Abstract in simplified Chinese:一种用于构建燃料组装之一包覆或导引管的全部或部份的管系由一种合金制成,其重量组成为l.O%至1.7%的钖,0.55%至O.8%的铁,0.20%至0.60%的铬及钒中之至少一元素的总合量,及 O.10%至O.I8%的氧,碳及硅成份分别在100ppm至180ppm及50ppm至120ppm的范围中。合金亦仅包含锆及无可避免的杂质。
Abstract:
A fuel channel box manufacturing method processes a fuel channel box (1) of a zirconium-base alloy by a beta-quench treatment that heats the fuel channel box by a heating coil (2). 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 β-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:
The invention relates to a cladding tube (1) which is practically homogenous as far as chemical composition and particle structure is concerned and is made of zircalloy components, exhibiting an elongation at rupture of at least 20 % with a ductility parameter η = (a)
Abstract:
A tube for forming a nuclear fuel assembly guide tube or sheath. The tube is made of an alloy containing 1.0-1.7 wt % of tin, 0.55-0.8 wt % of iron, 0.20-0.60 wt % total of chromium and/or vanadium, and 0.10-0.18 wt % of oxygen, carbon and silicon being present in amounts of 100-180 ppm and 50-120 ppm respectively, while the only other components of the alloy are zirconium and the unavoidable impurities.
Abstract:
An underwater laser processing method is carried out by irradiating, through a laser beam irradiation apparatus, a laser beam having a high output, a short pulse and a visible wavelength to a surface of a structure immersed in a water to improve residual stress of a material of the surface of the structure and remove a crack or a CRUD thereof. The laser beam irradiation apparatus comprises a pulse laser device suspended into a water in which a metal material is accommodated from an upper side thereof for irradiating a laser beam having a visible wavelength to a processing position, a beam strength adjusting device for adjusting an output per 1 pulse of a laser beam generated by the pulse laser device and a mechanism for adjusting a spot diameter and a multiplexing ratio of an irradiated beam.
Abstract:
An underwater laser processing method is carried out by irradiating, through a laser beam irradiation apparatus, a laser beam having a high output, a short pulse and a visible wavelength to a surface of a structure immersed in a water to improve residual stress of a material of the surface of the structure and remove a crack or a CRUD thereof. The laser beam irradiation apparatus comprises a pulse laser device suspended into a water in which a metal material is accommodated from an upper side thereof for irradiating a laser beam having a visible wavelength to a processing position, a beam strength adjusting device for adjusting an output per 1 pulse of a laser beam generated by the pulse laser device and a mechanism for adjusting a spot diameter and a multiplexing ratio of an irradiated beam.
Abstract:
A method of operating a nuclear reactor having within a reactor core a plurality of nuclear fuel channel boxes (1) each formed of a tubular member made of a zirconium based alloy, comprising the steps of exchanging fuel (11) after a predetermined period of operation time, which fuel is disposed in the channel boxes (1), and subsequently operating the reactor in a predetermined period of time, said alloy containing hexagonal crystals having a strain occurring due to neutron irradiation of 0.5 x 10²² n/cm² growth being not more than 2.5 x 10⁻⁴, an operation of said reactor after the degree of burn-up on taking-out reached 32 GWd/t or after nuclear fuel (11) was exchanged being effected, while the channel boxes (1) are located at the same positions as those in a previous operation and while the nuclear fuel (11) is exchanged at least two times. Further disclosed is a method of manufacturing said nuclear fuel channel boxes (1).
Abstract:
L'acier austénitique destiné à être employé dans les zones radioactives des réacteurs nucléaires résiste dans une large mesure à la corrosion fissurante sous contrainte induite par les rayonnements lorsqu'on diminue sa teneur en silicium, en phosphore et en soufre par rapport aux qualités d'aciers disponibles dans le commerce et que sa structure granulaire présente des dépôts de carbure finement dispersés, notamment de carbure de niobium. Il est possible d'obtenir une fine dispersion en désagrégeant tout d'abord les dépôts grossiers de niobium au moyen de recuits à des températures comprises entre 1100 et 1150 °C et en faisant déposer le carbure au moyen de recuits ultérieurs à des températures d'environ 750 °C.