| Patent application number | Description | Published |
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| 20080260088 | APPARATUS AND METHOD FOR SUPPORTING FUEL ASSEMBLIES IN AN UNDERWATER ENVIRONMENT HAVING LATERAL ACCESS LOADING - A fuel rack for supporting radioactive fuel assemblies in an underwater (or other submerged) environment that reduces the depth required for the pool to effectuate the fuel rack loading procedure. The fuel rack is specially designed to afford lateral loading. In one embodiment, the fuel rack comprises a body structure comprising at least one substantially vertically oriented elongated cell for receiving a nuclear fuel assembly, the body having a top, a bottom and a first lateral side; at least one elongated slot in the first lateral side of the body structure that forms a passageway into the cell through which a vertically oriented fuel assembly can be loaded; and means for supporting a fuel assembly within the cell in a substantially vertical orientation. In another embodiment, the invention is a method of laterally loading a fuel rack that utilizes rotation of the fuel assembly to secure the fuel assembly within its designated cell. | 10-23-2008 |
| 20080265182 | APPARATUS FOR PROVIDING ADDITIONAL RADIATION SHIELDING TO A CONTAINER HOLDING RADIOACTIVE MATERIALS, AND METHOD OF USING THE SAME TO HANDLE AND/OR PROCESS RADIOACTIVE MATERIALS - A system, method and apparatus for providing additional radiation shielding to a container holding radioactive materials. The invention utilizes a sleeve-like structure that is slid over a container holding high level radioactive materials to add radiation shielding protection. Because the sleeve-like structure and container are non-unitary and slidably separable from one another, crane lifting capacity is not affected. In one aspect, the invention is an apparatus comprising: a tubular shell constructed of a gamma radiation absorbing material and having an inner surface that forms a cavity having an axis, the cavity having an open top end and an open bottom end; a plurality of spacers extending from the inner surface of the shell toward the axis of the cavity, the spacers extending a first height from the inner surface of the tubular shell; and one or more flange members located at or near the open top end of the cavity extending from the tubular shell toward the axis of the cavity, the flange member extending a second height from the inner surface of the shell, the second height being greater than the first height. | 10-30-2008 |
| 20080314570 | HEAT EXCHANGER APPARATUS FOR ACCOMMODATING THERMAL AND/OR PRESSURE TRANSIENTS - A heat exchanger apparatus for accommodating thermal and pressure transients. In one embodiment, the heat exchanger apparatus comprises: a first outer shell having an open end and an end wall; an inner shell having a cavity, the inner shell extending through the end wall of the first outer shell; a first tube sheet having a rim portion having a design feature for allowing the rim portion to act as an expansion joint; the outer rim portion of the first tube sheet connected to the first outer shell so as to enclose the open end of the first outer shell and form a first header cavity between the first outer shell and the inner shell; a clearance existing between the inner shell and the first tube sheet; a plurality of holes in the inner shell that form passageways between the first header cavity and the cavity of the inner shell; a first end cap connected to the rim portion of the first tube sheet so as to form a first plenum on the other side of the first tube sheet; a plurality of tubes located in the cavity of the inner shell and operably connected to the first tube sheet; an opening in the first outer shell for flowing a shell-side fluid into and/or out of the first header cavity; and an opening in the first end cap for flowing a tube-side fluid into and/or out of the first plenum. | 12-25-2008 |
