33 results about "Nuclear waste storage" patented technology

A method comprising storing nuclear waste, including identifying a subterranean storage site location having a shale rock layer. The layer has an expected fluid overpressure in a range corresponding to greater than hydrostatic pressure to less than lithostatic pressure from overlying rock layers. Storing the waste can include forming a storage borehole, with an end segment of the storage borehole located within the layer and measuring the fluid pressure in the end segment of the storage borehole. If the measured fluid pressure in the end segment of the storage borehole is in the expected fluid overpressure range, forming a monitoring borehole in the layer with an end segment of each of the monitoring boreholes being in a vicinity of the end segment of the storage borehole and storing nuclear waste in the end segment of the storage borehole. A system for storing and monitoring nuclear waste is also described.

A nuclear waste cask in one embodiment includes an axially elongated cask body defining a longitudinally-extending opening forming an entrance to an internal storage cavity of the cask configured for holding radioactive nuclear waste materials. A closure lid detachably coupled to the cask body at the top opening seals the cavity. A cask locking mechanism includes a plurality of first locking protrusions spaced apart on the lid which are selectively interlockable with a plurality of second locking protrusions spaced apart on the cask body to lock the lid to the cask body. The first locking protrusions may be disposed on slideable locking bars moveable between locked and unlocked positions while the lid remains stationary on the cask body. Hydraulic or pneumatic actuators may be used to change position of the locking bars. The cask and lid may include other features such as impact absorbers and lifting elements.

A radioactive nuclear waste storage system includes a cask comprising a hermetically sealed internal cavity configured for holding the waste such as spent nuclear fuel submerged in an inventory of water. One or more pressure surge capacitors disposed inside the cask include a vacuum cavity evacuated to sub-atmospheric conditions prior to storage of fuel in the cask. At least one rupture disk seals a vacuum chamber inside each capacitor. Each rupture disk is designed and constructed to burst at a predetermined burst pressure level occurring inside the cask external to the capacitor. This allows excess cask pressure occurring during a high pressure excursion resulting from abnormal operating conditions to bleed into capacitor, thereby returning the pressure inside the cask to acceptable levels. In one embodiment, the capacitors are located in peripheral regions of the cask cavity adjacent to the circumferential wall of the cask body.

In one embodiment, a dry storage system for radioactive nuclear waste includes a canister having a tubular shell defining an interior cavity for storing nuclear waste, a lid sealably welded to one end of the shell and attached to An end closure for the second end of the housing. The end closure includes a base plate having an upwardly turned peripheral annular closure flange. In one embodiment, a circumferentially extending butt joint is formed between the closing flange and the second end of the housing, the butt joint being hermetically sealed by a full wall thickness butt weld. Various embodiments may further include a secondary pressure maintaining barrier that encloses the tank or selected portions thereof that are most susceptible to failure under certain conditions.

The invention belongs to the field of corrosion electrochemical testing, in particular to a metal material corrosion testing device and method in a high-pressure bentonite environment. The device includes a high-compacted bentonite bearing cabin and a compacted soil sheet located in the high-compacted bentonite loaded cabin, a connection and export system, a three-electrode system and a sealing plug, and the compacted soil sheet is connected to the high-compacted bentonite bearing cabin through the connection and export system , and lead out from the high-compacted bentonite bearing cabin through the connection export system, the compacted soil sheet is used to compact the bentonite carried in the high-compacted bentonite bearing cabin to prepare high-compacted bentonite, and the sealing plug is used for all The sealing of the high-compacted bentonite bearing compartment is described, and the three-electrode system is connected to an external electrochemical workstation through wires to conduct corrosion tests on metal materials. The invention can truly simulate the deep geological environment where the nuclear waste storage tank is buried, and obtain the corrosion degree of the storage tank material in each burial stage.

The invention provides a preparation method of an iron-based amorphous coating. Iron-based amorphous alloy powder is used as a raw material, and flame spraying is adopted to prepare the amorphous coating by activity combustion high speed fuel gas. The amorphous alloy powder contains the following elements and inevitable impurities: 16.0-19.0 of Cr; 1.0-3.0 of Mn; 4.0-9.0 of Mo; 1.0-3.0 of W; 13.0-17.0 of B; 2.5-4.5 of C; 1.0-3.5 of Si; and the balance of Fe. In the invention, preparation cost of the amorphous coating is reduced, the prepared iron-based amorphous coating and a substrate are bonded tightly, the structure is compact, the porosity and the oxygen content are very low, the iron-based amorphous coating has high hardness, excellent corrosion resistance and unique non-magnetism, thus the iron-based amorphous coating has a great application prospect in the field of ship, hydraulic, oil field development establishment, and nonmagnetic vessel hull; and because the content of B ishigher, the iron-based amorphous coating has favorable neutron absorption capacity, and can be used for a nuclear waste storage tank.

A screen panel for converting X-rays into light photons includes a rigid foam plate (2), a first layer (1) of composite material located on one face of the rigid foam plate (2) and a second layer (3) of composite material located on the other face of the rigid foam plate, parallel to the first face. The screen panel applies, for example, to medical radiology and to non-destructive testing of nuclear waste storage packages.

PURPOSE: By safeing and rapidly advancing the test process of the nuclear fuel the use after-edge flaw detection system improves the safety of the Atomic Electrical Power Plant equipment. CONSTITUTION: In the inside which canister is shut tightly with cover, the fuel is stored after use after use in the coke weighing hopper floor. The valve cone brush has the MC type pickup bolt for pulling up canister, and the pump and the valve sending the nuclide sample to the reservoir outside. The equipment panel is installed outside reservoir(100).