Radiation Damage Limitations in the Design of the Wisconsin Tokamak Fusion Reactor

Kulcinski, G.L.; Brown, Richard G.; Lott, RG; Sanger, P.

doi:10.13182/nt74-a16271

Cited by 38 publications

(3 citation statements)

References 15 publications

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“…The concept of a flowing, renewable liquid surface has been proposed as a potentially viable solution to this critical issue. This idea was first proposed and analysed in the early 1970s [1,2] for protecting divertor target plates and modelling studies followed [3] and continue today. The largest effort has been devoted to studies of the MHD effects associated with flowing liquid metals in magnetic fields.…”

Section: Introductionmentioning

confidence: 99%

Deuterium plasma interactions with liquid gallium

et al. 2002

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Liquid metals such as gallium, tin and lithium are potential plasma-facing materials that may be used to withstand the high heat and particle fluxes in a fusion plasma environment. The interaction of plasma with liquid gallium surfaces has been examined experimentally because of the liquid's wide temperature range (303-2478 K) and relatively low chemical reactivity. The deuterium retention in liquid gallium samples following plasma exposure in the PISCES experimental plasma device is measured using thermal desorption spectroscopy and is found to be independent of exposure temperature. The retention level saturates at a value of roughly 3 × 10 23 D m −3 (or about 5 ppm) for sample exposure temperatures ranging from 333 to 800 K and incident ion fluences up to 1.5 × 10 26 D m −2 . Results from the analyses of the surface after plasma exposure using Auger electron spectroscopy is reported. Micropitting is observed in scanning electron microscope pictures taken after plasma exposure and after resolidification of the gallium surface. Calculations based on the observed retained concentration of deuterium in gallium show that the pumping capabilities of a flowing gallium surface will be small. In addition, measurements of the erosion yield of deuterium-bombarded gallium are presented and compare favourably with results from sputtering yield calculations.

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Section: Introductionmentioning

confidence: 99%

Deuterium plasma interactions with liquid gallium

et al. 2002

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“…The energy use per person then increased again as fossil fuels became extensively used (Kulcinski 2004). The use of coal enabled the industrial revolution.…”

Section: Historical Energy Flowsmentioning

confidence: 99%

Systemic Transitions

2009

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“…Various attempts (10,(13)(14)(15)(16) have been made to use available data on type 316 stainless steel to predict the lifetime of components of this material in fusion reactor service. These show that, depending on the assumptions made, any of a number of properties can be performance or lifetime limiting.…”

Section: Implications Of Materials Property Changes Oh Fusion Reactor mentioning

confidence: 99%

Behavior of Type 316 stainless steel under simulated fusion reactor irradiation

Wiffen¹,

Maziasz²,

Bloom³

et al. 1978

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NOTrCE-Hik itport wii prepared u «n accoim of wock tponiorcd by the Uniud SlaleaGoitnunenl. Neither At United Suiei noi Die tfciiled Slatci Department of Etttiff, nor iny or thtk employees, IKX any or their contrition, ubconfraclon, or (heir employ*!, imkn uiy unrnnty, expreit or implied, or iKtimes any left! lUbililyoi teiponeibOity for IheKcuncy.compfeleMK or UKfulntn of iny inrormttion, •pDaraiui, product or proceM dkckwd, or fepretenu that lit u» would not infringe privately owned ri|[t1l. ABSTRACT Fusion reactor irradiation response in alloys containing nickel can be simulated in thermal-spectrum fission reactors, where displacement damage is produced by the high-energy neutrons and helium is produced by the capture of two thermal neutrons in the reactions: 58 Ni + n -*• 59 Ni + y; S9 Ni + n -• 56 Fe + a. Examination of type 316 stainless steel specimens irradiated in HFIR has shown that swelling due to cavity formation and degradation of mechanical properties are more severe than can be predicted from fast reactor irradiations, where the helium contents produced are far too low to simulate fusion reactor service. Swelling values are greater and the temperature dependence of swelling is different than in the fast reactor case. The property change most restrictive for fusion reactor performance is the low values of ductility that result from irradiation. These results imply limitations on the operating conditions and useful lifetimes of stainless steel first-wall and high flux region structural components of fusion reactors. *0perated for the U.S.

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Radiation Damage Limitations in the Design of the Wisconsin Tokamak Fusion Reactor

Cited by 38 publications

References 15 publications

Deuterium plasma interactions with liquid gallium

Deuterium plasma interactions with liquid gallium

Systemic Transitions

Behavior of Type 316 stainless steel under simulated fusion reactor irradiation

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