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An armor with rollers is provided that enables a user to move in all positions by rolling on a hard and smooth surface while constantly varying his bearing points on the ground.
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| Number | Title | Issue Date |
| 8116422 | LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reac... | 02/14/2012 |
| 7881420 | Method and apparatus for reducing vibration in component of a nuclear reactor A vibration mitigation apparatus and method of reducing vibration in a reactor component are described, which may reduce the amplitude of vibration in the reactor component. The apparatus may be provided on the reactor component to reduce the amplitude of vibration ... | 02/01/2011 |
| 7873135 | Method and apparatus for mitigating vibration in a nuclear reactor component A device is provided for mitigating vibration in a component of a nuclear reactor by removing vibration energy. To reduce vibration in the component, a device operatively connected to the component and including a magnet may be actuated within a conductive cylinder.... | 01/18/2011 |
| 7760842 | Method and apparatus of estimating dryout properties in a nuclear light water reactor The invention concerns a method of estimating when dryout may occur in a nuclear light water reactor of the boiling water reactor kind. The method includes the use of a formula which expresses the local dryout property of the nuclear reactor. The formula includes at... | 07/20/2010 |
| 7492851 | Clamp for feedwater sparger end bracket assemblies and method of preventing separation of feedwater sparger end bracket assemblies A constrained feedwater sparger end bracket assembly comprises a boiling water reactor vessel, a feedwater sparger including a conduit within the vessel, a feedwater sparger end bracket assembly connected to an end of the conduit at a sparger/bracket junction, and a... | 02/17/2009 |
| 7429807 | Adjustable speed drive system for primary loop recirculation pump An adjustable speed drive system for a primary loop recirculation pump capable of keeping a PLR pump operating even if a single malfunction occurred in a main adjustable speed drive circuit portion. The drive system for the primary loop recirculation pump has a back... | 09/30/2008 |
| 7340387 | Control rod driving simulator for verification of control rod driving mechanism control system of atomic power plant A control rod driving simulator has a control rod driving unit having a plurality of coil members vertically mounted therein, a control rod mounted vertically movably through the centers of the coil members, a cart having a reserve tank storing cooling water, a cool... | 03/04/2008 |
| 7272204 | Method and apparatus for clamping a riser brace assembly in nuclear reactor An apparatus and method are provided which are designed to structurally replace welds that attach a riser brace assembly to a jet pump riser pipe. The riser brace assembly may include an upper clamp assembly, a lower clamp assembly, and a plurality of mechanical fas... | 09/18/2007 |
| 7264770 | Mitigation of stress corrosion cracking of structural materials exposed to a high temperature water A method for mitigating stress corrosion cracking of a component exposed to a high temperature water in a high temperature water system is provided. The method comprises the steps of lowering corrosion potential conditions to a desired low corrosion potential in the... | 09/04/2007 |
| 7250143 | Device for spraying water The invention concerns a device for spraying water in a feedwater tank of a thermal power plant. Because the spraying device comprises a catalyst for the conversion of the gases contained in the water, the gases released from the water during the spray degasificatio... | 07/31/2007 |
| 7218068 | Power source for re-circulation pump and method of controlling the same A variable-voltage variable-frequency power source for an electric motor that drives a re-circulation pump for a boiling water nuclear reactor. The power source has a semiconductor electric power converter and a speed controller for controlling the semiconductor ele... | 05/15/2007 |
| 7215729 | Fuel assembly and nuclear reactor A resistance member (e.g., fuel holding portion of the lower tie plate) is provided at the lower end of the fuel assembly. Provision is made of a coolant ascending path in which said water rods have coolant inlet ports that are open in a region lower than the resist... | 05/08/2007 |
| 7158919 | Remote monitoring system A remote monitoring system including a sub-system, local to a nuclear power plant and a remote sub-system at an operations base. Process data is collected manually by a hand-held computer and automatically by instrumentation on the power plant. The data collected is... | 01/02/2007 |
