Abstract: The instrumentation column (5) comes to bear via a bearing surface and a sealing gasket (16) inside a bearing element including a tubular length (8) and a closure cover (11) joined together by screwed assembly means. The tubular length (8) and the cover (11) each include a bearing surface (33a, 34) which is symmetrical of revolution about the axis of the instrumentation column (5). The bearing surface (33a) of the cover (11) and the bearing surface (34) of the tubular length (8) between them, through direct metal-to-metal contact, provide sealing against the pressurized water of the reactor.

Abstract: A sealed neutron tube with magnetic confinement of the electrons by permanent magnets. The sealed tube contains a D-T gas mixture under low pressure, fitted with a target, an extraction-acceleration electrode (EAE) and an ion source with 2n Penning cells having anodes in a single cathode cavity and one permanent magnetization system (PMS) per cell. The ions, formed in the ion source, by means of the simultaneous presence of an electric and magnetic field, are accelerated by the EAE and projected onto the target in order to cause emission of neutrons therefrom. In this tube, half (n) of the PMS is magnetized to a nominal value and the other half is weakly magnetized or unmagnetized.

Abstract: A self-powered fixed incore detector for a nuclear reactor has a neutron sensitive emitter element having a low neutron absorption cross section, such as a vanadium element, which extends the length of the active fuel region and generates a full length signal representative of full length power. A number of gamma sensitive emitter elements, preferably platinum but alternatively zirconium, cerium, tantalum, or osmium elements, provide sequentially increasing overlap with the neutron sensitive emitter element to define axial regions of the active fuel region and generate apportioning signals. The portion of the full length signal generated by the neutron sensitive emitter element attributable to each of the axial regions of the core are determined from ratios of the apportioning signals generated by the gamma sensitive elements.

Abstract: A control cluster for a water cooled and moderated nuclear reactor, comprises a spider and rods suspended from the spider. Each rod contains neutron-absorbing material. In a lower portion of each rod, the material is a metal neutron absorber. In an upper portion, it is a stack of pellets of boron carbide B.sub.4 C. In a middle fraction occupying a height lying in the range 35% to 45% of the total height, it is zirconium diboride ZrB.sub.2 isotopically enriched in boron 10 or hafnium diboride HfB2.

Abstract: The control rod for a nuclear reactor includes a plurality of wings each having segments of neutron absorbing material exposed along the length of the rod. During refueling, the segments of neutron absorbing material are rearranged within the control rod and the control rod is reinserted into the reactor core. By rearranging the segments, optimum use of the depletion capacity of each segment is effected, maximizing the number of cycles for which the control rod may be used.

Abstract: An improved system for passively removing hydrogen inside containment in a nuclear reactor in the event of a loss of coolant accident by means of catalytic hydrogen recombination. A baffle wall located inside containment is used to establish within containment an air upflow path and an air downflow path in convective exchange. The air upflow is past the area of the coolant lines and is effective to entrain hydrogen from the break and the air downflow path is in the area adjacent the containment wall. The air upflow path downstream of the coolant lines is ducted so as to confine the entrained hydrogen to the ducted air upflow path and catalytic hydrogen recombiners are located in the ducted air upflow path for recombining said entrained hydrogen with oxygen in said ducted air upflow.

Abstract: A vertical seismic isolation structure is capable of achieving vertical seismic isolation of nuclear reactor components connected to each other by primary pipings, while suppressing the relative displacement with respect to the primary pipings. A nuclear reactor vessel, circulating pumps and heat exchangers, all of which are connected to each other by primary pipings in which a coolant is circulated, are mounted on a common deck. Vertical seismic isolators each of which has laminated large coned disc springs and is capable of expanding and contracting in only the vertical direction are installed on the top of a concrete wall surrounding the respective nuclear reactor components. The common deck is placed on all the vertical seismic isolators so as to support the entire seismic isolation structure (the common deck, the nuclear reactor components, etc.).

Abstract: In a slow positron beam generating device having a cyclotron for irradiating protons or deuterons during an irradiating time interval, a target member receives the protons or the deuterons to generate radioisotopes which emit positrons by causing .beta..sup.+ decay. Ejecting electrodes receive the positrons moderated by a moderator to eject a slow positron beam. The irradiating time interval is longer than a half life of the radioisotope. Preferably, the irradiating time interval is longer than a six multiplied by the half life of the radioisotope.

Abstract: A thermal neutron detector comprises an enclosure containing a helium-xenon gas mixture, an optical fiber, and an electrode arranged to detect ion particles. The optical fiber detects photons generated by a reaction of the gas mixture with neutrons passing through the enclosure. The reaction also generates ion particles that are detected by the electrode. A coincidence detector generates an output signal corresponding to the correlation of ion detections from the electrode with photon detections from the optical fiber, rejecting signals generated from the electric field that are not correlated with photon detections.

Abstract: In a bulk material analyzer in which bulk material is received in an activation region between a pair of neutron sources laterally disposed on one side of the activation region for emitting neutrons for bombarding the bulk material within the activation region to cause gamma-rays to be emitted from the bombarded bulk material and a pair of gamma-ray detectors laterally disposed on another side of the activation region for detecting gamma-rays emitted from the bulk material, a primary neutron moderator is disposed about the neutron sources for reducing the velocity of the emitted neutrons; and a secondary neutron moderator is disposed about the primary neutron moderator for further reducing the velocity of the neutrons and is further disposed adjacent the lateral edges of the activation region for channeling and reflecting the neutrons into the activation region.

