Characterization of graphite-matrix pulsed reactor fuels
The performance of the Annular Core Pulsed Reactor (ACPR) is being upgraded in order to accommodate higher fluence experiments for fast reactor fuel element transient and safety studies. The increased fluence requires a two-zone core with the inner zone containing fuel having a high enthalpy and the capability of withstanding very high temperatures during both pulsed and steady state operation. Because the fuel is subjected to a temperature risetime of 2 to 5 ms and to a large temperature difference across the diameter, fracture due to thermal stresses is the primary failure mode. One of the fuels considered for the high enthalpy inner region is a graphite-matrix fuel containing a dispersion of uranium--zirconium carbide solid solution particles. A program was initiated to optimize the development of this class of fuel. This summary presents results on formulations of fuel which have been fabricated by the Materials Technology Group of the Los Alamos Scientific Laboratory.
- Research Organization:
- Sandia Labs., Albuquerque, N.Mex. (USA)
- DOE Contract Number:
- E(29-1)-789
- OSTI ID:
- 7138298
- Report Number(s):
- SAND-76-5706; CONF-761101-6; TRN: 77-002109
- Resource Relation:
- Conference: 24. conference on remote systems technology, Washington, DC, USA, 14 Nov 1976
- Country of Publication:
- United States
- Language:
- English
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ACPR REACTOR
DISPERSION NUCLEAR FUELS
FABRICATION
MECHANICAL PROPERTIES
SPECIFICATIONS
THERMAL STRESSES
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
MIXED SPECTRUM REACTORS
NUCLEAR FUELS
PULSED REACTORS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SOLID FUELS
SOLID HOMOGENEOUS REACTORS
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors