Fuel cladding covered by a mesh
In various aspects, a nuclear fuel rod cladding is disclosed. The cladding can include a base tube and a mesh structure including gaps therein. The base tube can include an elongated tubular wall and can be configured to house nuclear fuel therein. The mesh structure can be positioned along at least a portion of the elongated tubular wall and can be configured to provide structural support to the base tube. In one aspect, the gaps of the mesh structure are designed to permit neutrons emitted by the nuclear fuel to pass therethrough to escape the fuel rod cladding.
1 . A nuclear fuel rod cladding, the nuclear fuel rod cladding comprising:
a base tube comprising an elongated tubular wall, the base tube configured to house nuclear fuel therein, wherein the base tube consists of a zirconium or a zirconium alloy material; and
an oxidation-resistant mesh coating comprising mesh segments, wherein the mesh coating is formed directly on an outer surface of the elongated tubular wall, and wherein gaps are defined between the mesh segments corresponding to portions of the outer surface of the tubular wall that are uncoated by the mesh coating;
wherein the mesh coating is configured to limit oxidation formed on the elongated tubular wall to provide structural support to the base tube; and
wherein the gaps of the mesh coating are designed to permit neutrons emitted by the nuclear fuel to pass therethrough to escape the fuel rod cladding.
2 . The nuclear fuel rod cladding of claim 1 , wherein the mesh coating comprises chromium, yttrium, iron, or a combination thereof.
3 . The nuclear fuel rod cladding of claim 1 , wherein the portions of the outer surface of the tubular wall uncoated by the mesh coating corresponding to the gaps are in a range of about 5% to about 90% of a surface area of the outer surface of the elongated tubular wall.
4 . The nuclear fuel rod cladding of claim 1 , further comprising an oxidation-resistant coating applied to an outer surface of the mesh coating and the portions of the outer surface of the tubular wall that are uncoated by the mesh coating.
5 . The nuclear fuel rod cladding of claim 1 , wherein the mesh coating is configured in a square pattern, a diamond pattern, a spiral pattern, or a combination thereof.
6 . The nuclear fuel rod cladding of claim 1 , wherein the mesh segments have a width in a range of about 0.5 mm to about 3 mm.
7 . The nuclear fuel rod cladding of claim 1 , wherein the mesh segments have a thickness in a range of 10 microns to 30 microns.
8 . A nuclear fuel rod cladding, the nuclear fuel rod cladding comprising:
a base tube comprising an elongated tubular wall, the base tube configured to house nuclear fuel therein, wherein the base tube consists of a zirconium or a zirconium alloy material; and
a porous coating directly on an outer surface of the elongated tubular wall, wherein the porous coating comprises pores therein, and wherein the pores define portions of the outer surface of the elongated tubular wall that are uncovered by the porous coating;
wherein the porous coating is configured to limit oxidation formed on the elongated tubular wall to provide structural support to the base tube; and
wherein the pores of the porous coating are designed to permit neutrons emitted by the nuclear fuel to pass therethrough to escape the fuel rod cladding.
9 . The nuclear fuel rod cladding of claim 8 , wherein the porous coating comprises chromium, yttrium, iron, or a combination thereof.
10 . The nuclear fuel rod cladding of claim 8 , wherein wherein the portions of the outer surface of the elongated tubular wall that are uncovered by the porous coating and are defined by the pores are in a range of about 5% to about 90% of a surface area of the outer surface of the elongated tubular wall.
11 . The nuclear fuel rod cladding of claim 3 , wherein the portions of the outer surface of the tubular wall uncoated by the mesh coating corresponding to the gaps are in a range of 50% to 90% of a surface area of the outer surface of the elongated tubular wall.