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Nov 1971; 117 p
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AbstractAbstract
[en] The first wall surfaces of fusion devices will be exposed to bombardment by inert gaseous projectiles such as helium. The flux, energy and angular distribution of the helium radiation will depend not only on the type of device but also on its design parameters. For near term tokamak devices, the first wall surface phenomena caused by helium bombardment that appear to be quite important are physical sputtering and radiation blistering. Examples of these processes for a number of first wall candidate materials are discussed. While the physical sputtering phenomen is well understood, the mechanism of blister formation is still not fully understood. The various models proposed for radiation blistering of metal during helium bombardment is critically reviewed in the light of most recent experimental results
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1979; 15 p; Symposium on inert gases in metals; Harwell, UK; 8 - 11 Aug 1979; Available from NTIS., PC A02/MF A01
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AbstractAbstract
[en] The fabrication of large and heavy nuclear components like reactor pressure vessels, steam generators and pressurizers needs maximum safety and requires a high degree of know how for the planning, design and production stages, including, quality assurance. Highly skilled and experienced operators are needed for the manifold tasks involved, as well as all the necessary equipment for handling, machining, non-cutting shaping, heat treatment, welding and for a great number of destructive and non-destructive tests. (author). 9 figs
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Kaminsky, M.; Das, S.K.
Argonne National Lab., Ill. (USA)1976
Argonne National Lab., Ill. (USA)1976
AbstractAbstract
[en] The interaction of plasma radiations with the exposed surfaces of components of plasma devices and future controlled thermonuclear fusion reactors (CTR) can cause a variety of surface effects. In turn, such surface effects can cause (a) the release of plasma contaminants, and (b) the damage and erosion of the irradiated surfaces. The contamination of the plasma can have serious effects on plasma stability and on plasma temperature, and the surface erosion can seriously limit the lifetime of the irradiated components. At present, knowledge of surface erosion rates for the plasma parameters and materials envisioned in CTR applications is only fragmentary. To what extent the erosion rates will be affected by synergistic effects due to the simultaneous bombardment of surfaces by high fluxes of energetic particles of various types and by photons is almost completely unknown. A summary of some of the major surface erosion phenomena which have been identified as being important for CTR applications by using single irradiation sources (e.g., accelerators) will be given. A discussion of some potential solutions to reduce surface erosion will be included. The main features of a recently completed two component irradiation facility at ANL for CTR related surface studies will be described
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1976; 9 p; 4. annual conference on the use of small accelerators; Denton, Texas, United States of America (USA); 25 Oct 1976; Available from NTIS. $3.50.
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AbstractAbstract
No abstract available
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Journal Article
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Journal of Applied Physics; v. 44(1); p. 25-31
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AbstractAbstract
[en] Experiments were conducted to determine the surface damage of ATJ graphite, V, Cu, and Type 316 stainless steel under 60-keV D+ irradiation. The irradiations were conducted in the pulsed mode. For a total accumulated dose of 8.1 x 1018 ions/cm2, blisters were readily seen for Cu surfaces, but no blisters were observed on Type 316 stainless steel and vanadium surfaces. For the case of ATJ graphite, the surface damage was observed in the form of ridges and grooves. In the case of copper, many large blisters with diameters ranging from 3.5 μm to 46 μm are observed in addition to some small ones (average diameter approx. 2 μm. The blister density of the large blisters is the highest in the case of copper (1.1 x 105 blisters/cm2). These observations of blister formation are related to the differences in the premeability of deuterium in these materials. An examination of the cross section of the ridges in fractured samples of graphite indicates that they are not hollow. The mechanisms of formation of these ridges is not clear at present. 1 figure
Original Title
60 keV, 8.1 x 1018 ions/cm2
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Secondary Subject
Source
Argonne National Lab., IL (USA); p. 227-230; 1979; p. 227-230
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Report
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Numerical Data
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ALLOYS, CARBON, CARBON ADDITIONS, CHARGED PARTICLES, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CLOSED PLASMA DEVICES, CORROSION RESISTANT ALLOYS, DATA, DATA FORMS, ELEMENTS, ENERGY RANGE, HEAT RESISTING ALLOYS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, KEV RANGE, METALS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NONMETALS, NUMERICAL DATA, PHYSICAL PROPERTIES, RADIATION EFFECTS, STAINLESS STEELS, STEELS, THERMONUCLEAR DEVICES, TOKAMAK DEVICES, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENTS
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Das, S.K.; Kaminsky, M.