Abstract: The control rod includes a plurality of elongated tubes containing neutron-absorbing material in a planar array to form wings on opposite sides of a central axis of the control rod. Each tube is formed with a plurality of protuberances in excess of four such that the tubes can be welded to adjacent tubes with the weld lines disposed inwardly of the side surfaces of the wings to improve the flexibility of the control rod. The wings of each planar array have connecting elements of each other planar array thereof, enabling lateral movement of the planar arrays of wings relative to one another to further enhance flexibility and movement of the control rod between the fuel channels of the nuclear core.

Abstract: A control rod for a nuclear reactor incorporates a plurality of neutron absorber tubes containing neutron absorbing materials. The absorber tubes are substantially rectangular inside and outside, each tube containing at least one axial stack of substantially round neutron absorbing material segments or capsules.

Abstract: A method for determining the core flow rate from pump differential pressure method equations and a heat balance equation for determining the temperature and density of the reactor water in the downcomer and lower plenum region. The measured reactor water temperature is used only as an initial estimate for this new method. This allows the first estimate of the core flow to be determined based upon the reactor water density that corresponds to this temperature and the pump differential pressure and pump rotational speed measurements. Then, with this intial core flow measurement value, and other available plant measurements and assumed nominal values for the heat balance equation, revised values for the reactor water temperature and density can be calculated. Using a standard numerical method, such as the successive approximation technique, a more accurate estimate for the reactor water density can be obtained.

Abstract: The present invention relates to method of fueling and operating a nuclear reactor core. Fueling the nuclear reactor core for a power operation cycle includes the steps of designating a central core region, a buckled core region and a peripheral core region, placing at least two fuel assemblies of relatively high reactivity in the fuel cells in the central core region and placing fuel assemblies of relatively low reactivity in the cells in the peripheral core region.

Abstract: In a nuclear fuel rod assembly including a plurality of fuel rods and at least one water rod held together in a bundle, and wherein end plugs at the lower ends of the fuel rods and the at least one water rod engage a lower tie plate, an improvement wherein the end plug at the lower end of the at least one water rod is hollow and includes a multi-diameter flow metering bore for regulating coolant flow into the water rod.

Abstract: An apparatus for measuring fuel assembly bow and twist comprising a fixturing apparatus, a reference device and an ultrasonic measuring device.

Abstract: The lower end of each of a plurality of fuel rods is supported by a fuel supporting portion of a lower tie plate. The fuel supporting portion includes a plurality of second coolant paths for supplying a coolant from below the fuel supporting portion to a first coolant path defined above the fuel supporting portion and between the fuel rods. The total cross-sectional area of all the second coolant paths is smaller than the cross-sectional area of the first coolant path.

Abstract: Pressure vessels of nuclear plants are equipped with so-called pressure-vessel fittings for the purpose of receiving fuel assemblies. If a bulky part of that type is to be exchanged, very large transport containers for transporting to a location outside the nuclear plant are required. In order to ensure that smaller transport containers can be used, it is necessary to dismantle the bulky parts. In order to ensure that the dismantling operation can be carried out without complicated holding devices, provision is made for setting down an open transport container on the bottom of a water tank. A bulky part is inserted into the transport container and the bulky part projects a predeterminable amount above an end surface of the transport container. The bulky part is separated above the end surface through the use of a separating device disposed on the end surface of the transport container.

Abstract: Iodine-125 is produced by neutron irradiation of .sup.124 Xe gas to form .sup.125 Xe and permitting decay of .sup.125 Xe to form .sup.125 I. Irradiation of the xenon-124 is effected in a first chamber within an enclosure and decay is effected in a second chamber within the enclosure and free from neutron flux. The apparatus is submersible in a nuclear reactor pool so as to absorb any radiation escaping the apparatus during the process. Xenon can be caused to move between the chambers remotely, underwater. The second chamber is removable from said enclosure and is transported to a suitable location to recover the .sup.125 I from its interior. Such recovery is effected by admitting an aqueous wash solution into the second chamber, whereupon it is heated, causing water from the wash solution to reflux and cleanse the interior surfaces of the second chamber, thus creating an aqueous solution of .sup.125 I, which then is caused to drain into a suitable container.

Abstract: A diving bell type control rod of sodium bond type. The control rod including a plurality of control elements each comprising a pellet chamber for packing B.sub.4 C pellets and disposed in a cladding tube, an intermediate plug disposed above the pellet chamber, an upper chamber formed above the intermediate plug, a vent tube allowing the pellet chamber to communicate with the upper chamber while penetrating through the intermediate plug, upper and lower vent holes formed in upper and lower two stages in the cladding tube at the upper chamber, a sodium inflow port opening to the upper surface of the intermediate plug, and a sodium introduction tube extending from the sodium inflow port to a position below the lower end surface of the intermediate plug while penetrating through the intermediate plug.