The invention provides a nuclear reactor cladding, wherein at least one layer of coating is deposited on the exterior surface of the cladding. A nuclear reactor cladding, wherein at least one layer of coating is deposited on the interior surface of the cladding. A method of coating a nuclear reactor cladding, with the steps of selecting the cladding and depositing at least one layer of a first coating on the cladding.

A fuel channel for a nuclear power boiling water reactor is configured to include a bundle of fuel rods with nuclear fuel. The fuel channel is made of a sheet material and has a plurality of sides which have an elongated shape and which are connected to each other such that a corner with an elongated shape is formed where two adjacent sides meet. In one or more corners, the sheet materials from the two adjacent sides overlap with each other such that there is a corner region with double sheet material consisting of the overlapping sheet material from one of the two sides and the overlapping sheet material from the other of the two sides.

A fuel channel for a nuclear power boiling water reactor is configured to include a bundle of fuel rods with nuclear fuel. The fuel channel is made of a sheet material and has a plurality of sides which have an elongated shape and which are connected to each other such that a corner with an elongated shape is formed where two adjacent sides meet. In one or more corners, the sheet materials from the two adjacent sides overlap with each other such that there is a corner region with double sheet material consisting of the overlapping sheet material from one of the two sides and the overlapping sheet material from the other of the two sides.

Methods, processes, and systems of nuclear reactor cores are provided. In one embodiment, the reactor core may comprise a nuclear fuel rod inserted into each of a plurality of moderator blocks in the reactor core; e.g., wherein the fuel comprises plutonium, carbon, hydrogen, zirconium and thorium. In some embodiments, the fuel may comprise hydrogen-containing glass microspheres, wherein the glass microspheres may be coated with a burnable poison, and other coating materials that may aid in keeping the hydrogen within the microsphere glass at relatively high temperature. The disclosed methods, processes and systems may aid in providing energy to remote areas.

Methods, processes, and systems of nuclear reactor cores are provided. In one embodiment, the reactor core may comprise a nuclear fuel rod inserted into each of a plurality of moderator blocks in the reactor core; e.g., wherein the fuel comprises plutonium, carbon, hydrogen, zirconium and thorium. In some embodiments, the fuel may comprise hydrogen-containing glass microspheres, wherein the glass microspheres may be coated with a burnable poison, and other coating materials that may aid in keeping the hydrogen within the microsphere glass at relatively high temperature. The disclosed methods, processes and systems may aid in providing energy to remote areas.

A thermal-neutron reactor core includes: a solid moderator expanding to a lengthwise direction; a fuel in the moderator, parallel to the lengthwise direction of the moderator, the fuel containing a fissile material; a cooling tube parallel to the lengthwise direction of the moderator; and a plurality of kinds of burnable poison included in the fuel. The may contain a metal hydride. Furthermore, the plurality of kinds of burnable poison may include one burnable poison containing a concentration of one particular isotope of that one burnable poison.

A fuel pellet for a nuclear reactor includes a plurality of tristructural-isotropic fuel particles embedded in a structural silicon carbide matrix. A method of manufacturing a fuel pellet includes the steps of coating a plurality of tristructural-isotropic fuel particles with a coating slurry including silicon carbide powder to form a plurality of coated fuel particles; compacting the plurality of fuel particles; and sintering the compacted plurality of fuel particles to form the fuel pellet.

A nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same. The fuel assembly comprises an enclosure adapted to enclose a porous nuclear fuel body having the volatile fission product therein. A fluid control subassembly is coupled to the enclosure and adapted to control removal of at least a portion of the volatile fission product from the porous nuclear fuel body. In addition, the fluid control subassembly is capable of circulating a heat removal fluid through the porous nuclear fuel body in order to remove heat generated by the nuclear fuel body.

A nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same. The fuel assembly comprises an enclosure adapted to enclose a porous nuclear fuel body having the volatile fission product therein. A fluid control subassembly is coupled to the enclosure and adapted to control removal of at least a portion of the volatile fission product from the porous nuclear fuel body. In addition, the fluid control subassembly is capable of circulating a heat removal fluid through the porous nuclear fuel body in order to remove heat generated by the nuclear fuel body.

A nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same. The fuel assembly comprises an enclosure adapted to enclose a porous nuclear fuel body having the volatile fission product therein. A fluid control subassembly is coupled to the enclosure and adapted to control removal of at least a portion of the volatile fission product from the porous nuclear fuel body. In addition, the fluid control subassembly is capable of circulating a heat removal fluid through the porous nuclear fuel body in order to remove heat generated by the nuclear fuel body.