The embodiments of the present disclosure generally relate to storage of hazardous radioactive materials and, more particularly, to dry storage, spent nuclear fuel casks for containing spent nuclear fuel or other hazardous radioactive material(s).
Spent nuclear fuel has historically been stored in deep reservoirs of water, called “spent fuel pools,” within nuclear power plants. This spent fuel storage technology is often termed “wet storage.” Spent fuel pools at reactors are reaching their spent fuel capacity limits, causing concerns about the need to shut down reactors because there is no more room for the spent fuel. Dry nuclear spent fuel storage technology (termed “dry storage”) is deployed throughout the world to expand the capabilities of nuclear power plants to discharge and store nuclear spent fuel external to a reactor's spent fuel pool, thereby extending the operating lives of the power plants.
There are two fundamental classes of technology used in dry spent fuel storage: (a) metal casks with final closure lids that are bolted closed at the power plants after loading with spent fuel, and (b) concrete storage casks containing metal canisters having canister final closure lids that are welded closed or sealed with mechanical methods at the power plants following spent fuel loading. This latter dry storage technology is referred to as “canister-based concrete spent fuel storage.” The concrete cask serves as an enclosure, or “overpack” that provides mechanical protection, heat removal features, and radiation shielding for the inner metal canister that encloses the radioactive materials. The use of this technology tends to have significant capital cost and other economic advantages over the use of metal cask technology for storage.
Embodiments of a thermal divider insert and method for a dry storage, spent nuclear fuel cask are disclosed. The thermal divider insert enables safe storage of the hazardous nuclear material when one or more air inlets have been fully or partially blocked to an extent that insufficient air flows into the air inlets and through the cask for adequate cooling of the hazardous nuclear material.
In one embodiment, among others, a cask comprises a metal canister having a top, bottom, and sidewall. The canister contains the hazardous nuclear material. A concrete overpack contains the metal canister with the hazardous nuclear material. The overpack has a top, bottom, and sidewall. The overpack has an inside surface that is spaced from an outer surface of the canister to create an annular region that permits flow of air between the surfaces for cooling the canister. One or more air inlets near the bottom of the overpack communicates air from an outside environment into the annular region. One or more outlet vents near the top of the overpack communicates air from the annular region to the outside environment. The thermal divider insert extends through a respective outlet vent and into the annular region and is designed to establish two separate and opposite air flows (i.e., inward air flow and outward air flow) through the respective vent and the annular region when the overpack air inlets have been blocked. When not blocked in normal operation, the two air flows both flow upwardly through the annular region and outwardly from the vent.
An embodiment of the thermal divider insert, among others, comprises (a) a planar horizontal radial plate and (b) a curved vertical plate extending from the radial plate, in order to establish the two separate and opposite air flows through the vent. The horizontal radial plate extends through the overpack outlet vent. The radial plate has a curvature along its inside and outside edges that corresponds to a curvature associated with the overpack outlet vent. The redial plate establishes a lower air flow region and an upper air flow region within the overpack outlet vent. When the one or more air inlets are blocked, then the lower air flow region enables inward air flow from the outside environment, and the upper air flow region enables outward air flow to the outside environment. When the one or more air inlets are not blocked, then the upper and lower air flow regions enable outward air flow to the outside environment.
As for the curved vertical plate, it extends downwardly at a right angle from the inside edge of the radial plate and has a curvature that corresponds to a curvature associated with the annular region. The curved vertical plate essentially establishes an outer annular region and an inner annular region. When the one or more inlets are blocked, the outer annular region enables inward air flow from the lower air flow region within the vent, and the inner annual region enables outward air flow to the upper air flow region of the vent. When the one or more air inlets are not blocked, the outer and inner annular regions enable upward air flow into the lower and upper air flow regions, respectfully, and then outwardly from the vent into the outside environment.
An embodiment of a method, among others, for safely storing hazardous nuclear material when one or more air inlets have been fully or partially blocked to an extent that insufficient air flows into the air inlets and through the cask for adequate cooling of the hazardous nuclear material, comprises the steps of: when the one or more air inlets are not blocked, enabling air flow into the air inlets, through the annular region, and then through and out of the one or more air vents; and when the air inlets are blocked, enabling air flow inwardly through the vents, then through the annular region, and then through and out of the vents. Furthermore, another embodiment is an apparatus having a means for performing each of the foregoing steps.
Other embodiments, apparatus, methods, features, and advantages of the present invention will be apparent to one with skill in the art upon examination of the following drawings and detailed description. It is intended that all such additional embodiments, apparatus, methods, features, and advantages be included within this disclosure, be within the scope of the present invention, and be protected by the accompanying claims.
Many aspects of the disclosure can be better understood with reference to the following drawings. The components in the drawings are not necessarily to scale, emphasis instead being placed upon clearly illustrating the principles of the present disclosure. Moreover, in the drawings, like reference numerals designate corresponding parts throughout the several views.
The overpack heat removal function associated with canister-based spent fuel storage relies upon natural circulation of air though the annular region 18 between the overpack vertical inner boundary and the vertical outer boundary of the metal canister 14 containing the radioactive material stored within the overpack 12. The cooler, more dense air 16 is introduced into the annular region 18 via the one of more inlets 17 where the air 16 absorbs heat which is being emitted from the radioactive material 15 in the canister 14, thereby becoming less dense and more buoyant. This increased buoyancy results in the less dense air 16 rising upward through the annular region 18 until the air 16 reaches the upper area where is exits the overpack 12 via the one or more outlet vents 22. The movement of air 16 through the annular region 18, as described, is a continuous process that results in the removal of heat from the radioactive material 15 stored within the canister 14, thereby ensuring that the temperature of the radioactive material 15 is maintained below a predetermined limit.
With reference to
The annular region 18 within the overpack 12 serves to act as a single column for air 16 to travel upward through as the air 16 absorbs heat, becoming less dense. With the blockage of the normal introduction path for cooler, less dense air 16 at the bottom of the overpack 12, this single column for air 16 becomes stagnated, thereby resulting in no means to create a thermally induced driving force based on different air densities.
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The thermal divider insert 26 acts as a thermal material shield during normal system operation (i.e., no flood condition present that blocks the overpack inlets 17). When the one or more air inlets are not blocked, then the outer and inner annular regions enable upward air flow into the lower and upper air flow regions, respectfully, of the vents 22, and then outward air flow from the vents 22 into the outside environment.
Upon blockage of the overpack inlets 17 due to flood waters (or any other postulate condition that prevents or otherwise inhibits the introduction of cooler, more dense air 16 into the overpack inlets 17), a thermal imbalance is initially encountered within the annular region 18, resulting initially in a stagnant air condition. Since the radioactive material 15 within the canister 14 will continue to emit heat, the air 16 closest to the canister 14 will continue to absorb heat, thereby creating a difference in density as compared to the air 16 closest to the inner surface of the overpack 12. As shown by the arrows in
Finally, it should be emphasized that the above-described embodiments of the present invention, particularly, any “preferred” embodiments, are merely possible nonlimiting examples of implementations, merely set forth for a clear understanding of the principles of the invention. Many variations and modifications may be made to the above-described embodiment(s) of the invention without departing substantially from the spirit and principles of the invention. All such modifications and variations are intended to be included herein within the scope of this disclosure and the present invention.
As an example, it is envisioned that other embodiments of the thermal divider insert 26 of