摘要:
The invention belongs to the technical field of nuclear reactor materials design, and discloses a method for improving the withstanding capability of the cladding material in the fast neutron irradiation environment, comprising the following steps: selecting the cladding material with the annular structure and placing it on the outer side of the metallic fuel slug, with leaving a 0.2-0.8 mm gap between the metallic fuel slug and the cladding material; processing the operation in a reactor subsequently, with an annealing process of the fast neutron reactor fuel during the operation of the reactor; improves the withstanding capability of the cladding material in the fast neutron irradiation environment. The invention processes annealing treatment of the cladding material by balancing the internal and external stresses, multiple cycles of steady-state and transient operations, enhancing the withstanding capability of the steel in the high neutron irradiation environment, improving the lifetime of the cladding material.
摘要:
A spring mounting device in a cladding tube for nuclear fuel, comprising a spring distributor, a spring loader in the cladding tube, the distributor supplying the springs to the loader, said loader comprising a longitudinal slide to receive the spring, a pusher in order to set the spring into place in the cladding tube and is able to move in the slide, means of displacement of said pusher, said device comprising mechanical means in order to associate the actuation of the means of displacement with that of the spring distributor.
摘要:
A method for installing a locking retainer in a tube to maintain internal components within the tube under compression comprising the steps of: a) providing an elongated retainer spring having large and small diameter sections with the large diameter section of a size for an interference fit with the interior diameter of the tube and the smaller diameter section of a size having a clearance with the interior diameter of the tube; b) inserting a smaller diameter section of an elongated tool into the larger diameter section of the elongated retainer spring; c) engaging a transition between the smaller and larger diameter sections of the tool against a transition between the larger and smaller diameter sections of the elongated retainer spring; d) inserting the combined tool and retainer spring into an open end of the tube containing internal components with an end of the smaller diameter section of the retainer spring entering the tube first; e) advancing the combined tool and retainer spring within the tube to compress the smaller diameter spring against an adjacent internal component until an end of the tool engages the adjacent internal component enabling the spring to apply a selected axial preload on the internal components in the tube; and f) withdrawing the tool from the retainer spring.
摘要:
Method of fabricating a fuel rod, comprising providing an effective amount of a metal oxide in the fuel rod to generate steam and mitigate the tendency for secondary hydriding. Fuel rods fabricated according to the method of the invention are also provided.
摘要:
Method of fabricating a fuel rod, comprising providing an effective amount of a metal oxide in the fuel rod to generate steam and mitigate the tendency for secondary hydriding. Fuel rods fabricated according to the method of the invention are also provided.
摘要:
The present invention relates to a fuel assembly with a substantially square cross section for a light-water reactor. The light-water reactor comprises a plurality of fuel rods (4) extending between a top tie plate (5) and a bottom tie plate (6). A fuel rod (4) comprises a cladding tube (7a) with a first and a second end which surround a column with fissionable material (7b). According to one aspect of the invention, at least one fuel rod (4) is provided with an axial gap (19) in the fissionable material (7b), such that fissionable material (7b) is arranged on both sides of the axial gap (19) in the fuel rod (4).
摘要:
A cladding tube for use in holding fissionable material in a water cooled nuclear reactor is provided. The cladding tube includes inner and outer circumferential regions, and including (1) a substrate defining the outer circumferential region, and (2) an inner liner defining the inner circumferential region. The inner liner is made from a zirconium alloy having at least one alloying element which promotes hydrogen absorption in a concentration of between about 1 and 15 weight percent. The hydrogen absorption promoting element can be one of the following: nickel, chromium, iron, zinc, vanadium, gallium, yttrium, palladium, platinum, or aluminum.
摘要:
The present invention provides a cladding having an outer circumferential substrate, a zirconium barrier layer metallurgically bonded to the inside surface of the substrate and an inner circumferential liner metallurgically bonded to the zirconium barrier. The inner circumferential liner is more ductile than conventional Zircaloy. The low ductility of the inner circumferential liner is obtained by using a zirconium alloy containing a low tin content (e.g. less than 1.2% by weight) and/or a low oxygen content (e.g. less than 1000 ppm). The inner circumferential liner is less than about 25 micrometers thick.
摘要:
A barrier tube of non-circular cross section is arranged in the space between the stainless steel cladding and metal fuel slugs of a liquid metal reactor. The non-circular shape of this barrier design promotes improved thermal bonding in both the cladding/barrier and barrier/fuel interface regions. The non-circular barrier results in three areas with liquid metal thermal bond gaps having an angle which approaches that for a metal fuel pin without a barrier. Thus, the degree of circumferential unbonding will be less than that which results in localized fuel melting during radiation.
摘要:
A fuel element for a nuclear reactor having a zirconium-tin alloy cladding tube, with a thin coating of particles of enriched boron-containing compound burnable poison particles, deposited from a liquid sol-gel which includes a glass binder material.