| 20090069621 | METHOD OF REMOVING RADIOACTIVE MATERIALS FROM A SUBMERGED STATE AND/OR PREPARING SPENT NUCLEAR FUEL FOR DRY STORAGE - A system, apparatus and method of processing and/or removing radioactive materials from a body of water that utilizes the buoyancy of the water itself to minimize the load experienced by a crane and/or other lifting equipment. In one aspect, the invention is a method comprising: a) submerging a container having a top, a bottom, and a cavity in a body of water having a surface level, the cavity filling with water; b) positioning radioactive material within the cavity of the submerged container; c) raising the submerged container until the top of the containment apparatus is above the surface level of the body of water while a major portion of the container remains below the surface level of the body of water; and d) removing bulk water from the cavity while the top of the container remains above the surface level of the body of water and a portion of the container remains submerged. The bulk water can be added back into the cavity to add neutron shielding after the container is placed in a staging area and prior to personnel performing the desired operations to the container. As a result, gamma radiation and neutron shielding of the container can be maximized for any crane capacity. | 03-12-2009 |
| 20090158614 | SYSTEM AND METHOD FOR PREPARING A CONTAINER LOADED WITH WET RADIOACTIVE ELEMENTS FOR DRY STORAGE - A system and method for preparing a container holding high level radioactive waste for dry storage. In one aspect, the invention is a method of preparing a canister having a cavity loaded with wet radioactive elements for dry storage, the method comprising: (a) providing a gas circulation system comprising a condensing module, a desiccant module, a gas circulator module; (b) connecting the gas circulation system to the canister so as to form a hermetically sealed closed-loop path that includes the cavity; (c) filling the hermetically sealed closed-loop path with a non-reactive gas; (d) circulating the non-reactive gas through the hermetically sealed closed-loop path until the condensing module is no longer removing substantial amounts of water from the circulating non-reactive gas, wherein the desiccant module is sealed off from the hermetically sealed closed-loop path during step (d); and (e) adding the desiccant module to the hermetically sealed closed-loop path and continuing to circulate the non-reactive gas through the hermetically sealed closed-loop path, the desiccant module dehumidifying the circulating the non-reactive gas. In another aspect, a system and method is disclosed wherein the second phase of drying is performed by a vacuum module rather than the desiccant module to achieve the desired dryness level, the vacuum module being switched into the closed loop after the first phase of drying is completed. | 06-25-2009 |
| 20090159550 | SYSTEM AND METHOD FOR THE VENTILATED STORAGE OF HIGH LEVEL RADIOACTIVE WASTE IN A CLUSTERED ARRANGEMENT - A system for receiving and storing high level radioactive waste comprising: an enclosure comprising walls having inlet ventilation ducts, a roof comprising an array of holes, and a floor; an array of metal shells located in an internal space of the enclosure, the array of metal shells being co-axial with the array of holes in the roof so that containers holding high level radioactive waste can be lowered through the array of holes in the roof and into the array of metal shells; the array of metal shells acting as load bearing columns for the roof; and each of the metal shells comprising (i) an expansion joint for accommodating thermal expansion and/or contraction of the metal shells; and (ii) one or more holes at a bottom portion of the metal shell. | 06-25-2009 |
| 20090175404 | APPARATUS FOR SUPPORTING RADIOACTIVE FUEL ASSEMBLIES AND METHODS OF MANUFACTURING THE SAME - Apparatus for supporting radioactive fuel assemblies, such as spent nuclear fuel. In one aspect, the invention is an apparatus, which can be in the form of a fuel basket, fuel rack, or the like, in which hexagonal storage tubes are used not only for their internal cells but are also strategically patterned to create resultant cells with their outside surfaces. In another aspect, the invention is an apparatus having flux traps surrounding each cell wherein the size of the flux traps decrease with distance from the center of the storage grid. | 07-09-2009 |
