Patent application number | Description | Published |
20110286567 | SYSTEM AND METHOD FOR RECLAIMING ENERGY FROM HEAT EMANATING FROM SPENT NUCLEAR FUEL - The present invention provides a system and method for reclaiming energy from the heat emanating from spent nuclear fuel contained within a canister-based dry storage system. The inventive system and method provides continuous passive cooling of the loaded canisters by utilizing the chimney-effect and reclaims the energy from the air that is heated by the canisters. The inventive system and method, in one embodiment, is particularly suited to store the canisters below-grade, thereby utilizing the natural radiation shielding properties of the sub-grade while still facilitating passive air cooling of the canisters. In another embodiment, the invention focuses on a special arrangement of the spent nuclear fuel within the canisters so that spent nuclear fuel that is hotter than that which is typically allowed to be withdrawn from the spent fuel pools can be used in a dry-storage environment, thereby increasing the amount energy that can be reclaimed. | 11-24-2011 |
20120037632 | VENTILATED SYSTEM FOR STORING HIGH LEVEL RADIOACTIVE WASTE - A system for storing high level radioactive waste. In one embodiment, the invention can be a system comprising an overpack body extending along a vertical axis and having a cavity for storing high level radioactive waste, the cavity having an open top end and a floor; an overpack lid positioned atop the overpack body to enclose the open top end of the cavity; an air inlet vent for introducing cool air into the cavity, the air inlet vent comprising an annular air inlet plenum and an annular air inlet passageway, the annular air inlet plenum extending radially inward from an outer surface of the overpack body to the annular air inlet passageway, the annular air inlet passageway extending upward from the annular air inlet plenum to an opening in the floor, and an air outlet vent in the overpack lid for removing warmed air from the cavity. | 02-16-2012 |
20120294737 | AUTONOMOUS SELF-POWERED SYSTEM FOR REMOVING THERMAL ENERGY FROM POOLS OF LIQUID HEATED BY RADIOACTIVE MATERIALS, AND METHOD OF THE SAME - An autonomous self-powered system for cooling radioactive materials comprising: a pool of liquid; a closed-loop fluid circuit comprising a working fluid having a boiling temperature that is less than a boiling temperature of the liquid of the pool, the closed-loop fluid circuit comprising, in operable fluid coupling, an evaporative heat exchanger at least partially immersed in the liquid of the pool, a turbogenerator, and a condenser; one or more forced flow units operably coupled to the closed-loop fluid circuit to induce flow of the working fluid through the closed-loop fluid circuit; and the closed-loop fluid circuit converting thermal energy extracted from the liquid of the pool into electrical energy in accordance with the Rankine Cycle, the electrical energy powering the one or more forced flow units. | 11-22-2012 |
20140047733 | SYSTEM AND METHOD FOR PREPARING A CONTAINER LOADED WITH WET RADIOACTIVE ELEMENTS FOR DRY STORAGE - A method for preparing a cavity loaded with wet radioactive elements for dry storage, the method including: connecting a condensing module, a vacuum module, and a gas circulator module to the cavity so as to form a hermetically sealed closed-loop path that includes the cavity; filling the closed-loop path with a non-reactive gas; circulating the non-reactive gas through the closed-loop path until the condensing module is no longer removing substantial amounts of water from the circulating non-reactive gas, wherein the vacuum module is sealed off from the closed-loop path during the circulating; discontinuing the circulation of the non-reactive gas through the closed-loop path; fluidly coupling the vacuum module to the cavity and fluidly isolating the cavity and the vacuum module; and applying a vacuum pressure to the cavity via the vacuum module so as to create a sub-atmospheric pressure within the cavity. | 02-20-2014 |
20140105347 | APPARATUS FOR SUPPORTING RADIOACTIVE FUEL ASSEMBLIES AND METHODS OF MANUFACTURING THE SAME - An 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 polygonal storage tubes are used not only for their internal cells but are also strategically patterned to create resultant cells with their outside surfaces. | 04-17-2014 |
20140150994 | AIR-COOLED HEAT EXCHANGER AND SYSTEM AND METHOD OF USING THE SAME TO REMOVE WASTE THERMAL ENERGY FROM RADIOACTIVE MATERIALS - A system for removing thermal energy generated by radioactive materials is provided. The system comprises an air-cooled shell-and- tube heat exchanger, comprising a shell and plurality of heat exchange tubes arranged in a substantially vertical orientation within the shell, the heat exchange tubes comprising interior cavities that collectively form a tube-side fluid path, the shell forming a shell-side fluid path that extends from an air inlet of the shell to an air outlet of the shell, the air inlet at a lower elevation than the air outlet; a heat rejection closed-loop fluid circuit comprising the tube-side fluid path, a coolant fluid flowing through the heat rejection closed-loop fluid circuit, the heat rejection closed-loop fluid circuit thermally coupled to the radioactive materials; and the air-cooled shell-and-tube heat exchanger transferring thermal energy from the coolant fluid flowing through the tube-side fluid path to air flowing through the shell-side fluid path. | 06-05-2014 |
