19 results about "Spent nuclear fuel" patented technology

An apparatus for installing and removing a fixing device for handling a spent nuclear fuel assembly is disclosed. The apparatus for installing and removing a fixing device for handling a spent nuclear fuel assembly is an apparatus for installing or removing the fixing device, provided between an upper fixture and a guide pipe constituting a nuclear fuel assembly, to or from the spent nuclear fuel assembly, and comprises: a rod part including a rotating rod with one end detachably connected to the fixing device, and at least one cover rod in which the rotating rod is positioned; and an operation part connected to the rod part so as to vertically move or rotatably operate the rotating rod and the cover rod.

Provided is a radiation decomposition device and a radiation decomposition method that allow efficient decomposition of an irradiated substance while reducing the size of equipment as much as possible. A radiation decomposition device (100) according to the present invention is characterized by including: a radiation source (101) that emits radiation released from a sealed radioactive substance; a reaction tank (103) that contains a to-be-irradiated substance (104); and a heat transfer tank (102) that covers the radiation source (101) and transfers, to the reaction tank (103), heat generated by the decay of the radioactive substance. It is preferable that the radiation source (101) is: a radiation source formed of spent nuclear fuel or vitrified waste containing fission products extracted from spent nuclear fuel; a radiation source containing fission products extracted from spent nuclear fuel; a radiation source containing Co-60; a radiation source containing Cs-137; or a high-level radioactive waste liquid.

The application belongs to the technical field of separation and extraction, and particularly relates to a 8C-DAPhen ligand, a preparation method and application thereof. The method is developed from the design of a ligand molecular structure, and a novel cyclic DAPhen ligand is developed through specific structure design. The ligand has a separation factor (SF Eu / Am ) of more than 600 for lanthanide and actinide elements, and exhibits excellent separation performance. The application provides a new perspective for in-depth understanding of lanthanide and actinide separation mechanism, and provides technical support for establishing an advanced spent nuclear fuel reprocessing system and realizing efficient utilization of minor actinide elements.

Nuclear waste, such as, but not limited to, spent nuclear fuel (SNF) assemblies or portions thereof, are placed within diecast molds, and then gravity fed molding occurs within those loaded diecast molds and around the SNF assemblies (or portions thereof) that are located within those diecast molds, using molten alloy(s) for filling the diecast molds, to form solid metal ingots upon sufficient cooling of the newly formed ingots. The molten alloy(s) may contain a copper alloy. The molten alloy(s) may also contain neutron absorbers and / or helium immobilizing materials. Each such formed ingot may entirely encapsulate a SNF assembly (or a portion thereof) within the resolidified alloy(s). The ingots may be formed into waste capsules. The ingots and / or the waste capsules may be landed in deeply located horizontal wellbores. The deeply located horizontal wellbores may be at least partially located within deeply located geologic formations.

As one way of preparing for global cooling, we will provide a nuclear reactor that requires less investment capital, is based on the premise that population density will decrease due to population decline, and it is unknown when, where, and what scale an earthquake will occur, and of course does not require a final disposal site, and can convince the media and local residents by reducing the amount of spent nuclear fuel from light water reactors. [Solution] A nuclear reactor in which a large number of allowable alloy-containing nuclear fuel rod assemblies 1, each consisting of a large number of allowable alloy-containing nuclear fuel rods made of heavy noble gas coolant and allowable enrichment plutonium alloy, are arranged in a square lattice pattern in the core of an existing BWR.

A nuclear fuel storage system comprises a fuel rack immersible in a fuel pool which comprises a baseplate and a cellular body extending from the baseplate. The body comprises plural cell walls arranged to define an array of upwardly open cells each configured to store a nuclear fuel assembly therein. A raised fuel assembly support ring may be disposed at the bottom of each cell on the baseplate to engage and support a fuel assembly. A neutron absorber insert disposed in at least one cell comprises a bottom end configured to frictionally engage the support ring to secure the neutron absorber insert therein. The absorber insert comprises resiliently deformable radial locking protrusions which frictionally engage an outward facing annular side surface of the support ring in one embodiment. The absorber insert may be retrofit into existing racks to restore reactivity control.

Disclosed is a neutron-absorbing composite material. The neutron-absorbing composite material comprises: an aluminum substrate; and reinforcing material powder dispersed in the aluminum substrate and having a boron carbide core and a gadolinium oxide shell covering the surface of the boron carbide core.

The present invention relates to a spent nuclear fuel storage container structured to reduce internal pressure, the storage container having at least one recess formed on the outer surface of a canister in which at least one spent nuclear fuel assembly is accommodated, and a support coupled to the inner surface of a cask, in which the canister is accommodated, and inserted in the recess, thereby reducing the internal pressure of the storage container.

Proposed is a cutting apparatus for a fuel basket accommodating spent nuclear fuel of a heavy water reactor, wherein the apparatus includes a base, a vertical support arranged on one side of the base; a turn table arranged to be reciprocated between one side and an opposite side of the base and be horizontally rotatable on the base; a horizontal support arranged to extend from an upper-end of the vertical support in a horizontal direction toward the turn table; a side-cutting means arranged on the vertical support protruding toward the turn table for cutting a side welding bead of the fuel basket mounted on the turn table; and an upper-cutting means arranged on the horizontal support protruding toward the turn table for cutting an upper welding bead of the fuel basket mounted on the turn table.