| 20090198092 | METHOD AND APPARATUS FOR TRANSPORTING AND/OR STORING RADIOACTIVE MATERIALS HAVING A JACKET ADAPTED TO FACILITATE THERMOSIPHON FLUID FLOW - A system, method and apparatus for transporting and/or storing radioactive materials, such as spent nuclear fuel. In one aspect, the invention is a jacket apparatus that is filled with a neutron absorbing fluid and adapted to facilitate a cyclical thermosiphon flow of the neutron absorbing fluid within the jacket when the neutron absorbing fluid is subjected to heat emanating from the cavity. In other aspects, the invention can be a method and container incorporating and/or using the same. In another aspect, the invention can be a container comprising: a gamma radiation absorbing body forming a cavity for receiving radioactive material; a jacket surrounding the body thereby forming a gap between the body and the jacket for holding a neutron absorbing fluid; a baffle positioned in the gap in spaced relation to both the body and the jacket so as to divide the gap into an inner region and an outer region; a passageway at or near a bottom of the gap between the inner region and the outer region that allows the neutron absorbing fluid to flow from the outer region into the inner region; and a passageway at or near a top of the gap between the inner region and the outer region that allows the neutron absorbing fluid to flow from the inner region into the outer region. | 08-06-2009 |
| 20100150297 | MANIFOLD SYSTEM FOR THE VENTILATED STORAGE OF HIGH LEVEL WASTE AND A METHOD OF USING THE SAME TO STORE HIGH LEVEL WASTE IN A BELOW-GRADE ENVIRONMENT - A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming hermetically sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings. | 06-17-2010 |
| 20100232563 | APPARATUS AND METHOD FOR SUPPORTING FUEL ASSEMBLIES IN AN UNDERWATER ENVIRONMENT HAVING LATERAL ACCESS LOADING - A method of loading nuclear fuel assemblies into a fuel rack in an underwater (or other submerged) environment that reduces the depth required for the pool to effectuate the fuel rack loading procedure. In one embodiment, the method comprises submerging a nuclear fuel assembly having an axis and a horizontal cross-section in a pool; providing a fuel rack in the pool, the fuel rack comprising a body structure comprising at least one elongated cell, a top, a bottom, a first lateral side, at least one elongated slot in the first lateral side that forms a lateral passageway into the cell; positioning the fuel assembly laterally adjacent to the elongated slot of the fuel rack so that the axis of the fuel assembly is substantially aligned with the elongated slot; and translating the fuel assembly in a lateral direction through the elongated slot and into the cell. | 09-16-2010 |
| 20100272225 | CASK APPARATUS, SYSTEM AND METHOD FOR TRANSPORTING AND/OR STORING HIGH LEVEL WASTE - A thermally conductive cask for storing high level radioactive waste. In one aspect the invention can be a thermally conductive cask comprising: a gamma shielding cylindrical body forming a cavity for receiving high level radioactive waste and having an outer surface formed of a first material having a first thermal conductivity; a neutron shielding cylindrical body surrounding the gamma shielding cylindrical body and having a layer formed of a second material having a second thermal conductivity that is greater than the first thermal conductivity, the layer forming an inner surface of the neutron shielding cylindrical body; and wherein the layer is clad to the outer surface of the gamma shielding cylindrical body. | 10-28-2010 |
| 20100282448 | HEAT EXCHANGER APPARATUS FOR CONVERTING A SHELL-SIDE LIQUID INTO A VAPOR - An apparatus for generating steam within a heat exchanger. In one aspect, the invention can be a heat exchanger comprising: a shell having an inner surface forming a cavity, the shell comprising an inlet for introducing the shell-side liquid into the cavity and an outlet for allowing the vapor to exit the cavity; a tube bundle comprising a plurality of tubes for carrying a tube-side fluid located in the cavity and having a longitudinal axis; a shroud circumferentially surrounding the tube bundle and positioned between the tube bundle and the inner surface of the shell so that an annular space exists between the shroud and the inner surface; an opening in a bottom portion of the shroud that forms a passageway between the annular space and the tube bundle; and an opening in a top portion of the shroud that forms a passageway between the annular space and the tube bundle. | 11-11-2010 |
| 20100282451 | HEAT EXCHANGER APPARATUS - A method, system and/or apparatus for reducing the pressure drop in a heat exchanger. In one aspect, the invention can be a heat exchanger comprising: a shell forming a cavity, the shell comprising an inlet for introducing a shell-side fluid into the cavity and an outlet for allowing the shell-side fluid to exit the cavity; a tube bundle for carrying a tube-side fluid, the tube bundle located in the cavity along a longitudinal axis; at least one stabilizing plate positioned within the cavity and arranged in a substantially transverse orientation, the stabilizing plate comprising a lattice structure having openings, wherein tubes of the tube bundle extend through the openings; and wherein the openings of the lattice structure are sized and shaped so that the tubes contact the lattice structure and a portion of the openings remain unobstructed by the tubes, thereby allowing axial flow of the shell-side fluid through the stabilizing plate. | 11-11-2010 |