| 7139359 | Integrated head assembly for a nuclear reactor An integrated head assembly (100) is disclosed for a nuclear reactor. The preferred integrated head assembly includes a lift assembly (150) that supports the reactor vessel closure head (90) and integrated head assembly for removal, a separate s... | 11/21/2006 |
| 7031779 | Method and apparatus for automated crack behavior prediction determination A method of predicting component crack behavior in a nuclear reactor provides access to a crack growth behavior model over a global network. A user inputs water chemistry and material characteristics of a particular nuclear reactor and can perform crack growth rate ... | 04/18/2006 |
| 6865244 | Device and method for cooling a reactor pressure vessel of a boiling water reactor plant In order to allow a reliable and passive external cooling of a reactor pressure vessel of a boiling water reactor, outside the reactor pressure vessel a differential-pressure measurement pipe is provided and has a first and a second pipe leg which are connected to o... | 03/08/2005 |
| 6839396 | Control device for a cooling circuit Control device for a cooling circuit which enables a pressure tank of a reactor to be cooled even when a serious failure occurs, without having to resort to the use of external energy. One or more rods is disposed below a bottom cap of the reactor pressure tank. Eac... | 01/04/2005 |
| 6728328 | Safety control circuit for a neutronic reactor A neutronic reactor comprising an active portion containing material fissionable by neutrons of thermal energy, means to control a neutronic chain reaction within the reactor comprising a safety device and a regulating device, a safety device including means definin... | 04/27/2004 |
| 6674825 | Determination of operating limit minimum critical power ratio A method and system for thermal-dynamic modeling and performance evaluation of a nuclear Boiling Water Reactor (BWR) core design is presented. Based on a predetermined generic transient bias and uncertainty distribution in the change in critical power rat... | 01/06/2004 |
| 6618461 | Systems and methods to enhance passive containment cooling system A nuclear reactor containment cooling system includes a containment vessel having a drywell and a wetwell, a cooling condenser submerged in a cooling pool of water located outside the containment vessel, a vent line extending from the condenser to a suppr... | 09/09/2003 |
| 6524534 | Apparatus for removing flammable gas An apparatus for removing flammable gas is started only when a concentration change in the flammable gas in a primary containment vessel is detected, so that the decrease in activity of a catalyst due to a catalyst poison is prevented. This apparatus has ... | 02/25/2003 |
| 6343106 | Boiling water reactor and operation thereof In a nuclear reactor, in-core stability is improved, power density is increased, and an economical natural-circulation reactor (or partial forced-circulation reactor) is achieved. The reactor core has a void reactivity coefficient between -0.07 and -0.03%... | 01/29/2002 |
| 6341151 | Preventive maintenance method and apparatus of a structural member in a reactor pressure vessel A preventive maintenance method and apparatus for a structural member in a reactor pressure vessel according to the present invention reduce a tensile residual stress on a surface of the structural member by impinging a water jet from a nozzle onto a plan... | 01/22/2002 |
| 6339630 | Sealed drive screw operator A sealed operator is provided for operating an internal locking control element for a closure head for the inner container in a dual container hazardous waste storage system. The operator includes a cylindrical housing in which a bushing/operator element ... | 01/15/2002 |
| 6333956 | Blow-off device and method of blowing off live steam A blow-off device for live steam includes a filter for radioactive substances in order to increase operational safety in a nuclear power plant. The filter is preferably integrated in a housing of a muffler or sound absorber and is disposed on a slide whic... | 12/25/2001 |
| 6327323 | Multiple reactor containment building A nuclear power plant includes at least two reactor vessels enclosed within a single containment building. In a first embodiment, the reactor vessels and steam generators operate separately from one another. In a second embodiment the reactor vessels join... | 12/04/2001 |