The application belongs to the technical field of extraction separation, and particularly relates to an OE-DAPhen ligand, a preparation method and application thereof. The application develops a novel DAPhen ligand through specific structure design from the design of a ligand molecular structure. The separation factor (SF) of the OE-DAPhen ligand for lanthanide and actinide elements is more than 400, and the OE-DAPhen ligand exhibits excellent separation performance. The application provides a new perspective for in-depth understanding of lanthanide and actinide separation mechanism, and provides technical support for establishing an advanced spent nuclear fuel reprocessing system and realizing efficient utilization of minor actinide elements. Eu / Am ).

The present application relates to a kind of volatile fission product trapping device and trapping method generated in spent fuel dry reprocessing, the device includes catalytic reaction device, dryer 1, fixed bed adsorption device 1, liquid adsorption device, dryer 2 and fixed bed adsorption device 2, by simulating effluent including radioactive tritium, carbon 14, iodine 129 and inert gas Kr and Xe, respectively with non-radioactive hydrogen, carbon dioxide, methyl iodine, Kr and Xe mixed gas as simulation gas source, by each component to each substance in mixed gas is classified and coordinated absorption, finally reach the index that the adsorption trapping efficiency of each effluent simulation is not less than 90%, by simulation can realize the high-efficiency adsorption trapping of the volatile radioactive effluent generated in spent nuclear fuel reprocessing process by the device of the present application.

A fuel rack for wet storage of nuclear fuel in a fuel pool comprises, in one embodiment, a base plate and a cellular body formed from slotted plates bonded to each other and stacked, coupled to the base plate. This cellular body comprises densely packed, upward-opening cells, each holding a nuclear fuel assembly. When the rack is submerged in water, open flax straps are formed between at least some of the water-filled cells, acting as neutron moderators to control the reactivity within the rack. In one embodiment, flax straps are interspersed between adjacent cells in a first direction along a first horizontal axis of the rack. However, flax straps are not interspersed between adjacent cells in a second direction perpendicular to a second horizontal axis. Other flax strap and cell arrangements are also provided. Tension elements penetrate some of the flax straps, and these tension elements compress the stack of plates to ensure stability.

Disclosed herein is a system comprising: (a) an experimentation cask having a receiving compartment defining an internal portion of the experimentation cask, wherein the receiving compartment is configured to receive a canister, wherein the canister is a vertical and / or horizontal spent fuel storage canister, (b) one or more sensing devices configured to non-destructively evaluate an internal and / or external state of the canister; wherein the one or more sensing devices are positioned within at least a portion of the internal portion of the experimentation cask, or at least a portion of an external portion of the experimentation cask; and wherein the experimentation cask provides radiation- and heat shielded. Also disclosed herein are methods for inspection of an internal and external integrity of the canister using the systems disclosed herein.

Underground nuclear installation (10), comprising: - a vertical shaft (12) having, at a lower end, a bottom (12c) and, at an upper end, an opening (12b), - at least one reactor building (26) housed in the shaft, - and which contains at least one nuclear reactor containment building (30) enclosed within said at least one reactor building (26), and / or at least one spent nuclear fuel pool housed in the shaft, - at least one protective slab (20) against external hazards which seals the opening (12b) of the shaft, extending in particular above said at least one reactor building, - one or more pieces of equipment or buildings (b1-b4) arranged on said at least one protective slab (20). Figure for the abbreviation: Fig. 3.

The present invention provides an automatic opening / closing type trolley for remote transfer of spent nuclear fuel in a repackaging facility, which has excellent shielding performance so as to minimize radiation due to radioactive materials and moreover to sufficiently carry out the remote transfer of spent nuclear fuel between respective working places in the repackaging facility, the automatic opening / closing type trolley comprising: a transfer cart which is moved on rails by a plurality of transport wheels driven by a driving means; and a storage shielding can comprising an upper shielding plate which is provided on the upper portion of the transfer cart and includes a docking cover that can be opened / closed to close the upper portion of the transfer cart, a fixed shielding plate and a rotating shielding plate for inserting a canister placed on a canister storage can into the side surface thereof and shielding the canister, and a vertical movement plate which moves the canister in the upward direction so as to be carried into the repackaging facility. Accordingly, convenience of use can be provided and conditions of securing high safety and handling the canister more conveniently can be achieved.

Provided is a spent nuclear fuel canister lid cutting system in dry environment which enables to safely transport the canister to which spent nuclear fuel is enclosed; to smoothly and easily lift and take out the canister to the cutting work space; to prevent the cutting work space from being exposed to radiation materials while cutting the canister lid; and to prevent a cover of a handling cask, which stores the canister, from being exposed to radiation materials. Thus, this system quickly and safely performs all working operations in order for superior work efficiency and high safety.

Device for reducing spent nuclear fuel, comprising a container for receiving nuclear fuel, wherein the device is configured to transmute long-lived radioisotopes of the nuclear fuel into radioisotopes having a significantly shorter half-life than the initial radioisotopes by interaction with fast neutrons.

Calorimeter for measuring the linear residual power of at least a portion or piece of a spent or new nuclear fuel rod. The invention essentially consists of a calorimeter whose core is delimited by a block of radioactive and thermal radiation-absorbing material surrounded by a housing of thermal insulation material that thermally isolates the core from the ambient environment. The block and the housing are each in two parts that can be separated for the easy and rapid insertion of a spent fuel rod. The calorimeter is instrumented with temperature sensors distributed along its length, which are inserted into the block and / or the housing to measure the linear residual power of the inserted fuel rod. Figure for the abstract: Fig. 2A