Abstract:
An apparatus (5) for splitting pipes (11) comprises means (1) for forming a longitudinal cut of the pipe (11), and diverging means (2) for opening up the cut pipe to expose the pipe interior. A method for splitting pipes (11) comprises the steps of forming a longitudinal cut of the pipe and opening out the cut pipe to expose its interior.
Abstract:
A method of incineration of minor actinides in nuclear reactors is presented. The minor actinides to be incinerated are embedded in at least one finite region of a core of a thermal nuclear reactor. This finite region is isolated from the rest of the core by means of a thin layer of material that absorbs thermal neutrons but is transparent to fast neutrons. This isolating material is preferably fissile, so that the neutron flux in the core is not simply filtered of its thermal neutrons, but also amplified in its fast neutrons.
Abstract:
The invention concerns a monobloc fuel element (10) formed with coated fissile particles, embedded in a matrix such as SiC, inert relative to the fissile and fertile heavy nucleus balance and relative to the coolant flowing in and around said element. Furthermore, the fuel element (10) comprises parallel plates (12) defining spaces (14, 20) between them. The ratio of the thickness (e1, e2) of the plates to the spaces enables to place at will the fuel element in the fast spectrum or in a thermal spectrum. The use of said fuel element in a boiling water and fast spectrum nuclear reactor and operating in natural circulation, wherein said ratio is substantially equal to 1, enables a high plutonium consumption.
Abstract:
The aim of the invention is to rectify disadvantages of conventional arrangements for dosing lithium in cooling water containing cationic impurities or for reducing cationic impurities. The cooling water cycle is guided through a first side of an electrodialysis unit and a concentration cycle is guided through a second side of the electrodialysis unit. Cationic impurities are filtered out of the medium of the concentration cycle by means of a selective ion exchanger that is arranged in the concentration cycle.
Abstract:
The present invention relates to a method for extracting the minor actinides from used nuclear fuel. The fuel of the initial load in the core (1) consists of a fuel mixture containing plutonium and aluminium granules, wherein the plutonium is present in an amount ranging from 1 to 2 atomic-percentage % while the balance consists of aluminium. The criticality of the core (1), which decreases together with the fuel depletion in the initial load, is maintained by adding minor-actinide granules in said load. After the plutonium has burnt out, a fuel is produced in the form of a metallic alloy containing minor actinides and aluminium in amounts ranging from 3 to 3.5 atomic-percentage % for the minor actinides and from 96.5 to 3 atomic-percentage % for the aluminium. The fuel composition thus obtained is maintained until the end of the burning process of the accumulated minor actinides. The minor-actinide combustion in the core (1) is compensated with plutonium. After the minor actinides have burnt out, a fuel is produced in the form of a metallic alloy that contains between 1 and 2 atomic-percentage % of plutonium, the balance consisting of aluminium. The composition thus obtained of the fuel in the mixture is maintained until the end of the burning process of the remaining plutonium reserves. This operation method for a fast homogeneous nuclear reactor is used for destroying the highly-radioactive and long-life irradiating products, i.e. minor actinides, in the nuclear fuel. This method also provides for a wider range of construction materials for the vessel (2) of the core (1), and can be used for reducing the accumulated amounts of military-grade plutonium.
Abstract:
A method of generating electricity from a radioactive source comprises placing the radioactive source inside a radiation proof container, subjecting the source to a magnetic field to thereby separate positively and negatively charged particles emanating from the source, collecting the charged particles at separate locations within the container and attaching conductors to the charged particle collectors to conduct electrical current to the outside of the container.
Abstract:
The present invention relates to a miniaturized nuclear reactor utilizing improved pressure tube structural members comprising: a moderator containing one calandria tube (12) contained within the moderator (20); one fuel channel pressure tube (14) contained within the one calandria tube (12); one fuel bundle (26) contained within the one fuel channel pressure tube (14); one fuel channel pressure tube pad (18) positioned between the one calandria tube (12) and the one fuel channel pressure tube (14); one horizontal exterior support pad (30) positioned on the bottom reactor wall, one fuel bundle pad (16) positioned between the one fuel bundle (26) and the one fuel channel pressure tube (14); one vertical support pad (24) positioned on a reactor side wall between the one calandria tube (12) and the reactor side wall; one angular support pad (28) positioned on a corner formed between the reactor top wall and the reactor side wall.
Abstract:
A reactivity control system includes a reservoir (42) containing a liquid nuclear poison (44), at least one stationary, hollow control blade (32) extending vertically into a reactor core (14), and a poison conduit (52) disposed in flow communication between the reservoir (42) and control blade (32) for channelling the poison (44) between the reservoir (42) and control blade (32). The level of the poison in the control blade is controlled for selectively varying nuclear reactivity in the core.
Abstract:
A nuclear reactor adapted for generating energy and/or decontaminating nuclear fuel using a plurality of energy beam generating accelerator devices configured for inducing a photo-fission reaction in the nuclear fuel.
Abstract:
A nuclear-powered plant for systems of up to about 100 MWs with a confinement section where the reaction takes place in a core having a reactive thorium/uranium-233 composition, and where an external neutron source is used as a modulated neutron multiplier for the reactor core output. The core is housed in a containment structure that radiates thermal energy captured in a multiple-paths heat exchanger. The exchanger heat energy output is put to use in a conventional gas-to-water heat exchanger to produce commercial quality steam.