20140169515 | 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. | 06-19-2014 |
20140177776 | SYSTEMS AND METHODS FOR STORING SPENT NUCLEAR FUEL - Systems and methods for storing spent nuclear fuel below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: a shell forming a cavity for receiving a canister of spent nuclear fuel, at least a portion of the shell positioned below grade; and at least one inlet ventilation duct extending from an above grade inlet to a below grade outlet at or near a bottom of the cavity; the inlet ventilation duct connected to the shell so that the cavity is hermetically sealed to ingress of below grade fluids. In another aspect, the invention is a method comprising: providing a below grade hole; providing a system comprising a shell forming a cavity for receiving a canister of spent nuclear fuel, at least a portion of the shell positioned below grade, and at least one inlet ventilation duct extending from an inlet to an outlet at or near a bottom of the cavity, the inlet ventilation duct connected to the shell; positioning the apparatus in the hole so that the inlet of the inlet ventilation duct is above grade and the outlet of the inlet ventilation duct into the cavity is below grade; filling the hole with engineered fill; and lowering a spent fuel canister into the cavity. | 06-26-2014 |
20140219408 | CONTAINER AND SYSTEM FOR HANDLING DAMAGED NUCLEAR FUEL, AND METHOD OF MAKING THE SAME - A container and system for handling damaged nuclear fuel, and a method of making the same. In one embodiment, the invention is a damaged fuel container having a specially designed top cap that can be detachably coupled to the elongated tubular wall by simply translating the top cap into proper position within, the elongated tubular wall, wherein biased locking elements automatically lock the top cap to the elongated tubular wall. In another embodiment, the vent screens of the damaged fuel container are integrally formed rather than being separate components. In still other embodiments, the lower vent screens are arranged on an upstanding portion of the damaged fuel container. In an even further embodiment, the elongated tubular wall is formed by an extrusion process. | 08-07-2014 |
20140247916 | Method For Controlling Temperature Of A Portion Of A Radioactive Waste Storage System And For Implementing The Same - A system and method for storing radioactive waste, such as spent nuclear fuel, in one embodiment, the invention is a method of controlling temperature of a portion of a storage system comprising a container loaded with radioactive waste and a ventilated module in which the container is positioned, the ventilated module configured so that heat generated by the radioactive waste causes a natural convective flow of air through, a ventilation passageway of the ventilated module, the method comprising; throttling the natural convective flow of the air through the ventilated module to alter a heat rejection rate of the storage system to compensate for a decreasing heat generation rate of the radioactive waste to maintain the portion of the storage system within a predetermined temperature range. | 09-04-2014 |
20140316182 | 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. | 10-23-2014 |
20140317952 | METHOD AND APPARATUS FOR PREPARING SPENT NUCLEAR FUEL FOR DRY STORAGE - A system and method for drying cavities containing spent nuclear fuel is devised. The invention utilizes a non-intrusive procedure that is based on monitoring the dew point temperature of a non-reactive gas that is circulated through the cavity, in one aspect, the invention is a system for drying a cavity loaded with spent nuclear fuel comprising: a canister forming the cavity, the cavity having an inlet and an outlet; a source of non-reactive gas; means for flowing the non-reactive gas from the source of non-reactive gas through the cavity; and means for repetitively measuring the dew point temperature of the non-reactive gas exiting, the cavity, | 10-30-2014 |
20140321596 | PASSIVE REACTOR COOLING SYSTEM - A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger. | 10-30-2014 |
20140321597 | LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM - A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink. | 10-30-2014 |