| 20100284506 | APPARATUS FOR STORING AND/OR TRANSPORTING HIGH LEVEL RADIOACTIVE WASTE, AND METHOD FOR MANUFACTURING THE SAME - A system for storing and/or transporting high level radioactive waste, and a method of manufacturing the same. In one aspect, the invention is a ventilated vertical overpack (“VVO”) having specially designed inlet ducts that refract radiation back into the storage cavity. A clear line-of-sight does not exist through the inlet ducts and, thus, the canister can be supported on the floor of the VVO. Also disclosed is a method of manufacturing a variable height VVO that falls within a regulatory license previously obtained for a shorter and taller version of the VVO. | 11-11-2010 |
| 20110033019 | SINGLE-PLATE NEUTRON ABSORBING APPARATUS AND METHOD OF MANUFACTURING THE SAME - A neutron absorbing insert for use in a fuel rack and method of manufacturing the same. In ones aspect, the invention is a neutron absorbing apparatus comprising: a plate structure having a first wall and a second wall that is non-coplanar to the first wall; the first and second walls being formed by a single panel of a metal matrix composite having neutron absorbing particulate reinforcement that is bent into the non-coplanar arrangement along a crease; and a plurality of spaced-apart holes formed into the single panel along the crease prior to bending. | 02-10-2011 |
| 20110150164 | METHOD OF TRANSFERRING HIGH LEVEL RADIONACTIVE MATERIALS, AND SYSTEM FOR THE SAME - An apparatus and method for inter-unit transfer of spent nuclear fuel. In one aspect, the invention is a method of transferring high level radioactive waste comprising: a) loading high level radioactive waste into a water-filled cavity of a canister body having an open top end at a first location; b) coupling a lid to the canister body to enclose the open top end; c) removing a volume of water from the cavity so that a water level of the water within the cavity is above a top end of the high level radioactive waste and a space exists between the water level and a bottom surface of the lid; d) hermetically sealing the cavity; and e) transferring the canister to a second location, the water level remaining above the top end of the high level radioactive waste during the transfer. | 06-23-2011 |
| 20110172484 | SYSTEM, METHOD AND APPARATUS FOR PROVIDING ADDITIONAL RADIATION SHIELDING TO HIGH LEVEL RADIOACTIVE MATERIALS - A system, method and apparatus for providing additional radiation shielding to a ventilated cask for holding high level radioactive materials. The invention utilizes a tubular shell that is ancillary to the ventilated cask that circumscribes the ventilated cask to add radiation shielding protection while improving heat removal by natural convective air flow. Because the tubular shell and cask are non-unitary and slidably separable from one another, crane lifting capacity is not affected. In one aspect, the invention is an apparatus for providing additional radiation shielding to a cask holding high level radioactive materials comprising: a tubular shell extending from an open bottom end to an open top end, the tubular shell having an inner surface that forms a cavity about a longitudinal axis; a plurality of primary apertures forming passageways through the tubular shell and circumferentially arranged in a spaced-apart manner about the tubular shell; a plurality of secondary apertures forming passageways through the tubular shell and circumferentially arranged in a spaced-apart manner about the tubular shell; and an annular seal coupled to the tubular shell and extending from the inner surface of the tubular shell; wherein the secondary apertures are located at an axial height above the annular seal and the primary apertures are located at an axial height below the annular seal. | 07-14-2011 |
