Saturation behavior of cascade damage production using fission fragment and ion irradiations

Birtcher, R. C.; Averback, Robert S; Blewitt, T.H.

doi:10.1016/0022-3115(78)90041-7

Cited by 34 publications

(9 citation statements)

References 11 publications

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“…The cubic structures are not directly produced by the defect cascades• Increases in background scattering indicate damage saturation after about 0•01 dpa and growth of an amorphous phase at damage levels above 0.04 dpa. The defect saturation dose is in agreement with the saturation dose of fission-fragment damage in metals [13], and tile amount of damage required for amorphization of U3Si is in agreement with the amorphization dose when damage is produced by high-energy heavy ions [3]. A possible explanation of the homogeneous phase transformation and amorphization behavior is that individual fission-fragment events damage a volume of material while directly amorphizing a smaller volume• Volume changes (>2%) in the small amorphous volumes introduce long range strains which are responsible for the homogeneous change of the lattice parameter.…”

Section: Resultssupporting

confidence: 64%

“…2 increase is thought to be due to defect accumulation while the large increase after , 0.05 dpa is thought to be due to amorphization. The saturation of the initial increase occurs at a dose similar to that found for defect saturation in fission fragment irradiated metals [13]. The large increase in background scattering occurs in the dose regime required for amorphization of U3Si by heavy ions [3].…”

Section: Resultsmentioning

confidence: 63%

See 1 more Smart Citation

Neutron Irradiated Uranium Silicides Studied by Neutron Diffraction and Rietveld Analysis

Birtcher

Mueller

Richardson³

et al. 1989

MRS Proc.

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Section: Resultssupporting

confidence: 64%

Section: Resultsmentioning

confidence: 63%

Neutron Irradiated Uranium Silicides Studied by Neutron Diffraction and Rietveld Analysis

Birtcher

Mueller

Richardson³

et al. 1989

MRS Proc.

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“…[7,12,31,38,43,47,63,65,[72][73][74][75]. The data are shown in Table 2 for various metals and types of irradiation.…”

Section: Systematics Of Frenkel Pair Resistivitymentioning

confidence: 99%

Defect production efficiency in metals under neutron irradiation

Broeders

Konobeyev

2004

Journal of Nuclear Materials

122

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“…In metals, a vacancy/interstitial pair is dynamically unstable and will recombine if their separation is less than a few lattice spacings. This limits the concentration of displacement defects to less than about 1 atomic percent, even in the absence of long range mobility [380]. Vacancies and interstitials also migrate by thermally activated diffusion and disappear at surfaces and dislocations.…”

Section: Hydrogen Interactions With Plasma-facing Materialsmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Saturation behavior of cascade damage production using fission fragment and ion irradiations

Cited by 34 publications

References 11 publications

Neutron Irradiated Uranium Silicides Studied by Neutron Diffraction and Rietveld Analysis

Neutron Irradiated Uranium Silicides Studied by Neutron Diffraction and Rietveld Analysis

Defect production efficiency in metals under neutron irradiation

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

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