20140329455 | METHOD FOR STORING RADIOACTIVE WASTE, AND SYSTEM FOR IMPLEMENTING THE SAME - A system and method for storing high level radioactive waste, such as spent nuclear fuel. In one embodiment, the invention is a method of storing high level radioactive waste comprising: a) positioning a metal canister containing high level radioactive waste having a heat generation rate in a storage cavity of a ventilated system comprising a cask body, a cask lid positioned atop the cask body, at least one outlet duct extending from a top of the storage cavity to an ambient atmosphere, and a plurality of inlet ducts, each of the inlet ducts extending from a first opening in the outer surface of the cask body to a second opening in the inner surface of the cask, body; and b) sealing selected ones of the plurality of inlet ducts over time as a function of a decay of the heat generation rate to maintain more a predetermined percentage of a vertical height of the metal canister above a predetermined threshold temperature. | 11-06-2014 |
20140341330 | 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. | 11-20-2014 |
20150027679 | FINNED TUBE ASSEMBLIES FOR HEAT EXCHANGERS - A finned tube assembly for an air cooled condenser and method for forming the same. The finned tube assembly comprises a flow conduit in the form of a bare steel tube and at least one set of fins bonded directly to the tube. In one embodiment, the tube has a non-circular cross section and the fins have a serpentine configuration. An oil based carrier and flux mixture is used in one embodiment to braze the fins onto the bare tubes, A braze filler metal may he introduced proximate to the bonding site by several different delivery mechanism. The braze filler metal may be aluminum or aluminum silicon. The finned tubes assemblies are combined in tube bundles and assembled to form an air cooled condenser which may be used in power generation, station, and other applications. | 01-29-2015 |
20150071398 | SYSTEM AND METHOD OF STORING AND/OR TRANSFERRING HIGH LEVEL RADIOACTIVE WASTE - A module for storing high level radioactive waste includes an outer shell, having a hermetically closed bottom end, and an inner shell forming a cavity and being positioned inside the outer shell to form a space therebetween. At least one divider extends from the top to the bottom of the inner shell to create a plurality of inlet passageways through the space, each inlet passageway connecting to a bottom portion of the cavity. A plurality of inlet ducts each connect at least one of the inlet passageways and ambient atmosphere, and each includes an inlet duct cover affixed atop a surrounding inlet wall, the inlet wall being peripherally perforated. A removable lid is positioned atop the inner shell and has at least one outlet passageway connecting the cavity and the ambient atmosphere, the lid and the top of the inner shell being configured to form a hermetic seal therebetween. | 03-12-2015 |
20150076161 | VENTILATED SYSTEM FOR STORING HIGH LEVEL RADIOACTIVE WASTE - A system for storing high level radioactive waste. In one embodiment, the invention can be a system comprising an overpack body extending along a vertical axis and having a cavity for storing high level radioactive waste, the cavity having an open top end and a floor; an overpack lid positioned atop the overpack body to enclose the open top end of the cavity; an air inlet vent for introducing cool air into the cavity, the air inlet vent extending from an opening in an outer surface of the overpack body to an opening in the floor; and an air outlet vent in the overpack lid for removing warmed air from the cavity. | 03-19-2015 |
20150085965 | SPACE SAVER FLANGED JOINT FOR A NUCLEAR REACTOR VESSEL - A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity. | 03-26-2015 |
20150110236 | NUCLEAR STEAM SUPPLY SYSTEM - A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel. | 04-23-2015 |
20150187449 | SYSTEM AND METHOD FOR RECLAIMING ENERGY FROM HEAT EMANATING FROM SPENT NUCLEAR FUEL - The present invention provides a system and method for reclaiming energy from the heat emanating from spent nuclear fuel contained within a canister-based dry storage system. The inventive system and method provides continuous passive cooling of the loaded canisters by utilizing the chimney-effect and reclaims the energy from the air that is heated by the canisters. The inventive system and method, in one embodiment, is particularly suited to store the canisters below-grade, thereby utilizing the natural radiation shielding properties of the sub-grade while still facilitating passive air cooling of the canisters. In another embodiment, the invention focuses on a special arrangement of the spent nuclear fuel within the canisters so that spent nuclear fuel that is hotter than that which is typically allowed to be withdrawn from the spent fuel pools can be used in a dry-storage environment, thereby increasing the amount energy that can be reclaimed. | 07-02-2015 |
20150221402 | STORAGE SYSTEM FOR NUCLEAR FUEL - A high-density fuel rack and system for wet storage of radio-active fuel, assemblies, such as spent nuclear fuel. The fuel rack includes a grid array of elongated cells each con figured for holding a fuel assembly, in one aspect, the cells are formed by a plurality of longitudinally-extending tubes having a rectilinear polygonal cross-sectional configuration. In one embodiment, the cells may have a cross-sectional shape of unequal width and length. The tubes may be variously arranged in contiguous or spaced apart configurations for non-flux trap and flux trap type racks, respectively. | 08-06-2015 |
