Abstract: Flow of mercury from a liquid-heavy-metal inflow port toward an inner forward end of a container body is rectified by a plurality of incoming-passage guide vanes in a liquid-heavy-metal incoming passage. Flow of the mercury from the forward end of the container body toward a liquid-heavy-metal outflow port is rectified by a plurality of return-passage guide vanes in a liquid-heavy-metal return passage. As a result, occurrence of stagnation and/or recirculation flows of the mercury in the container body is suppressed and a steady and highly uniform stream of the mercury is formed throughout in the container body. The container body is covered with a container outer shell to prevent any leakage of the mercury to outside due to a damage of the container body.

Abstract: A control system, and a control method, of a nuclear power plant capable of easily executing automatic output regulation by an automatic power regulator system even when a lower-accuracy maximum linear heat generation rate and a lower-accuracy minimum critical power ratio are determined in a short cycle by using brief calculation. While a core monitoring system does not calculate a maximum linear heat generation rate and a minimum critical power ratio, they are determined by utilizing the maximum linear heat generation rate and the minimum critical power ratio calculated by the core monitoring system as well as plant data, and the lower-accuracy maximum linear heat generation rate and the lower-accuracy minimum critical power ratio so determined are compared with predetermined thermal limit values.

Abstract: A spacer for a fuel assembly of a nuclear reactor includes an elongated spring which is held in a mesh in such a way that there is structural freedom with respect to a selection of a shape of the spring and that little spring material is required. Two lateral rims at a top end of the spring are bent around a center of a fuel element out of the mesh in such a way that they protrude through an assembly opening in the web into an adjacent mesh. The two rims approximately form-lockingly encompass an edge of the assembly opening through the use of a profiled section. A lower end of the spring is also correspondingly held on the web through the use of profiled sections on its two rims, which are bent outward. Two springs protruding into adjacent meshes can then also be fastened in the same assembly opening.

Abstract: The loader assist for mortars allows for the automated loading of ammunition through the muzzle. The invention assists soldiers by transporting the shell into the muzzle from a lower position near the base of the mortar tube thus reducing exposure to enfilade enemy fire and the effects of muzzle blast. The loader assist comprises a frame surrounding the mortar and attached thereto. The frame is supported on pivots mounted to a turntable such that both the invention and mortar move as a unit. A lift device is positioned at the center of the frame and parallel to the mortar axis. A carriage comprising a transfer device is positioned on top of said frame. Said elevator is comprised of two linear actuators which are positioned opposite each other, allowing the jaws on each shuttle to act in pairs with the respective jaws on the other, to grip the shell in two places.

Abstract: An end effector for supporting an ultrasonic testing probe on a robot arm having a robot mounting bracket for use in a nuclear reactor pressure vessel. The end effector has a wrist assembly with a rotatable wrist axle. The wrist assembly is coupled to the robot mounting bracket and a probe assembly is coupled to the wrist shaft. The ultrasonic testing probe is floatably disposed within the probe assembly.

Abstract: A method and an apparatus for deionizing water are disclosed. A condensate in the secondary cooling water system in a PWR nuclear power plant is passed through a mixture of an anion exchange resin and a cation exchange resin having a crosslinking degree of about 12 to 16%. The cation exchange resin has an improved, ion exchange capacity. thereby decreasing the frequency of changing the condensate.

Abstract: A neutron flux measuring apparatus, adapted to a boiling-water reactor (BWR) of a nuclear power plant and an advanced boiling-water reactor (ABWR) of a nuclear power plant, for measuring a neutron flux in a reactor pressure vessel, comprises a neutron flux detector assembly incorporating a local power range monitor detector assembly and a start-up range neutron monitor detector, a preamplifier amplifying a detector signal obtained from said start-up range neutron monitor detector, a start-up range neutron monitor operation unit operating, indicating and monitoring the amplified signal of the start-up range neutron monitor detector, and a local power range monitor operation unit operating, indicating and monitoring a signal obtained from the local power range monitor detector.

