Water cooled nuclear reactor and fuel elements therefor
AssigneeGamma Engineering Corporation
InventorHerbert Feinroth
Life of this patent
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Abstract
A fuel rod for a water cooled nuclear reactor comprises a cladding made of a continuous wound ceramic fiber tube. The wound fibers are impregnated with a matrix to achieve a required density and exposed to ammonia gas to create a solid gel. The gel is fired to form a ceramic composite having desirable thermal properties, strength, corrosion resistance, toughness and neutron capture cross-section.
Claims30
A fuel element for a water cooled nuclear reactor comprising, a cladding defining a closed waterproof gastight chamber therewithin, and nuclear fuel means disposed withins aid chamber, the major portion of said cladding being formed of a fibrous ceramic composite material an dhaving a high density ceramic coating thereon which is impermeable to fission gases, said composite material comprising a tow of ceramic fibers surrounded by a continuous matrix of ceramic oxide, said cladding being inert in high temeprature H.sub.2 O, being strong, tough, and having high thermal shock resistance and low neutron capture cross-section.
A fuel element for a water cooled nuclear reactor, comprising:
- a cladding of tubular construction having an open end;
- means closing said open end to define a closed waterproof gastight chamber within said cladding;
- and
- nuclear fuel means disposed within said chamber,
- said cladding being formed of a fibrous ceramic composite material and having a high density ceramic coating thereon which is impermeable to fission gases, said composite material comprising a tow of ceramic fibers surrounded by a continuous matrix of ceramic oxide that is inert in high temperature H.sub.2 O, strong, tough, and has a high thermal shock resistance, and low neutron capture cross-section.
In combniation, a nuclear reactor including a pressure vessel, water disposed within said vessel, and a fuel assembly disposed in contact with said water, said fuel assembly including a plurality of fuel elements, each fuel element comprising a cladding defining a closed waterproof gastight chamber therewithin and nuclear fuel means disposed within said chamber, the major portion of said cladding being formed of a fibrous ceramic composite material and having a highd ensity ceramic coating thereon which is impermeable to fission gases, said composite material comprising a tow of ceramic fibers surrounded by a continuous matrix of ceramic oxide, said cladding being inert in high temperature H.sub.2 O, strong, tough, and having a high thermal shock resistance and a low neutron capture cross-section.
In combination, a nuclear reactor including a pressure vessel, water disposed within said vessel, and a fuel assembly disposed in contact with said water, said fuel assembly including a plurality of fuel elements, each fuel element comprising:
- a cladding of tubular construction having an open end;
- means closing said open end to define a closed waterproof gastight chamber within said cladding;
- and
- nuclear fuel means disposed within said chamber,
- said cladding being formed of a fibrous ceramic composite material and having a high density ceramic coating thereon which is impermeable to fission gases, said composite material comprising a tow of ceramic fibers surrounded by a continuous matrix of ceramic oxide that is inert in higher temperature H.sub.2 O, strong, tough, and has a high thermal shock resistance and low neutron capture cross-section.
A fuel element for a water cooled nuclear reactor comprising, a cladding defining a closed waterproof gastight chamber therewithin, and nuclear fuel means disposed within said chamber, the major portion of said cladding being formed of a fibrous ceramic composite material comprising continuously wound ceramic fibers having an average diameter of between about 10 and 20 microns, said cladding being inert in high temperature H.sub.2 O, being strong, tough, and having high thermal shock resistance and low neutron capture cross-section.
A fuel element for a water cooled nuclear reactor, comprising:
- a cladding of tubular construction having an open end;
- means closing said open end to define a closed waterproof gastight chamber within said cladding;
- and
- nuclear fuel means disposed within said chamber,
- said cladding being formed of a fibrous ceramic composite material comprising continuously wound ceramic fibers having an average diameter of between about 10 and 20 microns, said cladding being inert in high temperature H.sub.2 O, strong, tough, and having a high thermal shock resistance, and low neutron capture cross-section.
In combination, a nuclear reactor including a pressure vessel, water disposed within said vessel, and a fuel assembly disposed in contact with said water, said fuel assembly including a plurality of fuel elements, each fuel element comprising a cladding defining a closed waterproof gastight chamber therewithin and nuclear fuel means disposed within said chamber, the major portion of said cladding being formed of a fibrous ceramic composite material comprising continuously wound ceramic fibers having an average diameter of between about 10 and 20 microns, said cladding being inert in high temperature H.sub.2 O, strong, tough, and having a high thermal shock resistance and a low neutron capture cross-section.
In combination, a nuclear reactor including a pressure vessel, water disposed within said vessel, and a fuel assembly disposed in contact with said water, said fuel assembly including a plurality of fuel elements, each fuel element comprising:
- a cladding of tubular construction having an open end;
- means closing said open end to define a closed waterproof gastight chamber within said cladding;
- and
- nuclear fuel means disposed within said chamber,
- said cladding being formed of a fibrous ceramic composite material comprising continuously wound ceramic fibers having an average diameter of between about 10 and 20 microns, said cladding being inert in high temperature H.sub.2 O, strong, tough, and having a high thermal shock resistance, and low neutron capture cross-section.
Dependencies are inferred from the claim text.