20150243385 | PASSIVELY-COOLED SPENT NUCLEAR FUEL POOL SYSTEM AND METHOD THEREFOR - A passively-cooled spent nuclear fuel pool system and method therefor. In one embodiment, the invention can be a passively-cooled spent nuclear fuel pool system comprising: a spent nuclear fuel pool comprising a body of liquid water having a surface level, at least one spent nuclear fuel rod submerged in the body of liquid water that heats the body of liquid water; a lid covering the spent nuclear fuel pool to create a hermetically sealed vapor space between the surface level of the body of liquid water and the lid; and a passive heat exchange sub-system fluidly coupled to the vapor space, the passive heat exchange sub-system configured to: (1) receive water vapor from the vapor space; (2) remove thermal energy from the received water vapor, thereby condensing the water vapor to form a condensed water vapor; and (3) return the condensed water vapor to the body of liquid water. | 08-27-2015 |
20150243388 | NUCLEAR STEAM SUPPLY SYSTEM - A nuclear steam supply system having a start-up sub-system for heating a primary coolant. In one embodiment, the invention can be a nuclear steam supply system comprising: a reactor vessel having an internal cavity, a reactor core comprising nuclear fuel disposed within the internal cavity; a steam generating vessel fluidly coupled to the reactor vessel; a primary coolant loop formed within the reactor vessel and the steam generating vessel, a primary coolant in the primary coolant loop; and a start-up sub-system fluidly coupled to the primary coolant loop, the start-up sub-system configured to: (1) receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant into the primary coolant loop. | 08-27-2015 |
20150243391 | SYSTEM, METHOD AND APPARATUS FOR PROVIDING ADDITIONAL RADIATION SHIELDING TO HIGH LEVEL RADIOACTIVE MATERIALS - A system, method and apparatus for providing radiation shielding to a ventilated cask for holding high level radioactive materials. In one aspect, the tubular shell is positioned to circumferentially surround the cask so that an annular gap exists between the tubular shell and a sidewall of the cask. The tubular shell includes a first air flow inlet and a second air flow inlet. An air flow barrier is placed within the annular gap, separating the annular gap into a first chamber and a second chamber. A first air flow into the first air flow inlet passes through the first chamber and into the inlet vent of the cask, a second air flow into the second air flow inlet passes through the second chamber and to an opening at the top end of the tubular shell, and the air flow barrier prohibits cross-flow of air between the first and second chambers. | 08-27-2015 |
20150255181 | NUCLEAR POWER GENERATION SYSTEM - A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop. This creates a temperature differential between the primary and secondary coolant sufficient to create natural thermally induced convective circulation of the primary coolant | 09-10-2015 |
20150287483 | PASSIVELY-COOLED SPENT NUCLEAR FUEL POOL SYSTEM - A passively-cooled spent nuclear fuel pool system in one embodiment includes a containment vessel comprising a thermally conductive shell and an annular reservoir surrounding the shell that holds a liquid coolant forming a heat sink. A spent fuel pool is disposed inside the containment vessel and includes a body of water in contact with a first peripheral sidewall of the fuel pool. At least one spent nuclear fuel rod submerged in the body of water heats the water. The first peripheral sidewall of the spent fuel pool is formed by a portion of the shell of the containment vessel adjacent to the fuel pool, thereby defining a shared common heat transfer wall. The heat transfer wall operates to transfer heat from the body of water in the spent fuel pool to the heat sink to cool the body of water. The heat transfer wall comprises metal in one embodiment. | 10-08-2015 |
20150287489 | NEUTRON SHIELDING RING, APPARATUS AND METHOD USING THE SAME FOR STORING HIGH LEVEL RADIOACTIVE WASTE - An apparatus, system and method for storing high level radioactive waste. In one aspect, the invention is a specially designed ring structure for providing neutron and gamma radiation shielding for high level radioactive materials that produce residual heat. A plurality of the ring structures may be arranged in a stacked assembly that completely surrounds an internal containment boundary. Collars may be provided at the ring-to-ring interfaces. The ring structures may have voids which are configured for receiving neutron absorbing material that completely surrounds the containment boundary. | 10-08-2015 |
