Abstract:
A fuel channel box manufacturing method processes a fuel channel box of a zirconium-base alloy by a beta-quench treatment that heats the fuel channel box by a heating coil. The distance between the heating coil and the opposite walls of the fuel channel box is controlled so that temperature differences between the opposite walls of the fuel channel box are reduced. The fuel channel box of a zirconium-base alloy is heated at a temperature in a temperature range including &bgr;-phase temperatures so that temperature difference between the opposite walls is 50° C. or below. The fuel channel box manufacturing method is capable of manufacturing a fuel channel box that is not subject to significant irradiated bow even if a deflection is produced therein originally when the same is manufactured and of manufacturing the fuel channel box at a high production efficiency.
Abstract:
This disclosure describes a method for metallurgically bonding a complete leak-tight enclosure to a matrix-type fuel element penetrated longitudinally by a multiplicity of coolant channels. Coolant tubes containing solid filler pins are disposed in the coolant channels. A leak-tight metal enclosure is then formed about the entire assembly of fuel matrix, coolant tubes and pins. The completely enclosed and sealed assembly is exposed to a high temperature and pressure gas environment to effect a metallurgical bond between all contacting surfaces therein. The ends of the assembly are then machined away to expose the pin ends which are chemically leached from the coolant tubes to leave the coolant tubes with internal coolant passageways. The invention described herein was made in the course of, or under, a contract with the U.S. Atomic Energy Commission. It relates generally to fuel elements for neutronic reactors and more particularly to a method for providing a leak-tight metal enclosure for a high-performance matrix-type fuel element penetrated longitudinally by a multiplicity of coolant tubes. The planned utilization of nuclear energy in high-performance, compact-propulsion and mobile power-generation systems has necessitated the development of fuel elements capable of operating at high power densities. High power densities in turn require fuel elements having high thermal conductivities and good fuel retention capabilities at high temperatures. A metal clad fuel element containing a ceramic phase of fuel intimately mixed with and bonded to a continuous refractory metal matrix has been found to satisfy the above requirements. Metal coolant tubes penetrate the matrix to afford internal cooling to the fuel element while providing positive fuel retention and containment of fission products generated within the fuel matrix. Metal header plates are bonded to the coolant tubes at each end of the fuel element and a metal cladding or can completes the fuel-matrix enclosure by encompassing the sides of the fuel element between the header plates.
Abstract:
A method of surface-treating a reactor member for effectively removing a Cr-deficient layer and a work-hardened layer considered to be a cause of stress-corrosion cracking (SCC) under low-stress conditions. The method of surface-treating a reactor member which is worked by bending (step 1) and then processed by a heat treatment (step 2), in which a work-hardened layer is formed by the bending, and in which a Cr-deficient layer is formed due to an oxide film attached by the heat treatment, uses at least one of: acid wash; grinding; electrolytic polishing; electro-discharge machining; surface cutting; surface deoxidation and softening; wet blasting; laser machining; or surface plating (step 3) to remove the work-hardened layer and the Cr-deficient layer from the reactor member or to prevent contact of the work-hardened layer and the Cr-deficient layer of the reactor member with a primary coolant.
Abstract:
Cladding tube for a fuel rod for a boiling water reactor fuel element, and its production. The cladding tube is composed practically homogeneously of the constituents of zircaloy and, with the ductility parameter &ggr;=3{square root over ((kd))}/(fr)2≦3.5 (&ggr;=ductility parameter, KD=mean grain diameter; fr=Kearns factor), has an elongation at break of at least 20%, set by low-temperature treatment of an extruded tube blank. The starting body used for the extrusion has a defined distribution of precipitated secondary particles which is produced by &bgr;-quenching and differs in the areas which form the inner surface and outer surface of the extruded tube. At the inner surface, the particles have a greater diameter and are at a greater average distance apart, this distribution being described by the “spacing”.