| 20120142991 | APPARATUS FOR PROVIDING ADDITIONAL RADIATION SHIELDING TO A CONTAINER HOLDING RADIOACTIVE MATERIALS, AND METHOD OF USING THE SAME TO HANDLE AND/OR PROCESS RADIOACTIVE MATERIALS - The present invention relates to a system, method and apparatus for providing additional radiation shielding to a container holding radioactive materials. In one aspect, the invention is an apparatus that includes a tubular shell constructed of a gamma radiation absorbing material and having an inner surface that forms a cavity having an axis, the cavity having an open top end and an open bottom end; a plurality of spacers extending from the inner surface of the shell toward the axis of the cavity, the spacers extending a first height from the inner surface of the tubular shell; and one or more flange members located at or near the open top end of the cavity extending from the tubular shell toward the axis of the cavity, the flange member extending a second height from the inner surface of the shell, the second height being greater than the first height. | 06-07-2012 |
| 20120226088 | APPARATUS, SYSTEM AND METHOD FOR FACILITATING TRANSFER OF HIGH LEVEL RADIOACTIVE WASTE TO AND/OR FROM A POOL - A method, apparatus and system for the transferring a container for receiving high level radioactive waste into and/or out of a pool. The instant invention utilizes a specially designed container in order to make effective use of a stand placed within the pool. In one embodiment, the invention is a system for transferring high level radioactive waste comprising: a container for receiving high level radioactive waste, the container having a support structure; a stand comprising a cavity for receiving the container and an opening forming a passageway into the cavity; wherein the support structure is sized, shaped and/or arranged so that: (i) when the container is substantially vertically oriented in a first rotational position, the support structure can not pass through the opening due to contact between the support structure and the stand; and (ii) when the substantially vertically oriented container is rotated an angle about a vertical axis to a second rotational position, the support structure can pass through the opening in an unobstructed manner. | 09-06-2012 |
| 20120306172 | APPARATUS, SYSTEM AND METHOD FOR LOW PROFILE TRANSLATION OF HIGH LEVEL RADIOACTIVE WASTE CONTAINMENT STRUCTURE - An apparatus, system and method for handling and translating a spent nuclear fuel storage cask. The apparatus comprises a body for supporting the cask close to the ground so that the cask and the apparatus can pass underneath over head doors. The apparatus further comprises rollers for translating the cask, the rollers adapted to move between a retracted position and an extended position, wherein when the rollers are in the retracted position, the rollers do not contact a ground surface. The apparatus additionally supports the storage cask during spent nuclear fuel transfer procedures. | 12-06-2012 |
| 20120307956 | NUCLEAR REACTOR SYSTEM HAVING NATURAL CIRCULATION OF PRIMARY COOLANT - A nuclear reactor system that, in one embodiment, utilizes natural circulation (i.e., thermosiphon) to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heal exchange sub-system is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heal exchange sub-system that is used to vaporize a secondary coolant. In another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground. | 12-06-2012 |
| 20130070885 | CANISTER APPARATUS AND BASKET FOR TRANSPORTING, STORING AND/OR SUPPORTING SPENT NUCLEAR FUEL - A canister apparatus, basket apparatus and combinations thereof for transporting and/or storing high level radioactive waste, such as spent nuclear fuel In one embodiment, the invention can be a basket apparatus for supporting a plurality of spent nuclear fuel rods within a containment structure, the basket apparatus comprising a plurality of disk-like grates, each disk-like grate, having a plurality of ceils formed by a gridwork of beams; and means for supporting the disk-like grates in a spaced arrangement with respect to one another and so that the cells of the disk-like grates are aligned. | 03-21-2013 |
| 20140186144 | SYSTEM FOR LOW PROFILE TRANSLATION OF HIGH LEVEL RADIOACTIVE WASTE - An apparatus system and method for handling and translating high level radioactive waste. The apparatus comprises a body for supporting the cask close to the ground so that the cask and the apparatus can pass underneath over head doors. The apparatus further comprises rollers for translating the cask. The apparatus additionally supports the storage cask during spent nuclear fuel transfer procedures. | 07-03-2014 |