20150306711 | BRAZING COMPOSITIONS AND USES THEREOF - Described herein are compositions for use in the brazing of metal substrates, methods of making and using these compositions are also described herein. Heat exchangers often have a distributor tube whose external surface is provided with cooling fins. The distributor tube is typically a steel tube coated with a metal having good heat conduction, such as aluminum. The cooling fins themselves also generally comprise aluminum because of its good heat conductivity and low weight. | 10-29-2015 |
20150310947 | SYSTEM AND METHOD FOR MINIMIZING MOVEMENT OF NUCLEAR FUEL RACKS DURING A SEISMIC EVENT - A system for storing nuclear fuel, the system including a storage rack and a bearing pad. The storage rack includes an array of cells, each cell configured to receive and store nuclear fuel rods, a base plate configured to support the array of cells, and a support structure configured to support the base plate and to allow cooling fluid to circulate under and up through apertures in the base plate. The bearing pad is coupled to the support structure and is configured to limit lateral movement of the storage rack independent from lateral movement of the bearing pad. The base plate defines a base plate profile in a horizontal plane of the base plate, and the bearing pad defines a bearing pad profile in the horizontal plane of the base plate, wherein the bearing pad profile extends outside of the base plate profile. | 10-29-2015 |
20150325318 | FAIL-SAFE CONTROL ROD DRIVE SYSTEM FOR NUCLEAR REACTOR - A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with, the CRDM and in position. | 11-12-2015 |
20150336204 | JOINING PROCESS FOR NEUTRON ABSORBING MATERIALS - A method and associated system for joining workpieces formed of neutron absorbing materials. The method includes positioning first and second workpieces together to form a joint, heating the first and second workpieces at the joint to a plastic condition, intermingling plastic material from the first and second workpieces together at the joint, and cooling the intermingled plastic material to a solid state forming a welded fusion zone comprised of material from the first and second metal matrix composite workpieces. The workpiece material at the joint is not melted by the heating. The heating may be perforated by frictionally heating the materials with a rotary tool, in one non-limiting embodiment, the neutron absorbing workpieces may be formed of metal matrix composites comprising aluminum or aluminum alloy and boron carbide. | 11-26-2015 |
20150340112 | RADIOACTIVE MATERIAL STORAGE CANISTER AND METHOD FOR SEALING SAME - A canister for storing radioactive materials includes a base plate, side wall and a top plate. The top plate includes a top surface with a top edge having a bevel, and with a channel set in from the top edge. The top plate is sealed to the sidewall by a weld formed between the beveled top edge and the top of the side wail. The base plate is sealed to a bottom of the sidewall, so that a sealed vessel is formed. | 11-26-2015 |
20150357066 | HIGH-DENSITY SUBTERRANEAN STORAGE SYSTEM FOR NUCLEAR FUEL AND RADIOACTIVE WASTE - An underground ventilated system for storing nuclear waste materials. The system includes a storage module having an outer shell defining an internal cavity and an inner shell. A majority of the height of the outer shell may be disposed below grade. The outer shell may include a hermetically sealed bottom. First and second canisters are positioned in lower and upper portions within the cavity respectively in vertically stacked relationship. A centering and spacing ring assembly is interspersed between the first and second canisters to transfer the weight of the upper second canister to the lower first canister. The assembly may include centering lugs which laterally restrain the first and second canisters in case of a seismic event. A natural convection driven ventilated air system cools the canisters to remove residual decay heat to the atmosphere. In one non-limiting embodiment, the shells are made of steel. | 12-10-2015 |
20150360332 | VERTICAL BUNDLE AIR COOLED HEAT EXCHANGER, METHOD OF MANUFACTURING THE SAME, AND POWER GENERATION PLANT IMPLEMENTING THE SAME - A vertical bundle air-cooled heat exchanger, In one embodiment, the invention can be a vertical bundle air-cooled condenser comprising: at least one tube bundle assembly comprising; a tube bundle comprising a plurality of finned tubes arranged in a substantially vertical and side-by-side orientation, each of the plurality of finned tubes comprising a cavity; a top header pipe comprising an inlet header cavity operably coupled to a source of steam; a bottom header pipe comprising an outlet header cavity for collecting condensate; top ends of the plurality of finned tubes coupled to the top header pipe and the bottom ends of the plurality of finned tubes coupled to the bottom header pipe; and, a shell having an open, top end and open bottom end, the at least one tube bundle assembly positioned within the shell. | 12-17-2015 |
