Design and experimental investigation into fuel element melting during pulsed heating in the IGRIK
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:186615
- All-Russian Research Institute of Technical Physics, Snezhinsk (Russian Federation); and others
Research has been performed on reactor fuel melting with pulsed input of energy in fuel elements up to 1.3 kj/g. The following were determined: energy input in fuel elements and energy input tempo; fission number distribution by the radius of the fuel element; the temperature of fuel and ampoule walls; and displacement of fuel boundaries.
- OSTI ID:
- 186615
- Report Number(s):
- CONF-950601-; ISSN 0003-018X; TRN: 96:007037
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 72; Conference: Annual meeting of the American Nuclear Society (ANS), Philadelphia, PA (United States), 25-29 Jun 1995; Other Information: PBD: 1995
- Country of Publication:
- United States
- Language:
- English
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