摘要:
A channel box for nuclear-reactor fuel assemblies (MOX fuel assembly) containing plutonium is provided, capable of properly controlling excess reactivity without mixing neutron absorber or burnable poison into a fuel rod. In the channel box for a nuclear-reactor fuel assemblies, there is no gap between tne channel box (1) and members (4) containing burnable poison because the members (4) containing burnable poison are in the channel box. The burnable poison does not directly contact the reactor water. Alternatively, the burnable poison members are on a water rod (3).
摘要:
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.
摘要:
The present invention provides a zirconium based alloy member which has very small deformation of elongation and bow occurring due to irradiation growth, a method of manufacturing it, and particularly an channel box for an atomic reactor fuel assembly. A zirconium based alloy plate member having a width of not less than 100 mm and a long length, containing not more than 5 wt% Nb and/or not more 5 wt% Sn, the member having (0001) orientation (Fℓ value) of hexagonal Zr with respect to longitudinal direction ranging from 0.20 to 0.35, the difference in Fℓ between the middle and the end being not more than the value calculated from (0.0935 × Fℓ - 0.00585) and an amount of bow at neutron irradiation of 35 GWd/t which bow occurs in the channel box for a reactor being not more than 2.16 mm.