Abstract: A heat exchanger for a nuclear reactor is provided. The heat exchanger comprises a first layer for flowing a first process fluid and a second layer for flowing a second process fluid. The first layer is comprised of a first material and the second layer is comprised of a second material differing in composition from the first material. The first layer and the second layer are stacked on each other in a core of the heat exchanger and the first layer and the second layer are bonded to each other. A heat exchanger for a nuclear reactor and a method for producing a heat exchanger are also provided.

Abstract: 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.

Abstract: A testing arrangement and method of using in performing an in-situ adhesion test of a cold spray deposit on a surface of a structure. The testing arrangement includes a specimen member having a number of apertures defined therein and a loading arrangement coupled to the specimen member. The loading arrangement is configured to provide a mechanical force of a known magnitude to the specimen member. In performing an in-situ test of a cold spray deposit on a structure, the method includes positioning the testing arrangement with respect to a surface of the structure, depositing the cold spray deposit on the surface of the structure, and testing the adhesion of the cold spray deposit to the surface.

Abstract: Methods and systems for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock comprising thorium and uranium with a first acid to form a first solution. The first solution is contacted an ion exchange resin that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin thereby forming a second solution. The second solution is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate. The precipitate is separated from the second solution.

Abstract: An enclosure for non-organic electronic components is provided which includes an inner cavity for housing non-organic electronic components and a neutron shielding barrier surrounding the inner cavity and the electronic components housed within the cavity. The barrier is formed from a neutron reflecting material in solid or powdered form and a neutron absorbing material in solid or powdered form. An optional structural support is provided in certain aspects of the enclosure design.