Lattice distortion of an fcc crystal near a free surface

RADIATION-INDUCED VOIDS IN METALS. Proceedings of the 1971 International Conference Held at Albany, New York, June 9--11, 1971.

“…Beeler: I would like to mention two features of carbon atom and precipitate behavior in the alpha iron seen in computer experiments: (1) Single-layer carbon platelets form at (1 10) and (100) void facets. The associated strain field inhibits the dynamic approach of interstitials to voids.…”

“…Our first results concern mainly nickel bombarded with Ni' or Ni2+ ions (from 100 to 500 keV) and copper bombarded with 500-keV Cu' ions. The samples were either thin foils (2000 to 3000 8) directly examined by transmission electron microscopy after bombardment or thick foils back thinned after irradiation ; the samples were not helium preinjected.…”

“…Pin A-205 was clad in solution-treated and aged Nimonic PE16 and pin A-206 in solution-treated and aged FV548. Figure 7 is an electron micrograph of a sample of FV548 from pin A-206 showing voids with well-defined facets-consistent with truncated octahedra bounded by (11 1) and (100) faces-stacking-fault loops (of as-yet unidentified character), a dislocation substructure, and zones denuded of voids adjacent t o grain boundaries. (Although, in our experience, voids never form actually on grain boundaries, the existence of denuded zones adjacent to the boundaries is not an invariable feature; in many specimens, denuded zones are absent, whereas in others zones up t o 1500 a thick have been seen.…”

“…This is about one-half the rate that would produce central melting, an undesirable occurrence. Assuming a core height of 3 f t and a plant thermal efficiency of 40%, a 1000-MW(e) plant requires about 100,000 fuel elements.…”

“…Numerous experimental fuel pins and materials capsules have been irradiated to high burnups and fluences in EBR- 11. Recent results describing the irradiation-induced swelling of various austenitic stainless steels are described here. The volume changes in 316 and 347 stainless-steel fuel-rod claddings from the General Electric Company F 2 series experiments (irradiated to burnups of over 100,000 MWd/metric ton) have been determined by immersion density measurements and transmission electron microscopy. Type 304 stainless steel irradiated in a materials test capsule to fluences of 5.4 x 10'' neutrons/cm2 (E > 0.1 MeV) with accurately known temperatures in the range 380 t o 690°C (716 to 1274'F) has been studied by electron microscopy.…”