摘要:
The invention relates to a nuclear power plant in which the sluice (10) between a fuel pool (4) and a reactor cavity (2) is provided with a contactor (36), with which the sluice (10) is automatically locked when the water level (h) in the fuel pool (4) falls under a predetermined threshold value (h G ).
摘要:
A concrete storage module (26) is adapted to slideably receive a cylindrical canister assembly (12) therein. Heat dissipation fins (62) and a tubular heat shield (96) are disposed within the module to help dissipate heat emitted from the nuclear fuel assemblies stored in the canister to air flowing through the module. The canister assembly (12) is composed of a basket assembly (70) constructed from multi-layer structural plates disposed in cross-cross or egg carton configuration. A single port tool (106) is provided for draining water from the canister (12) and replacing the drain water with make-up gas. The single port tool is mounted in the cover (100) of the canister and is in fluid flow communication with the interior of the canister.
摘要:
The invention relates to a storage rack (1) for nuclear fuel assemblies, including a rigid structure (2) defining a plurality of adjacent cells (4) and including, in each cell, a sleeve (16) defining a cavity (18) for receiving a nuclear fuel assembly, the sleeve having, in a cross-section orthogonal to the longitudinal direction, a polygonal general form, the sides of which are provided by means of plates (30) made of neutron-absorbing material. According to the invention, the sleeve also comprises: - profiles (22), each forming a corner piece and arranged on at least a plurality of angles for said cross-section having a polygonal general form, said profiles acting as a mounting bracket for the plates made of neutron-absorbing material; and – a means (36) for maintaining the profiles therebetween.
摘要:
A spent fuel storage rack 1 according to the present invention is installed in a fuel storage pool of a nuclear facility, and has a rectangular parallelepiped shape forming a plurality of lattice-like cells 2a that are configured to separately accommodate a plurality of fuel assemblies in a matrix of rows and columns. As shown in Fig. 1 , the spent fuel storage rack 1 includes: a base 17 configured to support lower parts of fuel assemblies, the base 17 forming a bottom surface of the spent fuel storage rack 1; an outer frame 3 located above the base 17, the outer frame 3 forming an outermost periphery of the spent fuel storage rack 1; and a lattice body 2 disposed inside the outer frame 3, the lattice body 2 forming the lattice-like cells 2a. The lattice body 2 includes: a main lattice 4 having a height equivalent to an active length of the fuel assembly; an upper lattice 5 disposed above the main lattice 4 so as to be fitted to an upper end of the main lattice 4; and a lower lattice 6 disposed between the base 17 and the main lattice 4 so as to be fitted to a lower end of the main lattice 4. Thus, the main lattice 4 can be formed without welding, whereby the main lattice 4 can be made of a boron-added stainless steel to which a sufficient amount of boron is added to absorb neutrons.
摘要:
Various geometric constructs are configured for use in modeling a system using an analysis method to model such systems based upon interstitial regions formed by these geometric constructs (50).
摘要:
A transport container for nuclear fuel is provided, comprising an outer container provided with internal insulation, the insulation defining an internal cavity, the cavity receiving a plurality of fuel containers, wherein the internal volume of the fuel containers is at least 5 % of the external volume of the outer container. The container allows substantially higher volume proportions of enriched fuel to be safely transported than is possible with prior containers.
摘要:
Corner of each square pipe is molded into a terrace shape having steps. When a basket is constructed by these square pipes, steps of adjoining square pipes are assembled together face to face. Fuel rod aggregates are housed inside the square pipes and in a cells formed between the square pipes. Since the adjoining square pipes are assembled in a staggered arrangement, boundaries of the cells are defined by the walls of the square pipes itself.