20160005501 | VENTILATED TRANSFER CASK WITH LIFTING FEATURE - An apparatus for transferring spent nuclear fuel in the form of a cask having a cylindrical inner shell forming a cavity configured to receive a canister containing spent nuclear fuel, an intermediate shell disposed concentrically around and spaced apart from the inner shell and an outer shell disposed concentrically around and spaced apart from the intermediate shell. A bottom flange is affixed to bottoms of each of the shells, and a bottom lid is removably affixed to the bottom flange. A top flange is affixed to tops of each of the shells, and a top lid is seated on the top flange. An annulus for air flow may be formed between the inner shell and the canister; the bottom lid may include an impact zone including impact absorbing structure; and the top flange may have integrally formed trunnions. | 01-07-2016 |
20160027538 | APPARATUS FOR SUPPORTING SPENT NUCLEAR FUEL - A fuel rack apparatus includes: a base plate having an upper surface and a lower surface; and a plurality of storage tubes coupled to and extending upward from the upper surface of the base plate, the storage tubes arranged in a side-by-side arrangement to form an array of the storage tubes. Each of the storage tubes extend along a longitudinal axis and include: an outer tube having an inner surface defining an inner cavity; and an inner plate-assemblage positioned within the outer tube that divides the inner cavity into a plurality of interior flux trap chambers and a fuel storage cell. | 01-28-2016 |
20160035444 | ULTRA-SAFE WET STORAGE FACILITY FOR NUCLEAR FUEL - An autonomous facility for storing spent nuclear fuel in one embodiment includes a building forming an enclosed interior space containing a water-filled spent fuel pool. The pool includes fuel racks containing spent fuel assemblies which heat the water via radioactive decay. A passive cooling system includes a submerged heat exchanger in the pool and an air cooled heat exchanger located in ambient air outside the building at a higher elevation than the pool heat exchanger. A heat transfer working fluid circulates in a closed flow loop between the heat exchangers via unpumped natural gravity driven flow to cool the fuel pool. The air cooled heat exchanger may be enclosed in a concrete reinforced silo adjoining the building for impact protection. The building may include a cask pit formed integrally with the pool to allow fuel assembles to be removed from a transport cask and loaded into the fuel rack underwater. | 02-04-2016 |
20160099085 | ENVIRONMENTALLY SUQUESTERED SPENT FUEL POOL - An environmentally sequestered nuclear spent fuel pool in one embodiment includes sidewalls and a base slab that confine a water impoundment. The pool includes fuel racks containing spent fuel assemblies which heat the water via radioactive decay. A dual liner system enclosing the pool forms an impervious barrier providing redundant provisions for preventing leakage of contaminated pool water into the environment. An interstitial space is formed between the liners which may be maintained at sub-atmospheric pressures by a vacuum pump system that evacuates the space. By maintaining the pressure in the space at a negative pressure with corresponding boiling point less than the temperature of the pool water, any leakage through the inner-most liner into the interstitial space will vaporize and be extracted via the pump for signaling a potential leak in the liner system. | 04-07-2016 |
20160118152 | SYSTEM AND METHOD FOR PREPARING A CONTAINER LOADED WITH WET RADIOACTIVE ELEMENTS FOR DRY STORAGE - A system for preparing a container holding radioactive waste for dry storage. In one aspect, the invention can be a system for preparing a container having a cavity loaded with radioactive elements for dry storage, the system comprising: a gas circulation system comprising a condenser module, a desiccant module, and a gas circulator module; the gas circulation system configured to form a hermetically sealed closed-loop path when operably connected to the cavity of the container; and means for adding and removing the desiccant module as part of the hermetically sealed closed-loop path. | 04-28-2016 |
Patent application number | Description | Published |
20090085286 | MECHANICAL BALL PROJECTION GAME DEVICES - Mechanical ball projection game devices, including game devices having mechanically-actuated ball loader assemblies, and game devices to release a tangible prize upon game balls reaching or entering a prize location to release a tangible prize upon game balls reaching or entering a prize location. Game devices disclosed herein include prize inserts that may be configured to receive one or more of paper currency, gift cards, financial transaction cards, greeting cards, toys, and candy. Mechanical ball projection game devices may include user-controllable features to redirect ball travel, features to guide and obstruct ball travel, and ball projector devices. | 04-02-2009 |
20100083509 | Folding scissors - A pair of scissors which has ring portions foldable from a position 180° with respect to one another to a position where the ring portions are rotated between 90° each and are substantially parallel and adjacent with one another. | 04-08-2010 |