Abstract: A device for measuring gas pressure that is dependent upon the level of a liquid comprises a pressure indicator or sensor (6, 6′) which is connected to an upper part of a tube conduit (7, 7′) which is filled with gas and intended to operate in a liquid mass, said conduit having a lower part connected to an upper part of a vessel (8, 8′) with a volume that is larger than the volume of the tube conduit. The vessel (8, 8′) has an inlet (13) to let the liquid in, which inlet has a cross-sectional area that is smaller than the cross-sectional area of the vessel and that is located near the bottom of the vessel. Therefore, liquid that penetrates into the vessel via the inlet forms a surface whose level in itself in the vessel may vary depending upon the level of the surrounding main liquid mass, however normally without the liquid rising up into the tube conduit (7, 7′) as such.

Abstract: When a radioactivated reactor pressure vessel is carried out from a nuclear reactor building of a nuclear power plant, a first opening portion for carrying out the reactor pressure vessel is provided in a roof of the nuclear reactor building, a radiation shield for covering the reactor pressure vessel and shielding radiations is carried into the reactor building through the first opening portion, and installed on a reactor shield wall, lowering a hanger through the first opening portion and a slit provided on an upper lid of the radiation shield, a part of a lid of the reactor pressure vessel and a part of the upper lid of the radiation shield are abutted by hanging up the reactor pressure vessel by the hanger, and the reactor pressure vessel and the radiation shield integrated therewith are raised and carried out of the reactor building, whereby the shield can be easily mounted on the large-sized apparatus in a short time and a dose of radiations exposed to a worker when the shield is mounted can be reduced.

Abstract: Within an upper plenum of a nuclear reactor, a portion of a heated coolant flows radially outward from a central portion of a core barrel (30) towards outlet nozzles (12) in a region of an upper core plate (21) extending outside of an outer periphery of the core along an inner wall of a core barrel (30). Portions of the coolant flows beneath the outlet nozzles (12). Thus, streams of heated coolant flowing in opposite directions may collide with each other. After collision, the flow directions of the heated coolant are changed to flow upward. Due to the collision, the coolant flow behavior becomes complicated and unstable, making it difficult to measure the temperature of the heated coolant with an outlet pipe (42) connected to the outlet nozzle (12).

Abstract: A weapon trigger guard apparatus is provided for use on a gun rack having a support member and a lock coupled to the support member. The weapon trigger guard apparatus comprises a base rigidly coupled to the support member of the rack, and a cover pivotably coupled to the base. The cover is movable between a first open position to permit installation and removal of the weapon from the rack and a second closed position in which the cover and the base cooperate to surround and enclose a trigger housing of the weapon.

Abstract: A Critical Channel Power (CCP) enhancement system is provided for a pressurized fuel-channel-type water-cooled nuclear reactor of the type adapted to be refuelled on-line by the insertion and removal of fuel bundles onto and from of a plurality of said fuel channel assemblies, each of said fuel channel assemblies. A means is provided for interlocking fuel bundles into pairs having their fuel elements aligned, thereby lowering the hydraulic resistance in the fuel channel and enhancing CCP. The means for interlocking prevents misalignment of the paired bundles during their residence time inside the reactor due to continuous rocking and vibration of the fuel bundles exposed to very high coolant mass flow rate and misalignment due to axial separation of bundles impacting upon one another during fuelling operations.

Abstract: A dry radioactive substance storage facility stores spent fuel assemblies from nuclear power plants. The facility comprises a structure having a storage room storing storage tubes containing spent fuel assemblies. An air inlet duct defining an air inlet passage through which air is supplied into the storage room and an stack defining an air discharged passage through which air from the storage room is discharge outside are connected to the storage room. Radiation shielding members are disposed on the side of the air inlet duct and on the side of the stack, respectively, in the storage room to intercept radiation propagating toward the air inlet passage and the air discharge passage.

Abstract: A forged nozzle shell course for a pressure vessel includes shell course comprising at least one reinforcement portion extending radially outward from an outer surface of the shell course with each reinforcing portion including a nozzle having a radius. The nozzle includes a bore extending from an outside surface of the reinforcing portion to an inside surface of the shell course, and at least one extension attachment surface located adjacent to and coaxial to the bore. The reinforcing portion having a longitudinal dimension equal to about 2.0 times the radius of the nozzle, and a circumferential dimension equal to about 1.5 times the radius of the nozzle, measured from the centerline of the nozzle bore.

