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 null-phase temperatures so that temperature difference between the opposite walls is 50null 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:
A fuel box for a nuclear fuel bundle for a boiling water reactor is manufactured by zirconium alloy plates. The plates have a composition such that the material after beta quenching and heat treatment will have a ductile, so called basketweave structure.
Abstract:
In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.
Abstract:
Nuclear fuel rod tubes of zirconium alloy are heat treated in an induction furnace to produce a protective oxide coating two to fifteen microns in thickness. The furnace is only slightly larger than the tubes and receives the endmost eight inches of the tube. The furnace is controllable in zones along the tube. To calibrate the furnace to produce the desired temperature profile, typically a flat profile at a temperature between 650.degree. and 750.degree. C..+-.1.5.degree. C., a temperature calibration probe is provided with spaced thermocouples for sensing the temperature developed in the probe at each of the zones when heated. The probe is made of inconel 600 stainless or the like, and is dimensioned and shaped to correspond closely to the dimensions of the fuel rod tubes, including having a closed chamfered end. At the opposite end the probe protrudes from the furnace, where the thermocouple leads are terminated. The leads pass through a potting compound in the probe, such as magnesium oxide. Whereas the probe conductive structures are substantially identical to the tube, the probe responds to the electromagnetic field in the induction furnace substantially the same as does the end of the tube, permitting calibration of the induction furnace zones for a desired temperature profile, e.g., flat along the length of the tube, notwithstanding differences in induced currents that would otherwise occur due to the end of the tube or the adjacent tube material.
Abstract:
The present invention relates to a process for the manufacture of zirconium based tubes formed from layers of varying composition. The process consists in preparing the tubular blank which is intended to form the outer layer of the tube by rolling-soldering a sheet, and then in fitting it onto another tubular blank, or core block, of smaller diameter, which is obtained by piercing a small bar, and which may be coated on the inside with a plating, in soldering the ends of said blanks in order to subject the assembly to a treatment of placing it in solution in a beta phase, followed by soaking it in water and drawing it. The invention is used for the production of Duplex or Triplex type tubes with an improvement in the gross weight of zirconium needed to make 1000 kg of useful metal, with good adherence being obtained between the layers of said tube.
Abstract:
A method for the destruction of chemical stable waste by pyrolysis whereby heat is applied to the waste using at least one plasma torch formed of non-transferred arc plasma type. The waste generated inside a duct having an end orifice flows upward passing the orifice and toward the nozzle of the plasma torch, wherein the axis of the nozzle of the plasma torch and the axis of the orifice are substantially collinear. Gaseous and/or liquid waste products resulting from the heating step are subjected to expansion and combustion in the combustion chamber whereby gaseous products resulting from combustion and expansion are quenched and then washed.
Abstract:
The present invention relates to a method of manufacturing tubes for a nuclear fuel element sheath, comprising a plurality of successive cold rolling and annealing steps including a final .beta. phase heat treatment consisting of maintaining said tube at a temperature between 950.degree. C. and 1250.degree. C. for a time duration sufficient for obtaining a homogeneous .beta. phase within and throughout the whole thickness of said tube, and rapidly cooling said tube to ambient temperature for retaining said .beta. phase throughout the whole thickness of said tube during subsequent cold processing steps including final cleaning of the tube.
Abstract:
The zirconium cladding of a coolant-displacement rod of a nuclear reactor is precollapsed in the zirconium oxide stack of pellets which supports the cladding. Current is conducted through the cladding in an atmosphere at reduced pressure containing residual oxygen, to heat the cladding to a temperature at which its yield strength is reduced. Then, while the rod remains at this temperature, it is subjected to isostatic pressure which collapses the cladding uniformly. The formation, by reason of exposure to neutron flux, of a long unsupported gap in the cladding which might be collapsed under the pressure of the coolant is precluded. In addition, the rod retains its symmetry. The outer surface of the cladding is oxidized, facilitating the movement of the rod into its thimbles of the core and improving the resistances of the cladding to reaction with the coolant.
Abstract:
This is a very narrowly defined martensitic steel alloy fuel cladding material for liquid metal cooled reactors, and a process for making such a martensitic steel alloy material. The alloy contains about 10.6 wt. % chromium, about 1.5 wt. % molybdenum, about 0.85 wt. % manganese, about 0.2 wt. % niobium, about 0.37 wt. % silicon, about 0.2 wt. % carbon, about 0.2 wt. % vanadium, 0.05 maximum wt. % nickel, about 0.015 wt. % nitrogen, about 0.015 wt. % sulfur, about 0.05 wt. % copper, about 0.007 wt. % boron, about 0.007 wt. % phosphorous, and with the remainder being essentially iron. The process utilizes preparing such an alloy and homogenizing said alloy at about 1000.degree. C. for 16 hours; annealing said homogenized alloy at 1150.degree. C. for 15 minutes; and tempering said annealed alloy at 700.degree. C. for 2 hours. The material exhibits good high temperature strength (especially long stress rupture life) at elevated temperature (500.degree.-760.degree. C.).
Abstract:
A zirconium alloy sheet containing 2 to 3% of niobium is cooled at a controlled and moderate rate to the .alpha.+.beta. state. Plates (2, 2') are cut from the cooled sheet and cold-formed. The grid (1) is assembled from the plates (2, 2') which are welded together and the completed grid is then returned to the .alpha. phase by heating at a temperature of between 400.degree. and 550.degree. C. for a period of ten to thirty hours.