Abstract: The present invention relates to passive cooling systems and methods for cooling a spent fuel pool in a nuclear power plant in the absence of onsite and offsite power, e.g., in a station blackout event. The systems include a gap formed along the periphery of the spent fuel pool, a heat sink, one or more thermal conductive members, a water supply system for delivering water to at least partially fill the gap and conduct heat generated from the spent fuel pool through the gap to at least one thermal conductive member for transporting heat to the heat sink, and a thermal switch mechanism for activating and deactivating the water supply system. In particular, the passive spent fuel pool cooling systems and methods of the invention are useful when the active spent fuel pool cooling system is unavailable or inoperable.

Abstract: An emergency spent nuclear fuel pool cooling system that requires no external electrical power source and relies on the expansion of a cryogenic fluid through an evaporator/heat exchanger submerged within the spent fuel pool, to power various components used to cool the spent fuel pool and adjacent areas and provide makeup water to the spent fuel pool. Other than the evaporator/heat exchanger to which the cryogenic fluid is connected, the remaining components employed to cool the pool and the surrounding area and provide makeup water can be contained in a relatively small, readily transportable skid.

Abstract: The present invention relates to passive cooling systems and methods for cooling a spent fuel pool in a nuclear power plant in the absence of onsite and offsite power, e.g., in a station blackout event. The systems include a gap formed along the periphery of the spent fuel pool, a heat sink, one or more thermal conductive members, a water supply system for delivering water to at least partially fill the gap and conduct heat generated from the spent fuel pool through the gap to at least one thermal conductive member for transporting heat to the heat sink, and a thermal switch mechanism for activating and deactivating the water supply system. In particular, the passive spent fuel pool cooling systems and methods of the invention are useful when the active spent fuel pool cooling system is unavailable or inoperable.

Abstract: An emergency spent nuclear fuel pool cooling system that requires no external electrical power source and relies on the expansion of a cryogenic fluid through an evaporator/heat exchanger submerged within the spent fuel pool, to power various components used to cool the spent fuel pool and adjacent areas and provide makeup water to the spent fuel pool. Other than the evaporator/heat exchanger to which the cryogenic fluid is connected, the remaining components employed to cool the pool and the surrounding area and provide makeup water can be contained in a relatively small, readily transportable skid.

Abstract: The present invention relates to passive cooling systems and methods for cooling a spent fuel pool in a nuclear power plant in the absence of onsite and offsite power, e.g., in a station blackout event. The systems include a gap formed along the periphery of the spent fuel pool, a heat sink, one or more thermal conductive members, a water supply system for delivering water to at least partially fill the gap and conduct heat generated from the spent fuel pool through the gap to at least one thermal conductive member for transporting heat to the heat sink, and a thermal switch mechanism for activating and deactivating the water supply system. In particular, the passive spent fuel pool cooling systems and methods of the invention are useful when the active spent fuel pool cooling system is unavailable or inoperable.

Abstract: Apparatus for passively generating electric power during a nuclear power station blackout by utilizing the temperature difference between the hot inlet of a residual heat removal circuit and the surrounding containment environment. A heat engine, such as a thermoelectric generator, a Stirling Cycle Engine or Rankine Cycle Engine, is coupled in heat exchange relationship with an uninsulated portion of the inlet to a passive residual heat removal heat exchanger and/or passive residual heat removal heat exchanger channel head to generate the power required to operate essential equipment needed to maintain the nuclear power station in a safe condition during a loss of normal onsite and offsite power.

Abstract: The present invention relates to a generation system for converting compressed air in a passive main control room habitability system to energy when the main control room habitability system is activated during an accident scenario in a nuclear reactor power plant. The system includes a pressure regulator for reducing the pressure of the compressed air to produce reduced pressurized air, an eductor to deliver air to the control room, and piping to connect the tank to the pressure regulator and the eductor to allow the flow of compressed air therein. The generation system includes a mechanism positioned upstream of the eductor for receiving the reduced pressurized air from the pressure regulator and converting at least a portion of said reduced pressurized air into energy.