Argonne National Lab., IL (USA)1979
Argonne National Lab., IL (USA)1979
AbstractAbstract
[en] The surface damage and erosion of chemically vapor deposited TiB2 coatings and commercial grade Ti, caused by 40-, 60- and 120-keV D+ and 4He+ irradiation, has been studied for the as deposited coatings and for the coating surfaces that were mechanically polished prior to irradiation. SEM analysis of polished TiB2 samples irradiated with D+ and 4He+ to a dose of 3.1 x 1018 ions/cm2 reveal significant surface damage due to blistering and flaking whereas for identical irradiation conditions, the as deposited TiB2 coatings show very little damage. For similar irradiation conditions the Ti metal samples showed blistering for the 4He+ irradiation case but no significant surface damage for the D+ case. Estimates of the irosion yields due to blister exfoliation in polished TiB2 samples show an increase with increasing projectile energy for the total dose studied
Primary Subject
Source
1979; 15 p; International conference on metallurgical coatings; San Diego, CA, USA; 23 - 27 Apr 1979; Available from NTIS., PC A02/MF A01
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Das, S.K.; Kaminsky, M.
Argonne National Lab., Ill. (USA)1976
Argonne National Lab., Ill. (USA)1976
AbstractAbstract
[en] Studies have been conducted to find materials with microstructures which minimize the formation of blisters. A promising class of materials appears to be sintered metal powder with small average grain sizes and low atomic number Z. Studies of the surface erosion of sintered aluminum powder (SAP 895) and of aluminum held at 4000C due to blistering by 100 keV helium ions have been conducted and the results are compared to those obtained earlier for room temperature irradiation. A significant reduction of the erosion rate in SAP 895 in comparison to annealed aluminum and SAP 930 is observed. In addition results on the blistering of sintered beryllium powder (type I) irradiated at room temperature and 6000C by 100 keV helium ions are given. These results will be compared with those reported recently for vacuum cast beryllium foil and a foil of sintered beryllium powder (type II) which was fabricated differently, than type I. For room temperature irradiation only a few blisters could be observed in sintered beryllium powder type I and type II and they are smaller in size and in number than in vacuum cast beryllium. For irradiation at 6000C large scale exfoliation of blisters was observed for vacuum cast beryllium but much less exfoliation was seen for sintered beryllium powder, type I, and type II. The results show a reduction in erosion rate cast beryllium, for both room temperature and 6000C
Primary Subject
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1976; 17 p; 2. international conference on surface effects in controlled fusion devices; San Francisco, California, United States of America (USA); 16 Feb 1976; Available from NTIS; Available from NTIS. $3.50.
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Report
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Conference
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Kaminsky, M.; Das, S.K.
Argonne National Lab., IL (USA)1978
Argonne National Lab., IL (USA)1978
AbstractAbstract
[en] Different metals have been proposed for radiation blistering of metals. For example, for the formation of blisters on helium bombarded metal surfaces such models are based on the coalescence of gas bubbles and the build-up of excess gas pressure in the implant region, causing large enough stresses for the occurrence of plastic deformation of the surface regions; or the percolation of helium in the lattice; or the build-up of large, lateral stresses in the implant layer causing buckling. These models are critically reviewed in the light of recent experimental results. A discussion of blistering effects at high doses is included
Original Title
4He+
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Secondary Subject
Source
1978; 28 p; 9. symposium on the physics of ionized gases; Dubrovnik, Yugoslavia; 28 Aug - 2 Sep 1978; Available from NTIS., PC A03/MF A01
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Das, S.K.; Kaminsky, M.
Argonne National Lab., Ill. (USA)1972
Argonne National Lab., Ill. (USA)1972
AbstractAbstract
No abstract available
Original Title
He bubble and blister formation at RT to 9000C and 0.5 MeV
Primary Subject
Source
1972; 15 p; Conference on defects and defect clusters in bcc metals and their alloys; Gaithersburg, Maryland, USA; 14 Aug 1973
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