Abstract: In a steam generator, there is provided an annular foraminous or perforated flow distribution plate (100) which may be in the form of a single-piece annulus fixedly secured to the lower end of the heat exchange tube wrapper (146) for installation within new steam generator facilities, or alternatively, may comprise a plurality of arcuately-shaped segments (210) secured together by suitable bolt fasteners (226) for installation within existing steam generator facilities. The plate (100) is adapted to be wedgingly interposed between the lower end of the tube wrapper (146) and the upper surface (204) of the heat exchange tube bundle tubesheet (122), and the plate (100) has the configuration of a conical frustum for stability.

Abstract: A filter module for use in filtering particulates from a high temperature gas has a central gas duct and at least one horizontally extending support mount affixed to the duct. The support mount supports a filter element thereon and has a chamber therein, which communicates with an inner space of the duct through an opening in the wall of the duct, and which communicates with the clean gas face of the filter element. The filter element is secured to the support mount over an opening in the top wall of the support mount, with releasable securement provided to enable replacement of the filter element when desired. Ceramic springs may be used in connection with the filter module either to secure a filter element to a support mount or to prevent delamination of the filter element during blowback.

Abstract: A method and apparatus are described for producing a high fluence neutron dosimeter which serves as a permanent record for fission rate measurement. An alpha-emitting source which is a radioactive parent of the daughter isotope of interest is used to implant recoil ions resulting from alpha decay into a substrate such as a mica solid state track recorder. The source and the mica solid state track recorder are arranged in spaced, opposing relation in an assembly housed in a vacuum. For example, a .sup.241 Am source in thin layer form can be placed next to the mica solid state track recorder. Each alpha decay of .sup.241 Am results in a .sup.237 Np ion with enough recoil energy to be implanted in the solid state track recorder. An ion-implanted mica solid state track recorder so produced is then exposed to neutrons, etched, and both the induced fission tracks and recoil ion tracks are counted. As a result, the fission rate in fissions per atom can be calculated.

Abstract: A filtering apparatus for separating particulates from a hot gas stream using hollow, tubular filter elements has a housing with a laterally extending support plate for the filter elements separating the housing into upper and lower sections. The tops of the filter elements are biased against the support plate and the bottoms thereof restrained from lateral movement by restraining rings. Blowback and purge gas systems provide for cleaning of the filter elements and maintenance of the blowback system clear of the solids or condensation products that might form during the separation. The apparatus is especially useful in filtering solids from a hot, corrosive gaseous stream, such as a zirconium tetrachloride process gas stream, where the gas stream contains gaseous constituents that are subject to condensation or solids formation during separation of the particulates and prior to discharge from the filtering apparatus.

Abstract: A filtering unit for filtering particulates from high temperature gases uses a spiral ceramic spring to bias a ceramic, tubular filter element into sealing contact with a flange about an aperture of a metallic tube sheet. The ceramic spiral spring may contact the upper edge of the filter element and be restrained by a stop member spaced from one end of the tube sheet, or the spring may contact the bottom of the filter element and be restrained by a support member spaced from the opposite end of the tube sheet. The stop member and support member are adjustably secured to the tube sheet. A filtering system uses the ceramic spiral spring to bias a plurality of ceramic, tubular filter elements in a respective plurality of apertures in a tube sheet which divides a vessel into upper and lower enclosed sections.

Abstract: A pipe loop arrangement for the closed primary system of a nuclear reactor. The heated reactor coolant flows through a horizontally positioned hot leg pipe while the return flow cooled reactor coolant flows through a cold leg pipe concentrically mounted within the hot leg pipe. A bell-mounted suction port and the high pressure discharge port of the reactor coolant pump are located within an outlet chamber with the steam generator. A transition piece slip fitted to an opening within the reactor vessel outlet flange connects the cold leg pipe to the inlet to the nuclear core. A flow shroud surrounding the pump discharge connects the pump discharge to the cold leg pipe, forms a volute for the pump discharge and separates the outlet chamber from the inlet chamber of the steam generator.

Abstract: Metallic reflector units supported solely by the core barrel substantially fill the annular spaces between the vertically spaced former plates which traverse the irregular space between the fuel assembly array and the core barrel in a pressurized water reactor. The support for each reflector unit comprises a pin extending radially outward along an extended line passing through the center of the metallic mass to support the vertical loads, and four elongated bolts in a rectangular pattern centered on the pin to resist overturning moments induced by seismic loads. The elongated bolts engage the core barrel and the bottoms of bores in the reflector units so that the bolts are free to bend to accommodate for thermal expansion of the reflector unit in all directions from the pin.

Abstract: A high fluence neutron dosimetry method is described, including the steps of: exposing a dosimeter containing an alpha-emitting target isotope to neutron irradiation to form an alpha-emitting product isotope; determining the alpha decay rates of the target nucleus and the product nucleus; and using known alpha decay constants for the target nucleus and the product nucleus and the determined alpha decay rates of the target nucleus and the product nucleus to determine the neutron capture rate of the product nucleus.

Abstract: A vibration arrestor for use in combination with the support structure for the upper ends of rod guides disposed in parallel axial relationship in an inner barrel assembly of a pressurized water reactor vessel, the rod guides being supported between a first, lower plate and a second, upper plate with their respective top ends disposed adjacent the second plate. At least for a selected type of rod guides and associated top plates, apertures provided in the top plates receive therein corresponding extensions which depend from the second plate.

