Fuel rod having heat transfer liquid filling the gap between fuel pellets and cladding tube
An improvement in a nuclear fuel rod is disclosed. The improved fuel rod includes a cladding tube, a plurality of fuel pellets stacked within the cladding tube, and a liquid material filling the gap between the fuel pellets and the cladding tube. The liquid material is selected from those having a thermal conductivity higher than that of helium, a melting point lower than about 400° C., a boiling point higher than 1600° C., and which are capable of wetting both the fuel pellets and the cladding sufficient to form a protective layer over the pellets and to wick into openings that may form in the cladding.
1. A nuclear fuel rod, comprising:
a silicon carbide cladding tube;
a plurality of fuel pellets stacked within the cladding tube, wherein the fuel pellets are selected from the group consisting of UO 2 , UN, U 3 Si 2 , and combinations thereof; and
a Sn—Zn alloy filling a gap between the fuel pellets and the cladding tube such that the Sn—Zn alloy is in direct contact with the silicon carbide cladding tube and the fuel pellets, the Sn—Zn alloy having a thermal conductivity higher than that of helium gas, a melting point above 315° C. and lower than 400° C., a boiling point higher than 1600° C., the Sn—Zn alloy capable of wetting both the silicon carbide cladding tube and the fuel pellets sufficient to wick into a crack in the cladding, the Sn—Zn alloy forming a solid protective layer over the pellets based on coolant contacting the Sn—Zn alloy via the crack, and the Sn—Zn alloy forming a plug within the crack based on coolant contacting the Sn—Zn alloy via the crack.
2. The nuclear fuel rod of claim 1 wherein the Sn—Zn alloy is selected from the group consisting of tin-based alloys, and zinc-based alloys.
3. The nuclear fuel rod of claim 2 wherein the Sn—Zn alloy is a zinc-based alloy.
4. A nuclear fuel rod, comprising:
a silicon carbide cladding tube;
a plurality of fuel pellets stacked within the cladding tube, wherein the fuel pellets comprise uranium-based fuel pellets; and
a Sn—Zn alloy filling a gap between the fuel pellets and the cladding tube such that the Sn—Zn alloy is in direct contact with the silicon carbide cladding tube and the fuel pellets, the Sn—Zn alloy having a thermal conductivity higher than that of helium gas, a melting point below 315° C., a boiling point higher than 1600° C., the Sn—Zn alloy is capable of wetting both the cladding and the fuel pellets sufficient to wick into a crack in the cladding and to form a layer over the pellets, wherein the Sn—Zn alloy wetting the cladding and the fuel pellets is configured to react with coolant to form a solid layer over the pellets based on the coolant contacting the Sn—Zn alloy via the crack in the cladding.
5. The nuclear fuel rod of claim 4 , wherein the Sn—Zn alloy comprises a eutectic alloy.
6. The nuclear fuel rod of claim 5 , wherein the eutectic alloy has a melting point corresponding to the eutectic temperature.
7. The nuclear fuel rod of claim 4 , wherein the uranium-based fuel pellets comprise UO 2 fuel pellets.
8. The nuclear fuel rod of claim 4 , wherein the uranium-based fuel pellets comprise UN fuel pellets.
9. The nuclear fuel rod of claim 4 , wherein the uranium-based fuel pellets comprise U 3 Si 2 fuel pellets.
10. The nuclear fuel rod of claim 4 , wherein the gap between the fuel pellets and the cladding tube is up to 0.1 mm.