Cermet fuel in a light water reactor: a possible way to improve safety. Part I. Fabrication and characterization

Progress in Nuclear Energy

Volumn 38, Issue 3-4, 2001, Pages 267-270

  Troyanov, V ^a   Popov, V ^a   Baranaev, Iu ^a  

^a INSTITUTE OF PHYSICS AND POWER ENGINEERING   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

CERMETS; CHARACTERIZATION; DUCTILITY; FABRICATION; FISSION PRODUCTS; LIGHT WATER REACTORS; NUCLEAR FUEL CLADDING; NUCLEAR FUEL PELLETS; STRESS CORROSION CRACKING; TEMPERATURE; THERMAL CONDUCTIVITY; ZIRCONIUM ALLOYS;

CERMET FUEL UTILIZATION; DESIGN BASIS ACCIDENT;

NUCLEAR FUELS;

EID: 0035080509     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0149-1970(00)00114-1     Document Type: Article

References (3)

1. Popov V., Ryzhkov A., Sharapov V., Troyanov V., Nikishov O., Spasskov V. A Cermet Fuel Application for PWR Safety Improvement. Proc. International Conference: Design and Safety of Advanced Nuclear Power Plants. 7.7:1992;1. Tokyo, Japan.
2. Popov V.V., Karpin A.D., Rumyantsev V.N., Troyanov V.M., Sugonyaev V.N., Melnichenco N.A. Results of Experimental Investigation for Substantiation of WWER Cermet Fuel Pin Performance. IAEA-TECDOC. 970:1997;35.
3. Troyanov V.M. Proc. Japanese-Russian Experts Meeting on nuclear fuels. 10:1998;1 Japan Atomic Industrial Forum, Inc. Tokyo.