Abstract: Apparatus for extracting useful electric or mechanical power in significant quantities from the decay heat that is produced within spent nuclear fuel storage casks. The power is used for either powering an active forced air heat removal system for the nuclear fuel storage casks, thereby increasing the thermal capacity of the casks, or for emergency nuclear plant power in the event of a station blackout. Thermoelectric generators or other heat engines are employed using the thermal gradient that exists between the spent nuclear fuel container surface and the environment surrounding the cask's components housing the nuclear fuel to produce the power.

Abstract: The present invention relates to passive cooling systems and methods for cooling a spent fuel pool in a nuclear power plant in the absence of onsite and offsite power, e.g., in a station blackout event. The systems include a gap formed along the periphery of the spent fuel pool, a heat sink, one or more thermal conductive members, a water supply system for delivering water to at least partially fill the gap and conduct heat generated from the spent fuel pool through the gap to at least one thermal conductive member for transporting heat to the heat sink, and a thermal switch mechanism for activating and deactivating the water supply system. In particular, the passive spent fuel pool cooling systems and methods of the invention are useful when the active spent fuel pool cooling system is unavailable or inoperable.

Abstract: The present invention relates to a generation system for converting compressed air in a passive main control room habitability system to energy when the main control room habitability system is activated during an accident scenario in a nuclear reactor power plant. The system includes a pressure regulator for reducing the pressure of the compressed air to produce reduced pressurized air, an eductor to deliver air to the control room, and piping to connect the tank to the pressure regulator and the eductor to allow the flow of compressed air therein. The generation system includes a mechanism positioned upstream of the eductor for receiving the reduced pressurized air from the pressure regulator and converting at least a portion of said reduced pressurized air into energy.

Abstract: Apparatus for passively generating electric power during a nuclear power station blackout by utilizing the temperature difference between the hot inlet of a residual heat removal circuit and the surrounding containment environment. A heat engine, such as a thermoelectric generator, a Sterling Cycle Engine or Rankine Cycle Engine, is coupled in heat exchange relationship with an uninsulated portion of the inlet to a passive residual heat removal heat exchanger and/or passive residual heat removal heat exchanger channel head to generate the power required to operate essential equipment needed to maintain the nuclear power station in a safe condition during a loss of normal onsite and offsite power.

Abstract: A pressurized fuel cell system (10), operates within a common pressure vessel (12) where the system contains fuel cells (22), a turbine (26) and a generator (98) where preferably, associated oxidant inlet valve (52), fuel inlet valve (56) and fuel cell exhaust valve (42) are outside the pressure vessel.

Abstract: A solid oxide fuel cell (40) having a closed end (44) and an open end (42) operates in a fuel cell generator (10) where the fuel cell open end (42) of each fuel cell contains a sleeve (60, 64) fitted over the open end (42), where the sleeve (60, 64) extends beyond the open end (42) of the fuel cell (40) to prevent degradation of the interior air electrode of the fuel cell by fuel gas during operation of the generator (10).

Abstract: A mono-container fuel cell generator (10) contains a layer of interior insulation (14), a layer of exterior insulation (16) and a single housing (20) between the insulation layers, where fuel cells, containing electrodes and electrolyte, are surrounded by the interior insulation (14) in the interior (12) of the generator, and the generator is capable of operating at temperatures over about 650.degree. C., where the combination of interior and exterior insulation layers have the ability to control the temperature in the housing (20) below the degradation temperature of the housing material. The housing can also contain integral cooling ducts, and a plurality of these generators can be positioned next to each other to provide a power block array with interior cooling.