Abstract:
A laser maintaining and repairing apparatus including a laser oscillator 7, beam guiding apparatus 8 connected to guide a laser beam of the laser oscillator 7, and emitting head 12 for converging the laser beam from the beam guiding apparatus 8 and emitting the beam to a portion to be processed. The beam guiding apparatus 8 includes liquid-tight tubular beam guiding members 9a to 9h. The beam guiding members 9a to 9h are provided with reflecting members 13a, 13b and at least one of mechanisms 10a, 10b and 11a, 11b for providing horizontal turning, horizontal extending, vertical turning and vertical extending operations at the beam guiding members 9a to 9h. With the laser maintaining and repairing apparatus of the noted structure, a laser beam of high energy density can be utilized and processing by the laser beam can be facilitated or the applying range can be increased.
Abstract:
A tube of zirconium-based alloy for constituting all or a portion of a cladding or guide tube for a nuclear fuel assembly. The tube is made of an alloy containing, by weight, 1.0-1.7% of tin, 0.55-0.80% of iron, 0.20-0.60% total of chromium and/or vanadium, and 0.10-0.18% of oxygen, with 50-200 ppm of carbon and 50-120 ppm of silicon. The alloy further contains only zirconium and unavoidable impurities, and it is completely recrystallized.
Abstract:
A part of a light-water reactor, for example, a cladding for a light-water reactor has at least a portion made of an intermetallic compound, such as Ni.sub.3 Al, Ni.sub.2 Al.sub.3, TiAl, Ti.sub.3 Al, Pt.sub.2 Si, PtSi, FeAl.sub.2, CoAl, and MoSi.sub.2, thereby having limited irradiation degradation by fast neutrons, improved ductility and usability at high temperatures the intermetallic compound is produced by a process comprising a step of irradiating the intermetallic compound with at least one selected from the group consisting of a neutron, a light ion, and an electron. The intermetallic compound may contain a twin and a third additional element segregatedly present or forms a second phase at or near to a grain boundary.
Abstract:
The invention relates to a fuel element for a pressurized-water reactor comprising a number of fuel rods arranged in a square lattice and wherein certain positions in the lattice contain guide tubes for receiving control rods, wherein the fuel element can be used for higher burnup by manufacturing the guide tubes of the element such that their irradiation-induced growth is reduced and their corrosion resistance is increased compared with conventionally manufactured guide tubes. This is achieved by finally heat-treating the guide tubes in two steps, the first step being a beta quenching and the second step a heat treatment in the alpha-phase region.
Abstract:
A method for fabricating a composite cladding comprised of a moderate-purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube which improves corrosion resistance. The improved corrosion resistance of the liner is accomplished by suitable heat treatment of the Zircaloy-zirconium composite cladding to allow diffusion of alloying elements, notably Fe and Ni, from the Zircaloy into the zirconium, in particular, to the inner surface of the zirconium liner. This diffusion anneal reduces the undesirable tendency of zirconium liner to oxidize rapidly.
Abstract:
A method of maintaining the housing of a reactor pressure vessel having: a reactor pressure vessel into which cooling water is introduced; a cylindrical housing which penetrates an end bracket of the reactor pressure vessel; and a circumferential weld for securing the intermediate portion of the housing to the reactor pressure vessel by welding, the method of maintaining a housing of a reactor pressure vessel comprising the steps of: remaining the cooling water in the reactor pressure vessel; preventing leakage of the cooling water in the reactor pressure vessel through the housing by sealing the housing; making the inside portion of the housing lower than the seal to be a hollow space of a gas atmosphere; heating a heat affected zone due to welding by using a heating device inserted into the hollow space from a lower portion so as to compressive-yield the inner surface of the housing in the heat affected portion upper than the circumferential weld and tensile-yield the outer surface; and cooling heated portion inside of the housing, which has been yielded, so as to tensile-yield the inner surface of the housing by using a cooling device inserted into the housing from a lower portion, whereby compressive stress is allowed to remain in the tensile-yielded portion.