| 6311897 | Passive pulse generator and method for activating a fitting with a passive pulse generator A passive pulse generator can be connected to a line in order to activate a safety fitting in a nuclear power plant. The line can be closed by a closure element. In the event of a temperature change in the vicinity of the pulse generator, the closure elem... | 11/06/2001 |
| 6011826 | Steam power station A steam power station, in particular a nuclear power station, includes a steam conduit leading through a wall and forming a fixed point with the wall for the introduction of forces and moments. A main valve is connected to the steam conduit at the fixed p... | 01/04/2000 |
| 5995575 | In-core guide tube restraint for a boiling water reactor A restraint assembly which is a bolted lattice structure for preventing the in-core guide tubes from experiencing excessive flow induced vibrations is described. In one embodiment, the restraint assembly includes upper and lower restraint brackets secured... | 11/30/1999 |
| 5991352 | Method for determining corrosion susceptibility of nuclear fuel cladding to nodular corrosion A method for determining the susceptibility of a sample of Zircaloy alloy to nodular corrosion. A specimen of such Zircaloy sample is annealed at a temperature within a temperature range bounded at its upper limit by the temperature Tc being th... | 11/23/1999 |
| 5964029 | Apparatus for repairing cracked core spray supply piping in a boiling water reactor An apparatus for repairing cracked core spray supply piping in a boiling water reactor vessel includes a pair of clamps extending circumferentially around the piping on opposite sides of a crack and a preloading mechanism urging the clamps toward one anot... | 10/12/1999 |
| 5839192 | Method and apparatus for repairing cracked core spray supply piping in a boiling water reactor An apparatus for repairing cracked core spray supply piping in a boiling water reactor vessel includes a pair of clamps extending circumferentially around the piping on opposite sides of a crack and a preloading mechanism urging the clamps toward one anot... | 11/24/1998 |
| 5683216 | Spring latching mechanisms for preventing relative movement of assembled components Spring latching mechanisms for preventing relative rotation or relative displacement of assembled components during operation of a nuclear reactor. The first type of mechanism prevents rotation of a threaded fastener which fastens a first component to a s... | 11/04/1997 |
| 5657360 | Reactor container A reactor container is composed of a dry well and a wet well and, in the reactor container, there is provided with a dry well cooling system, the dry well cooling system including, in one aspect, an in-dry-well heat exchanger disposed in the dry well of t... | 08/12/1997 |
| 5631938 | Reactor internal pump maintenance cover A maintenance cover for use in a nuclear reactor including a pump deck having at least one pump diffuser opening is described. The cover includes, in one embodiment, a substantially cylindrical member having a first end and a second end. The first end has... | 05/20/1997 |
| 5621777 | Pump drive system for recirculation of coolant flow in a nuclear reactor vessel The invention relates to a drive system for internal recirculation of coolant in a nuclear reactor (1), wherein the drive system for a main recirculation pump (10) for the coolant recirculation comprises a pump motor (11) connected to the main recirculati... | 04/15/1997 |
| 5610958 | Reactor circulating pump system A reactor circulating pump system comprises a pump and a power supply apparatus for driving the pump. In the power supply apparatus, an AC/DC converter and a DC/AC converter provided with an AC voltage/frequency adjuster are connected in series between an... | 03/11/1997 |
| 5539794 | Reduction of manganese content of stainless alloys to mitigate corrosion of neighboring in-core zirconium based components An improved stainless steel composition and an improved stainless Ni-based alloy are disclosed for use in nuclear reactor environments. The improved stainless alloys include a stainless steel and a stainless nickel based alloy that are particularly well a... | 07/23/1996 |
| 5493591 | Internal pump for nuclear reactors A nuclear internal pump is disclosed in which a flywheel and a thrust disc acting as an auxiliary impeller are fixed on a motor shaft. Fixed orifices X and Y are formed respectively between outer circumference section at larger and smaller diameter sides ... | 02/20/1996 |
| 5492409 | Device for mixing two fluids having different temperature A device for mixing two fluids having different temperatures comprises a connecting branch (6) extending into a main pipe (1) from a secondary pipe (2), said connecting branch having at its end positioned in the main pipe a distribution casing (7) with do... | 02/20/1996 |