20110034779 | Method for performing minimally invasive surgury - Pedicle screw apparatuses each including a pedicle screw assembly and an attached pedicle screw extender are placed in a true percutaneous manner, thereby overcoming issues resulting from placing pedicle screw assemblies through a retractor. Thus, a retractor can advantageously be built off of the pedicle screw apparatuses, thereby allowing visualization of the spine anatomy directly. Furthermore, such a method for performing surgery ensures ideal placement of the retractor for additional procedures that are often required such as, for example, decompression, interbody device placement, etc. | 02-10-2011 |
20110034780 | Blade body for use with a surgical retractor - A blade system configured for use with a surgical retractor comprising a blade body and a blade body surround. The blade body includes a retractor attachment structure engagable with a blade body mounting structure of the surgical retractor. The retractor attachment structure is configured for allowing the blade body to be independently pivotable about and translatable along the blade body mounting structure. The blade body surround includes a slot within a sidewall thereof. The blade body surround and the blade body are jointly configured to form a generally cylindrical-shaped structure when the blade body is in a seated position within the slot. | 02-10-2011 |
20110034781 | Retractor component system and method of using same - A blade assembly has a blade body and a blade body surround. A retractor attachment structure is attached to the blade body at the first end portion thereof extending from an exterior surface thereof. The retractor attachment structure is configured for having one of the blade body mounting structures of the retractor engaged therewith in a manner whereby the blade body is independently pivotable about and translatable along the blade body mounting structure. An alignment member protrudes from an interior surface of the blade body adjacent its first end portion. A slot extends through the blade body at its first end portion. The blade body surround and the blade body jointly form a generally cylindrical-shaped structure when the blade body is in a seated position within the slot. The cylindrical structure defines a central passage extending between the first and second end portions of blade body surround. | 02-10-2011 |
20110202094 | TRANS-POLYAXIAL SCREW - An orthopedic screw, including a threaded shaft defining a longitudinal axis; a head defining a region able to receive at least a portion of a prosthesis, the head being coupled to the shaft such that the head is movably offset from the longitudinal axis in a direction substantially perpendicular to the longitudinal axis; and a spacing element positionable within the head, the spacing element defining a first alignment marker positionable adjacent a second alignment marker defined by the head. | 08-18-2011 |
20110257685 | PRE-STRESSED SPINAL STABILIZATION SYSTEM - A spinal stabilization system, including a spinal implant having an elongate polymer body; a wire embedded in the body, the wire straining the polymer body; and a mounting element coupled to the elongate polymer body to facilitate engagement of the body to a spinal segment; and an orthopedic anchor having a threaded shaft; a head coupled to the threaded shaft, the head defining a cavity therein; a prosthesis coupling element at least partially disposed in the cavity and movable with respect to the head; and at least one asymmetrical ring circumscribing a portion of the prosthesis coupling element. | 10-20-2011 |
20120165613 | Retractor Component System And Method Comprising Same - A blade assembly has a blade body and a blade body surround. A retractor attachment structure is attached to the blade body at the first end portion thereof extending from an exterior surface thereof. The retractor attachment structure is configured for having one of the blade body mounting structures of the retractor engaged therewith in a manner whereby the blade body is independently pivotable about and translatable along the blade body mounting structure. An alignment member protrudes from an interior surface of the blade body adjacent its first end portion. A slot extends through the blade body at its first end portion. The blade body surround and the blade body jointly form a generally cylindrical-shaped structure when the blade body is in a seated position within the slot. The cylindrical structure defines a central passage extending between the first and second end portions of blade body surround. | 06-28-2012 |
