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IRRADIATION OF BERYLLIUM AT ELEVATED TEMPERATURES. PART I. IRRADIATION OF RIG X-17 IN HIFAR

Technical Report ·
OSTI ID:4629172

S>Results are given of an experiment in which beryllium metal, fabricated by six different routes, was irradiated to fast neutron doses of 3.5 to 5.5 x 10/sup 20/ nvt at temperatures of 450, 550, and 850 deg C. The examination covered density and dimensional changes, hardness and tensile testing, and optical and electron microscopy. Comparisons are given of the behavior of irradiated specimens, asreceived specimens, and control specimens given heat treatment similar to that received by the irradiated specimens. Volume changes in the irradiated specimens, due to the accumulation of helium gas into bubbles, are very small. It appears that the growth of gas bubbles in these materials occurred almost entirely at the grain boundaries and further, that the bubbles were larger in material that was heat treated before irradiation. Tensile properties were markedly affected by heat treatment, the elongation being much increased in most cases, but irradiation caused a marked decrease in elongation combined with increases in proof stress and ultimate tensile strength. The effect of irradiation was worst for irradiation and testing at 850 deg C and this is interpreted in terms of the distribution of gas bubbles at the grain boundaries. (auth)

Research Organization:
Australia. Atomic Energy Commission Research Establishment, Lucas Heights, New South Wales; United Kingdom Atomic Energy Authority. Reactor Group, Springfields, Lancs, England
NSA Number:
NSA-17-039677
OSTI ID:
4629172
Report Number(s):
TRG-Report-540
Country of Publication:
United Kingdom
Language:
English

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