Induced nuclear reactions: processes – systems – and elements – Handling of fission reactor component structure within... – Fuel component
Reexamination Certificate
2003-01-14
2004-09-07
Behrend, Harvey E. (Department: 3641)
Induced nuclear reactions: processes, systems, and elements
Handling of fission reactor component structure within...
Fuel component
C376S260000, C376S272000, C212S270000, C414S146000, C414S800000
Reexamination Certificate
active
06788755
ABSTRACT:
BACKGROUND OF THE INVENTION
1. Field of the Invention
This invention relates to overhead hoists or crane systems that are used to transfer especially sensitive or critical loads such as nuclear waste.
2. Description of the Related Technology
A nuclear reactor operates by facilitating a controlled nuclear chain reaction in a reactor core. Typically, the nuclear reaction is fueled by an isotope of uranium, which is supplied to the reactor core in a plurality of elongated fuel rods, which are typically metallic structures that are packed with uranium pellets. Periodically, the fuel rods must be removed and replaced, and the spent nuclear fuel must be safely moved and then stored to avoid contamination of the environment. This spent nuclear fuel remains highly radioactive and is also capable of generating significant thermal energy.
Spent nuclear fuel is preferably stored in a water filled pool or cask. Immersion in water not only dissipates the thermal energy that is generated, it helps in the attenuation of the radiation that is emitted from the spent nuclear fuel. Accordingly, although dry storage and transportation systems are available, spent nuclear fuel is typically shipped from one location to another in sealed, shielded containers that are typically referred to as casks. In certain facilities, spent nuclear fuel is transferred from a first location to a storage cask by first packing the spent nuclear fuel within a canister, and placing the canister within a temporary transfer cask. The transfer cask is lifted by a crane assembly that, according to federal regulations must be designed so that it is single failure proof, and is positioned immediately above a more permanent storage cask. While the temporary transfer cask and the canister remain suspended above the storage cask by the crane assembly, a combination of human and robotic activity is used to tie down the transfer cask so as to immobilize the transfer cask against potentially destabilizing movement with respect to the storage cask. The crane assembly is then disconnected from the transfer cask, and is subsequently connected to the top of the canister. A gate assembly at the bottom of the transfer cask is opened, and the canister is lowered out of the transfer cask and into the storage cask by the crane assembly until it is completely positioned within the more permanent storage cask. The crane assembly must then be disconnected from the canister and reconnected to the temporary transfer cask. The tie-downs are removed, and the temporary transfer cask is withdrawn.
While the foregoing process has been performed innumerable times safely and in compliance with applicable regulations, it requires a substantial amount of time and skill to perform. In addition, to the extent that human labor is needed to immobilize the transfer cask and to undo the immobilization at the end of the procedure there is a risk that personnel may be subjected to potentially harmful radiation.
A need exists for an improved system and process for transferring spent nuclear fuel from a first location to a storage cask that is more time and material efficient than the conventional process described above, and that furthermore minimizes the probability that humans will be placed in a position where they may be exposed to potentially harmful radiation.
SUMMARY OF THE INVENTION
Accordingly, it is an object of the invention to provide an improved system and process for transferring spent nuclear fuel from a first location to a storage cask that is more time and material efficient than the conventional process described above, and that furthermore minimizes the probability that humans will be placed in a position where they may be exposed to potentially harmful radiation.
In order to achieve the above and other objects of the invention, an apparatus for moving a canister of spent nuclear fuel from a first location to a storage cask includes a first lifting mechanism for engaging and lifting a transfer cask in which a canister of spent nuclear fuel is temporarily positioned, the first lifting mechanism comprising a lower engagement assembly that is substantially without freedom of movement with respect to the transfer cask when the first lifting mechanism is engaged with said transfer cask; a second lifting mechanism, the second lifting mechanism being constructed and arranged to engage an upper portion of the canister of spent nuclear fuel, and wherein the second lifting mechanism is mounted on the lower engagement assembly of the first lifting mechanism, whereby the canister of spent nuclear fuel may be lowered with respect to the transfer cask while the first lifting mechanism remains engaged with the transfer cask.
According to a second aspect of the invention, an apparatus for moving a canister of spent nuclear fuel from a first location to a storage cask includes a trolley assembly; a first single failure proof lifting mechanism mounted for movement with the trolley assembly for engaging and lifting a transfer cask in which a canister of spent nuclear fuel is temporarily positioned; and a second single failure proof lifting mechanism mounted for movement with the trolley assembly for engaging and lifting the canister of spent nuclear fuel.
According to a third aspect of the invention, a method of retrofitting an overhead crane assembly at a nuclear facility into a mobile nuclear cask transfer assembly, includes steps of removing a preexisting trolley from at least one travel rail of an overhead crane assembly; installing a mobile nuclear cask transfer assembly onto the at least one travel rail, the mobile nuclear cask transfer assembly comprising a trolley assembly, a first single failure proof lifting mechanism mounted for movement with the trolley assembly for engaging and lifting a transfer cask in which a canister of spent nuclear fuel is temporarily positioned, and a second single failure proof lifting mechanism mounted for movement with the trolley assembly for engaging and lifting the canister of spent nuclear fuel.
These and various other advantages and features of novelty that characterize the invention are pointed out with particularity in the claims annexed hereto and forming a part hereof. However, for a better understanding of the invention, its advantages, and the objects obtained by its use, reference should be made to the drawings which form a further part hereof, and to the accompanying descriptive matter, in which there is illustrated and described a preferred embodiment of the invention.
REFERENCES:
patent: 3765549 (1973-10-01), Jones
patent: 4450134 (1984-05-01), Soot et al.
patent: 4610839 (1986-09-01), Geier et al.
patent: 4818878 (1989-04-01), Popp et al.
patent: 5319686 (1994-06-01), Pizzano et al.
patent: 5546436 (1996-08-01), Jones et al.
patent: 5841147 (1998-11-01), Steinke et al.
patent: 5898747 (1999-04-01), Singh
patent: 5998800 (1999-12-01), Geinitz et al.
patent: 6674828 (2004-01-01), Weber et al.
patent: 2003/0006207 (2003-01-01), Norheim
patent: 0046 983 (2000-02-01), None
patent: WO98/53460 (1998-11-01), None
Nuclear Engineering International, Oct. 1990, pp 105-107, Holt.*
Holtec Hightlights (A Summary Report to our Clients, Suppliers and Company Personnel); UST&D's Dry Storage Equipment Output Soars; Mar. 7, 2001; p. 1-11.
Holtec Highlights (A Summary Report to our Clients, Suppliers and Company Personnel); The Cask Transfer Facility and MPC Automated Welding System Demonstrations are a Success; Oct. 5, 2000; p. 1-3.
Norheim Oddvar
Weber David P.
American Crane & Equipment Corporation
Behrend Harvey E.
Knoble & Yoshida & Dunleavy LLC
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