ANNULAR NUCLEAR FUEL ROD
Annular nuclear fuel rods are disclosed. The annular nuclear fuel rods include an outer cladding tube made of ceramic composite or cermet composite, an inner cladding tube made of ceramic composite or cermet composite, a nuclear fuel region located between the outer cladding tube and inner cladding tube, and an open channel for liquid coolant to flow.
1 . An annular nuclear fuel rod comprising:
an outer cladding tube made of ceramic composite or cermet composite;
an inner cladding tube made of ceramic composite or cermet composite;
a nuclear fuel region located between the outer cladding tube and inner cladding tube; and
an open channel for liquid coolant to flow, wherein the open channel extends through the inner cladding tube.
2 . The annular nuclear fuel rod of claim 1 , wherein the ceramic composite comprises silicon carbide (SiC), aluminum oxide (Al 2 O 3 ), boron carbide (BC), boron nitride (BN), carbon fiber (C), other ultra-high temperature ceramic matrix composites (UHTCMCs), technical ceramics such as: SiO 2 , SiN, ZrO 2 , SiAlON type ceramics, ZrB 2 , HfB 2 , TaSi 2 , Si 3 N 4 , MoSi 2 , ZrSi 2 , (Hf, Zr, Ta)C, or combinations thereof.
3 . The annular nuclear fuel rod of claim 1 , wherein the cermet composite comprises:
a metal; and
one or more of SiC, Al 2 O 3 , BC, BN, C, UHTCMCs, technical ceramics such as: SiO 2 , SiN, ZrO 2 , SiAlON type ceramics, ZrB 2 , HfB 2 , TaSi 2 , Si 3 N 4 , MoSi 2 , ZrSi 2 , (Hf, Zr, Ta)C, or combinations thereof.
4 . The annular nuclear fuel rod of claim 1 , wherein the nuclear fuel region comprises nuclear fuel in annular pellet form.
5 . The annular nuclear fuel rod of claim 4 , wherein the nuclear fuel in annular pellet form is selected from a group consisting of uranium dioxide (UO 2 ), uranium nitride (UN), uranium diboride (UB 2 ), uranium tetraboride (UB 4 ), and uranium carbide (UC), and wherein the nuclear fuel is alone, in combination with another nuclear fuel, or in combination with an additive selected from the group consisting of Zr, Cr, Mo, ZrB 2 , Cr 2 O 3 , Al 2 O 3 , and combinations thereof.
6 . The annular nuclear fuel rod of claim 4 , wherein the nuclear fuel in annular pellet form comprises greater than 5% enriched 235 U.
7 . The annular nuclear fuel rod of claim 4 , wherein the nuclear fuel in annular pellet form comprises at least 6% enriched 235 U.
8 . The annular nuclear fuel rod of claim 1 , further comprising:
an outer gap located between the outer cladding tube and the nuclear fuel region; and
an inner gap located between the inner cladding tube and the nuclear fuel region.
9 . The annular nuclear fuel rod of claim 1 , wherein the outer cladding tube, nuclear fuel region, and inner cladding tube are enclosed by a top end plug and a bottom end plug.
10 . The annular nuclear fuel rod of claim 9 , wherein the top end plug and bottom end plug are SiC annular end plugs or metallic annular end plugs.
11 . The annular nuclear fuel rod of claim 10 , wherein the SiC annular end plugs are attached to the outer cladding tube, nuclear fuel region, and inner cladding tube using ceramic brazing.
12 . The annular nuclear fuel rod of claim 10 , wherein the metallic annular end plugs are attached to the outer cladding tube, nuclear fuel region, and inner cladding tube using metallic brazing.
13 . The annular nuclear fuel rod of claim 8 , further comprising liquid metal in the outer gap located between the outer cladding tube and the nuclear fuel region.
14 . The annular nuclear fuel rod of claim 8 , further comprising liquid metal in the inner gap located between the inner cladding tube and the nuclear fuel region.
15 . The annular nuclear fuel rod of claim 9 , wherein the top end plug and bottom end plug are attached to the outer cladding tube, nuclear fuel region, and inner cladding tube using mechanical interlocking methods.
16 . The annular nuclear fuel rod of claim 9 , wherein the top end plug and bottom end plug are attached to the outer cladding tube, nuclear fuel region, and inner cladding tube using mechanical interlocking methods, ceramic brazing, metallic brazing, or combinations thereof.
17 . The annular nuclear fuel rod of claim 1 , wherein the annular fuel rod is used in reactors selected from the group consisting of: light water reactors (LWRs), heavy water reactors (HWRs), lead fast reactors (LFRs), sodium fast reactors, molten salt reactors, and gas cooled reactors.
18 . An annular nuclear fuel rod comprising:
an outer cladding tube made of ceramic composite or cermet composite;
an inner cladding tube made of ceramic composite or cermet composite;
a nuclear fuel region located between the outer cladding tube and inner cladding tube, wherein the nuclear fuel region comprises a nuclear cermet fuel in annular pellet form;
an open channel for liquid coolant to flow, wherein the open channel extends through the inner cladding tube.
19 . The annular nuclear fuel rod of claim 18 , wherein the nuclear cermet fuel in annular pellet form comprises:
an inert metal matrix; and
UO 2 , UN, UB 2 , UB 4 , or UC wherein the UO 2 , UN, UB 2 , UB 4 , or UC is alone, in combination, or in combination with an additive selected from the group consisting of Zr, Cr, Mo, ZrB2, Cr 2 03, AI2O 3 , and combinations thereof.
20 . The annular nuclear fuel rod of claim 18 , wherein the nuclear cermet fuel in annular pellet form comprises greater than 5% enriched 235 U.