20120172669 | Retractor Component System And Method Comprising Same - A blade assembly has a blade body and a blade body surround. A retractor attachment structure is attached to the blade body at the first end portion thereof extending from an exterior surface thereof. The retractor attachment structure is configured for having one of the blade body mounting structures of the retractor engaged therewith in a manner whereby the blade body is independently pivotable about and translatable along the blade body mounting structure. An alignment member protrudes from an interior surface of the blade body adjacent its first end portion. A slot extends through the blade body at its first end portion. The blade body surround and the blade body jointly form a generally cylindrical-shaped structure when the blade body is in a seated position within the slot. The cylindrical structure defines a central passage extending between the first and second end portions of blade body surround. | 07-05-2012 |
20120190935 | Retractor Component System And Method Comprising Same - A blade assembly has a blade body and a blade body surround. A retractor attachment structure is attached to the blade body at the first end portion thereof extending from an exterior surface thereof. The retractor attachment structure is configured for having one of the blade body mounting structures of the retractor engaged therewith in a manner whereby the blade body is independently pivotable about and translatable along the blade body mounting structure. An alignment member protrudes from an interior surface of the blade body adjacent its first end portion. A slot extends through the blade body at its first end portion. The blade body surround and the blade body jointly form a generally cylindrical-shaped structure when the blade body is in a seated position within the slot. The cylindrical structure defines a central passage extending between the first and second end portions of blade body surround. | 07-26-2012 |
20120197300 | Method For Performing Minimally Invasive Surgery - Pedicle screw apparatuses each including a pedicle screw assembly and an attached pedicle screw extender are placed in a true percutaneous manner, thereby overcoming issues resulting from placing pedicle screw assemblies through a retractor. Thus, a retractor can advantageously be built off of the pedicle screw apparatuses, thereby allowing visualization of the spine anatomy directly. Furthermore, such a method for performing surgery ensures ideal placement of the retractor for additional procedures that are often required such as, for example, decompression, interbody device placement, etc. | 08-02-2012 |
20130123859 | CERVICAL SPINAL SYSTEM - An orthopedic fixation system, including a tissue anchor including a first instrument engagement feature and a second instrument engagement feature; a first tool engageable with the first instrument engagement feature, and a second tool engageable with the second instrument engagement feature, where the first and second tools are engageable simultaneously with the tissue anchor. | 05-16-2013 |
20130123921 | BIOLOGIC INJECTION SYSTEM - A medical compound delivery device, including an elongated compound delivery conduit; a housing attached to the delivery conduit; a dispensing element movably positioned within the housing; an actuation element coupled to the housing, the actuation element operable to selectively move the dispensing element from the housing into the delivery conduit in discrete length increments; and a pressure limiting element configured to limit movement of the dispensing element when a pressure in the delivery conduit exceeds a predetermined threshold pressure. | 05-16-2013 |
20140336764 | EXPANDABLE SPINAL FUSION CAGE - A device, system, and method for performing a spinal procedure. The device includes first and second shape-memory outer platforms, the outer platforms expanding at a temperature greater than the transformative temperature, a core member having first and second expansion bodies and first and second wedge members, the first expansion body being coupled to the first outer platform and the second expansion body being coupled to the second outer platform, and a screw rotatably disposed within the core member, the screw passing through at least a portion of each of the first and second wedge members. Rotation of the screw causes the first and second wedge members to move toward each other and the first and second expansion bodies to move away from each other. Thus, reaching a transformation temperature and rotating the screw expands the device to come in contact with and anchored against both of the adjacent vertebrae. | 11-13-2014 |
20140343608 | EXPANSION INTERSPINOUS FIXATION DEVICE AND METHOD - A device and method for performing interspinous fixation or spinal fusion is provided. The device may generally include a first plate and a second plate, each having an adjustable length, and a mechanical actuator for increasing or reducing the length of the plates and, correspondingly, the device. Operation of the mechanical actuator causes first and second inner expansion portions of each plate to simultaneously slide on an outer fixed portion of the plate, to increase or decrease (depending on the direction of operation of the mechanical actuator) the separation between the first and second inner expansion portions, and thus, lengthen or shorten the plates and device. | 11-20-2014 |