FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. PHASE I. Progress Report for May 1, 1959 to October 31, 1959
Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1 1/2 in. diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and fuel particle coatings such as alumina. Low fission product leakage rates at high temperatures have been observed for some of these coatings. High-level irradiation has given no visible evidence of radiation damage to either the silicon carbide coating or the coating-graphite bond. (auth)
- Research Organization:
- Sanderson and Porter, New York
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-15-001059
- OSTI ID:
- 4137406
- Report Number(s):
- NYO-2706
- Country of Publication:
- United States
- Language:
- English
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