RADIOACTIVE WASTE SYSTEMS FOR A SODIUM-COOLED REACTOR
Journal Article
·
· Chem. Eng. Progr.
OSTI ID:4819820
A proposed radioactive waste handling system capable of processing wastes of a 360 Mw sodium-cooled, graphitemoderated reactor station is described. The design of the waste disposal facilities is similar to the system used for the Sodium Reactor Experiment and the system of the 75 Mw Hallam Power Reactor Station. (N.W.R.)
- Research Organization:
- Atomics International, Canoga Park, Calif.
- NSA Number:
- NSA-16-007334
- OSTI ID:
- 4819820
- Journal Information:
- Chem. Eng. Progr., Journal Name: Chem. Eng. Progr. Vol. Vol: 58
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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