New facility for post irradiation examination of neutron irradiated beryllium
- Oarai Research Establishment, Ibaraki-Ken (Japan)
Beryllium is expected as a neutron multiplier and plasma facing materials in the fusion reactor, and the neutron irradiation data on properties of beryllium up to 800{degrees}C need for the engineering design. The acquisition of data on the tritium behavior, swelling, thermal and mechanical properties are first priority in ITER design. Facility for the post irradiation examination of neutron irradiated beryllium was constructed in the hot laboratory of Japan Materials Testing Reactor to get the engineering design data mentioned above. This facility consist of the four glove boxes, dry air supplier, tritium monitoring and removal system, storage box of neutron irradiated samples. Beryllium handling are restricted by the amount of tritium;7.4 GBq/day and {sup 60}Co;7.4 MBq/day.
- Research Organization:
- Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
- OSTI ID:
- 212922
- Report Number(s):
- CONF-9509218-; ON: DE96002404; TRN: 96:010071
- Resource Relation:
- Conference: 2. International Energy Agency (IEA) workshop on beryllium technology for fusion, Jackson, WY (United States), 6-8 Sep 1995; Other Information: PBD: Sep 1995; Related Information: Is Part Of Proceedings: 2nd IEA international workshop on beryllium technology for fusion; Longhurst, G.R.; PB: 399 p.
- Country of Publication:
- United States
- Language:
- English
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