Simulation of Short-Term Annealing of Displacement Cascades in Face-Centered Cubic Metals

Heinisch, HL; Doran, D.G.; Schwartz, David M.

doi:10.1520/stp28214s

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“…However, for a given o annealing condition, the residual point defect fraction (defects after annealing/defects initially produced) is independent of FKA energy from -10 to 500 keV (refs. 72,74). This result is critical to the validity of fission reactor simulation of fusion irradiations.…”

Section: Vacancies and Interstitialsmentioning

confidence: 99%

Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Maziasz¹

1985

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A major purpose of the Techni cal Information Center is to provide the broadest dissemination possi ble of information contained in DOE's Research and Development Reports to business, industry, the academib community, and federal, state and local governments.Although a small portion of this report is not reproducible, it is being made available to expedite the availability of information on the research discussed herein.

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Section: Vacancies and Interstitialsmentioning

confidence: 99%

Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Maziasz¹

1985

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Simulating Frenkel pair recombination by application of a space-partitioning tree data structure

Helm

1994

Radiation Effects and Defects in Solids

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Simulation of Short-Term Annealing of Displacement Cascades in Face-Centered Cubic Metals

Cited by 2 publications

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Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Simulating Frenkel pair recombination by application of a space-partitioning tree data structure

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