The swelling of beryllium from neutron-induced gases
Specimens of beryllium which had received an irradiation in the Materials Testing Reactor up to an integrated fast flux of 10 nvi have been examined after annealing at various temperatures above 400 deg C. These annealing treatments have resulted in significant decreases in over-all density of the beryllium specimens, the density decrease being 0.8 and 20% after annealing for one hour at 600 and 995 deg C, respectively. The quantity of neutron-induced gases contained in the beryllium was determined to be approximately 23 cc of gas per cc of beryllium for an integrated fast flux of 10 /sup 22/. Analysis of the gas shows that it is mainly He/sup 4/. The results of the investigation suggest that the neutron-induced gases will not be a serious deterrent to the use of beryllium in reactor applications at temperatures up to 600 deg C. (auth)
- Research Organization:
- Atomic Energy of Canada Ltd. Chalk River Project, Chalk River, ON (Canada)
- NSA Number:
- NSA-13-004217
- OSTI ID:
- 4282390
- Report Number(s):
- CRMet-809; AECL-719
- Country of Publication:
- Canada
- Language:
- English
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