Gas retention in irradiated beryllium

Technical Report · Fri Jun 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/6133872· OSTI ID:6133872

Beeston, J M; Miller, L G; Longhurst, G R ^[1]; Causey, R A ^[2]

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1. EG and G Idaho, Inc., Idaho Falls, ID (USA)
2. Sandia National Labs., Albuquerque, NM (USA)

Helium (an inert gas) with low solubility in beryllium is trapped in irradiated beryllium at low temperatures (<100{degree}C) while the tritium generated may have some mobility and be released. The subject of tritium retention in irradiated beryllium within fusion reactor blankets is of considerable interest in their conceptual design. Results from experiments on three sets of irradiated beryllium specimens are examined in this paper. The beryllium specimens were irradiated at abut 75{degree}C in capsules to protect them from the cooling water. One set of samples was irradiated to {approximately}3 {times} 10{sup 22} n/cm{sup 2} (E > 1 MeV). In these samples the calculated helium generated was {approximately} 14,000 appm. They are described in terms of swelling, annealing, microstructure, and helium bubble behavior (size, density and mobility). A second sample was irradiated to {approximately}5 {times} 10{sup 22} n/cm{sup 2} (E > 1 MeV). In that one the calculated helium and tritium generated were {approximately}24,000 appm He and {approximately}3720 appm, and tritium content was examined in a dissolution experiment. Most of the tritium was released as gas to the glovebox indicating the generated tritium was retained in the helium bubbles. In a third set of experiments a specimen was examined by annealing at a succession of temperatures to more than 600{degree}C for tritium release. In the temperature range of 300--500{degree}C little release (0.01--0.4%) occurred, but there was a massive release at just over 600{degree}C. Theories of swelling appear to adequately describe bubble behavior with breakaway release occurring at high helium contents and at large bubble diameters. 8 refs., 6 figs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6133872
• Report Number(s): EGG-FSP-9125; ON: DE91006206; TRN: 91-001931
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
36 MATERIALS SCIENCE
BERYLLIUM
SWELLING
HELIUM
SOLUBILITY
TRITIUM
ANNEALING
BREEDING BLANKETS
BUBBLES
IRRADIATION
THERMONUCLEAR REACTOR MATERIALS
ALKALINE EARTH METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
ELEMENTS
FLUIDS
GASES
HEAT TREATMENTS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATERIALS
METALS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
RARE GASES
REACTOR COMPONENTS
YEARS LIVING RADIOISOTOPES
700209* - Fusion Power Plant Technology- Component Development &amp; Materials Testing
360106 - Metals &amp; Alloys- Radiation Effects