Abstract: The invention concerns a spacer (14) for a nuclear boiling water reactor. The spacer (14) comprises a plurality of cells (16) for holding or allowing elongated elements (12) to pass through the cells. Between the cells (16) there are a plurality of flow channels (18). The spacer comprises at least a plurality of deflecting members (22). The deflecting member comprises a vane (24) which extends in a direction from a cell (16) into the neighbouring flow channel (18). The vane is inclined relative to a vertical plane (26) and is wider in its upper part than in its lower part. The invention also concerns a fuel assembly for a nuclear boiling water reactor, comprising a deflecting member with vane of similar construction.

Abstract: A low impulse firing attachment and companion ammunition for combination gas and recoil operated automatic weapons is comprised of a barrel insert and piston that provide the mechanism for containing the expanding propellant gases produced on firing. Such mechanism provides the required gas pressure at the gas port of the weapon to power the gas system. The barrel insert also allows the use of a sub-caliber piston for the propellant gases to act against. The gas pressure forces the barrel and piston apart, accelerating the recoiling mass rearward to provide recoil operation. The sub-caliber piston allows the use of the relatively high gas port pressure while limiting the peak force transmitted through the adapter. The blank and adapter provide the appropriate gas pressure at the gas port to power the gas system. The adapter also acts as a piston inside the barrel so that the gas pressure forces the barrel rearward, which provides the recoil operation.

Abstract: A metal cooling tube of a water-cooled nuclear reactor, having an inner surface thereof exposed to an aqueous cooling medium containing hydrogen peroxide. The cooling tube has its inner surface coated with matter selected from the group consisting of the element manganese, molybdenum, zinc, copper, cadmium for absorbing such hydrogen peroxide and then affecting decomposition of the hydrogen peroxide in the aqueous medium. In preferred embodiment such coating is manganese and oxides thereof. A method for lowering the electrochemical corrosion potential of a metal allow cooling tube exposed to an aqueous medium in a water-cooled nuclear reactor is also disclosed. Such method comprises the step of coating an inner surface of such tube with matter selected from the group of elements comprising manganese, molybdenum, zinc, copper, cadmium, so as to permit absorption and hydrogen peroxide in such aqueous medium and effect decomposition of hydrogen peroxide in such aqueous medium.

Abstract: A tubular blank (22) is rolled on a mandrel (14) in a pilgrim rolling mill. In a first rolling stage, a first part of the blank (22) is rolled on a first part (18, 19) of the mandrel (14), with a reduction of the outside diameter of the blank (22) to the outside diameter of the guide tube and a reduction of the wall thickness of the blank (22) to one of a first wall thickness (e1) and a second wall thickness (e2) exceeding the first wall thickness (e1). The mandrel (14) is advanced in the axial direction. A second part of the blank (22) is rolled on a second part (20,21) of the mandrel spaced from the first part in the axial direction with a reduction of the outside diameter of the blank to the outside diameter of the guide tube and a reduction of the wall thickness of the blank (22) to the other of the first wall thickness (e1) and second wall thickness (e2).

Abstract: An ECP sensor includes a tubular ceramic probe having a closed tip at one end packed with a metal and metal oxide powder. A metal support tube receives an opposite end of the probe, and is joined thereto by a braze joint therewith. An electrical conductor extends through the support tube and probe, and has an end buried in the powder for electrical contact therewith. A ceramic band bridges the probe and tube at the joint for sealing thereof.

Abstract: A locking device for a reactor instrumentation protective sleeve and reactor instrumentation column assembly. The locking device includes a protective sleeve coupled to the instrumentation column by a selectively operable and closeable clip assembly. The locking device also includes a locking sleeve supported by the protective sleeve. The locking sleeve is supported by the protective sleeve such that a portion of the locking sleeve covers a portion of the protective sleeve and the clip assembly.