Khripunov, B.I., Golubeva, A.V., Ogorodnikova, O.V., Klimov, N.S., Chernov, V.M., Oyaidzu, M., & Yamanishi, T. Tritium retention in reduced-activation ferritic/martensitic steels. United States. doi:10.13182/FST14-T30.
Hatano, Y., Abe, S., Matsuyama, M., Alimov, V.K., Max-Planck-Insitut fuer Plasmaphysik, EURATOM Association, Garching, Spitsyn, A.V., Bobyr, N.P., Cherkez, D.I., Khripunov, B.I., Golubeva, A.V., Ogorodnikova, O.V., Klimov, N.S., Chernov, V.M., Oyaidzu, M., and Yamanishi, T. Sun . "Tritium retention in reduced-activation ferritic/martensitic steels". United States. doi:10.13182/FST14-T30.
@article{osti_22429717,
title = {Tritium retention in reduced-activation ferritic/martensitic steels},
author = {Hatano, Y. and Abe, S. and Matsuyama, M. and Alimov, V.K. and Max-Planck-Insitut fuer Plasmaphysik, EURATOM Association, Garching and Spitsyn, A.V. and Bobyr, N.P. and Cherkez, D.I. and Khripunov, B.I. and Golubeva, A.V. and Ogorodnikova, O.V. and Klimov, N.S. and Chernov, V.M. and Oyaidzu, M. and Yamanishi, T.},
abstractNote = {Reduced-activation ferritic/martensitic (RAFM) steels are structural material candidates for breeding blankets of future fusion reactors. Therefore, tritium (T) retention in RAFM steels is an important problem in assessing the T inventory of blankets. In this study, specimens of RAFM steels were subjected to irradiation of 20 MeV W ions to 0.54 displacements per atom (dpa), exposure to high flux D plasmas at 400 and 600 K and that to pulsed heat loads. The specimens thus prepared were exposed to DT gas at 473 K. Despite severe modification in the surface morphology, heat loads had negligible effects on T retention. Significant increase in T retention at the surface and/or subsurface was observed after D plasma exposure. However, T trapped at the surface/subsurface layer was easily removed by maintaining the specimens in the air at about 300 K. Displacement damage led to increase in T retention in the bulk due to the trapping effects of defects, and T trapped was stable at 300 K. It was therefore concluded that displacement damages had the largest influence on T retention under the present conditions.},
doi = {10.13182/FST14-T30},
journal = {Fusion Science and Technology},
number = 2,
volume = 67,
place = {United States},
year = {Sun Mar 15 00:00:00 EDT 2015},
month = {Sun Mar 15 00:00:00 EDT 2015}
}