Abstract: A high temperature solid oxide fuel cell generator produces electrical power from oxidation of hydrocarbon fuel gases such as natural gas, or conditioned fuel gases, such as carbon monoxide or hydrogen, with oxidant gases, such as air or oxygen. This electrochemical reaction occurs in a plurality of electrically connected solid oxide fuel cells bundled and arrayed in a unitary modular fuel cell stack disposed in a compartment in the generator container. The use of a unitary modular fuel cell stack in a generator is similar in concept to that of a removable battery. The fuel cell stack is provided in a pre-assembled self-supporting configuration where the fuel cells are mounted to a common structural base having surrounding side walls defining a chamber.

Abstract: An electrochemical fuel cell generator configuration is made having a generator section which contains a plurality of axially elongated fuel cells, each cell containing a fuel electrode, air electrode, and solid oxide electrolyte between the electrodes, in which axially elongated dividers separate portions of the fuel cells from each other, and where at least one divider also reforms a reformable fuel gas mixture prior to electricity generation reactions, the at least one reformer-divider is hollow having a closed end and an open end entrance for a reformable fuel mixture to pass to the closed end of the divider and then reverse flow and pass back along the hollowed walls to be reformed, and then finally to pass as reformed fuel out of the open end of the divider to contact the fuel cells, and further where the reformer-divider is a composite structure having a gas diffusion barrier of metallic foil surrounding the external walls of the reformer-divider except at the entrance to prevent diffusion of the refor

Abstract: A fuel cell generator apparatus and method of its operation involves: passing pressurized oxidant gas, (O) and pressurized fuel gas, (F), into fuel cell modules, (10 and 12), containing fuel cells, where the modules are each enclosed by a module housing (18), surrounded by an axially elongated pressure vessel (64), where there is a purge gas volume, (62), between the module housing and pressure vessel; passing pressurized purge gas, (P), through the purge gas volume, (62), to dilute any unreacted fuel gas from the modules; and passing exhaust gas, (82), and circulated purge gas and any unreacted fuel gas out of the pressure vessel; where the fuel cell generator apparatus is transpatable when the pressure vessel (64) is horizontally disposed, providing a low center of gravity.

Abstract: A multiple circuit hybrid cryostat power lead has a plurality of laterally spaced, electrically isolated lead elements inside a tubular enclosure. Each lead element has an inner section with a high temperature superconducting (HTS) conductor inward of a divider in the tubular enclosure, and an outer normal conductor section outward of the divider. The outer sections of the lead elements have a pair of copper conductors spirally wound in an annular chamber between an electrically insulating central support and an electrically insulating sleeve to form helical flow passages. Cryogen vapor flows outward in the tubular enclosure inward of the divider over the HTS conductors, through a slotted heat exchanger electrically connecting the HTS and copper conductors at the divider, and through the helical flow passages to vents at outer terminals.

Abstract: A vapor cooled current lead for a superconducting device located in a cryostat includes a normal conductor section extending from ambient conditions inward to an intermediate point, and a composite lead having a ceramic high temperature superconductor core with a metallic sheath extending between the normal conductor section and the superconducting device, preferably in a helical path to reduce heat leak by conduction. The metallic sheath is stripped away at spaced intervals, preferably adjacent the low temperature end of the composite lead, and the gaps are filled with a filler which provides mechanical strength for the core and reduces thermal conduction. A flow of cryogen vapor directed by a tubular housing maintains the high temperature superconducting material below its critical temperature, and cools the normal conductors.

Abstract: A superconducting magnetic energy (SMES) system having an axially sectioned multilayered solenoid coil immersed in a liquid helium bath contained in annular helium vessel includes as an interface between each section of the inner and outer layers of the coil and the helium vessel a finger plate assembly comprising a plurality of electrically nonconductive finger plates clamped at one end with spacers between adjacent finger plates to hanger plates welded to the helium vessel walls. The other ends of the finger plates are interleafed with the turns of the coil and clamped together with the coil turns by clamping assemblies which clamp the turns in adjacent layers of the coil. Loading bars between the layers transmit the radial loads generated by the magnetic and thermal forces acting on the coil to the finger plates.