Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor

S. B. Gilliam; S. M. Gidcumb; D. Forsythe; N. R. Parikh; J. D. Hunn; L. L. Snead; G. P. Lamaze

doi:10.1016/j.nimb.2005.07.060

Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor

S. B. Gilliam, S. M. Gidcumb, D. Forsythe, N. R. Parikh, J. D. Hunn, L. L. Snead, G. P. Lamaze

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Abstract

The first wall of an inertial fusion energy reactor may suffer from surface blistering and exfoliation due to helium ion fluxes and extreme temperatures. Tungsten is a candidate for the first wall material. A study of helium retention and surface blistering with regard to helium dose, temperature and tungsten microstructure was conducted to learn how the damaging effects of helium may be diminished. Single crystal and polycrystalline tungsten samples were implanted with 1.3 MeV ³He in doses ranging from 10¹⁹/m² to 10²²/m². Implanted samples were analyzed by ³He(d, p)⁴He nuclear reaction analysis and neutron depth profiling techniques. Surface blistering occurred for doses greater than 10 ²¹ He/m² and was analyzed by scanning electron microscopy. Repeated cycles of implantation and flash annealing indicated that helium retention was reduced with decreasing implant dose per cycle. A carbon foil energy degrader, currently in development, will allow a continuous spectrum of helium implantation energy matching the theoretical models of He ion fluxes within the IFE reactor. Crown

Original language	English
Pages (from-to)	491-495
Number of pages	5
Journal	Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms
Volume	241
Issue number	1-4
DOIs	https://doi.org/10.1016/j.nimb.2005.07.060
State	Published - Dec 2005

Funding

This work was supported under the US Department of Energy High Average Power Laser Program managed by the Naval Reactor Laboratory through subcontract with the Oak Ridge National Laboratory.

Keywords

Helium retention
IFE
Implantation
Tungsten

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10.1016/j.nimb.2005.07.060

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Gilliam, S. B., Gidcumb, S. M., Forsythe, D., Parikh, N. R., Hunn, J. D., Snead, L. L., & Lamaze, G. P. (2005). Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 241(1-4), 491-495. https://doi.org/10.1016/j.nimb.2005.07.060

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title = "Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor",

abstract = "The first wall of an inertial fusion energy reactor may suffer from surface blistering and exfoliation due to helium ion fluxes and extreme temperatures. Tungsten is a candidate for the first wall material. A study of helium retention and surface blistering with regard to helium dose, temperature and tungsten microstructure was conducted to learn how the damaging effects of helium may be diminished. Single crystal and polycrystalline tungsten samples were implanted with 1.3 MeV 3He in doses ranging from 1019/m2 to 1022/m2. Implanted samples were analyzed by 3He(d, p)4He nuclear reaction analysis and neutron depth profiling techniques. Surface blistering occurred for doses greater than 10 21 He/m2 and was analyzed by scanning electron microscopy. Repeated cycles of implantation and flash annealing indicated that helium retention was reduced with decreasing implant dose per cycle. A carbon foil energy degrader, currently in development, will allow a continuous spectrum of helium implantation energy matching the theoretical models of He ion fluxes within the IFE reactor. Crown",

keywords = "Helium retention, IFE, Implantation, Tungsten",

author = "Gilliam, {S. B.} and Gidcumb, {S. M.} and D. Forsythe and Parikh, {N. R.} and Hunn, {J. D.} and Snead, {L. L.} and Lamaze, {G. P.}",

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Gilliam, SB, Gidcumb, SM, Forsythe, D, Parikh, NR, Hunn, JD, Snead, LL & Lamaze, GP 2005, 'Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor', Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, vol. 241, no. 1-4, pp. 491-495. https://doi.org/10.1016/j.nimb.2005.07.060

Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor. / Gilliam, S. B.; Gidcumb, S. M.; Forsythe, D. et al.
In: Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, Vol. 241, No. 1-4, 12.2005, p. 491-495.

Research output: Contribution to journal › Article › peer-review

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AU - Gilliam, S. B.

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AU - Parikh, N. R.

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N2 - The first wall of an inertial fusion energy reactor may suffer from surface blistering and exfoliation due to helium ion fluxes and extreme temperatures. Tungsten is a candidate for the first wall material. A study of helium retention and surface blistering with regard to helium dose, temperature and tungsten microstructure was conducted to learn how the damaging effects of helium may be diminished. Single crystal and polycrystalline tungsten samples were implanted with 1.3 MeV 3He in doses ranging from 1019/m2 to 1022/m2. Implanted samples were analyzed by 3He(d, p)4He nuclear reaction analysis and neutron depth profiling techniques. Surface blistering occurred for doses greater than 10 21 He/m2 and was analyzed by scanning electron microscopy. Repeated cycles of implantation and flash annealing indicated that helium retention was reduced with decreasing implant dose per cycle. A carbon foil energy degrader, currently in development, will allow a continuous spectrum of helium implantation energy matching the theoretical models of He ion fluxes within the IFE reactor. Crown

AB - The first wall of an inertial fusion energy reactor may suffer from surface blistering and exfoliation due to helium ion fluxes and extreme temperatures. Tungsten is a candidate for the first wall material. A study of helium retention and surface blistering with regard to helium dose, temperature and tungsten microstructure was conducted to learn how the damaging effects of helium may be diminished. Single crystal and polycrystalline tungsten samples were implanted with 1.3 MeV 3He in doses ranging from 1019/m2 to 1022/m2. Implanted samples were analyzed by 3He(d, p)4He nuclear reaction analysis and neutron depth profiling techniques. Surface blistering occurred for doses greater than 10 21 He/m2 and was analyzed by scanning electron microscopy. Repeated cycles of implantation and flash annealing indicated that helium retention was reduced with decreasing implant dose per cycle. A carbon foil energy degrader, currently in development, will allow a continuous spectrum of helium implantation energy matching the theoretical models of He ion fluxes within the IFE reactor. Crown

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Gilliam SB, Gidcumb SM, Forsythe D, Parikh NR, Hunn JD, Snead LL et al. Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2005 Dec;241(1-4):491-495. doi: 10.1016/j.nimb.2005.07.060

Helium retention and surface blistering characteristics of tungsten with regard to first wall conditions in an inertial fusion energy reactor

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