Abstract: A full range steam generator level control system and method is provided by a weighted linear combination of a pair of inputs from a low power and a high power controller to actuate feedwater regulation valves.

Abstract: A high pressure seal fitting with a built-in low pressure seal arrangement for sealing a space defined by an inner diameter of a pipe and a rod slidably disposed within the first pipe and extending beyond and end of the first pipe. The fitting includes a fitting body provided with an axial passage for slidably accommodating the rod and having a first end region constructed for engaging the end of the pipe for forming a high pressure seal between the pipe and the fitting body, and a second end region opposite the first end region and including an outer circumferential protrusion having the shape of a ferrule for cooperating with components utilized to form a compression seal to form a releasable high pressure seal. The fitting body further includes a low pressure sealing device disposed in the axial passage at the second end region of the fitting body for maintaining a low pressure seal between the fitting body and the rod when the releasable high pressure seal is disconnected.

Abstract: An inservice inspection of a surface area or welds of a nuclear reactor pressure vessel is carried out, without the need to remove the core barrel and lower internals therefrom, by providing access to the annular chamber between the core barrel and the pressure vessel wall through an aperture in the upper flange of the core barrel. An inspection means, such as an ultrasonic testing device is inserted into the annular chamber through the access and positioned proximate the weld to be inspected and inspection of the weld effected by the device.

Abstract: A pressure control system for a pressurized water nuclear reactor and method for quickly closing the valves associated with the pressurizer thereof has a temperature detection device on the loop seal of each valve and a valve responsive thereto to change water to the loop seal upon a temperature rise therein and stop the flow of water to the loop seal upon a temperature drop therein. The rapid formation of water seals in the loop seals for the valves protects the valve seats from wear and degradation and prolongs the life thereof.

Abstract: A method and apparatus for controlling the magnitude of an analog current through a load to be proportional to the magnitude of an input voltage. A sensing resistor is connected in series with the load. A controllable voltage is applied across the series connection of the load and sensing resistor for driving a current therethrough. A pulse width modulator receives the input voltage and a feedback voltage corresponding to the voltage drop across the sensing resistors when current is conducted thereby and produces square wave pulses each having a pulse width which is adjusted in response to a difference between the magnitudes of the input voltage and the feedback voltage.

Abstract: A tool for maintaining ice baskets associated with a nuclear reactor system. The frame of the tool includes a platform which is disposed on a lattice support structure surrounding a selected and isolated basket. The tool includes an electric drill mounted for vertical reciprocation, in parallel axial relationship with the ice basket, and plural, selectively connectable auger shaft sections having a continuous helical fin thereabout which are connected in succession between the drill and a rotary drill bit, for drilling a hole of the required length, down through the ice within the ice basket. The drill then is maintained at an upper, vertically fixed position and a funnel positioned about the auger; ice chips or flakes are fed into the funnel while the drill is driven in reverse rotation, the auger conveying the ice to the bottom of the ice basket for filling lowermost voids and for filling successively higher voids as the auger is withdrawn.

Abstract: Failure of the control-rod assemblies, particularly the control-rod guides and the WDRC's, by transverse flow of coolant through these members is prevented by directing the flow through a calandria above the guides. To avoid a high pressure drop in the coolant between the calandria and the outlet nozzles, the outlet nozzles are at the same level as the calandria. The calandria has hollow tubes between upper and lower supports. The length of the portion of the tubes between the supports is greater than the diameter of the outlet nozzles.

Abstract: A nuclear reactor including, in the upper internals, a guide structure capable of effectively accommodating and guiding without binding the large number of neutron-absorber rods included in modern reactors of improved efficiency. The neutron-absorber rods include control rods, gray rods, and water-displacement rods. All rods are suspended in clusters from spiders or vanes. The upper internals of the reactor includes cruciform guides for the control-rod and gray-rod clusters. Each of these guides is composed of a plurality of vertical guide sections of transverse cruciform cross section. Plates extending throughout the cross-section of the reactor are supported between each pair of successive guide sections. The plates are perforated, the perforations in each plate being patterned to pass the water-displacement rod clusters. The plates are oriented so that the patterned perforations are aligned to serve as guides for the water-displacement rod clusters.

Abstract: A ferromagnetic material is integrally incorporated with each of the ionic beads of one component of a mixed ionic resin bed containing more than one ionic bead component, such that the one ionic bead component can be separated from the other component by attraction to a magnetic field. Ionic beads containing a ferromagnetic material are attracted to an inhomogeneous magnetic field while other ionic beads devoid of the ferromagnetic material are not so attracted. In another embodiment, a ferromagnetic material having a specific Curie temperature may be incorporated with one ionic bead component while the other bead component contains a different ferromagnetic material having a different Curie temperature.

Abstract: Apparatus for transferring, not only the fuel assemblies, but other component assemblies including control-rod assemblies, thimble-plug assemblies, poison assemblies and the like during refueling of a nuclear reactor. The apparatus includes an outer mast for guiding and protecting the component assemblies which are transferred, an inner mast movable vertically within the guiding mast. The inner mast has grippers for engaging and lifting or lowering fuel assemblies. The outer mast has internal grooved rollers along its length. The inner mast is formed at oppositely facing channels held in a rigid assembly by plates to which the channels are secured. Opposite corners formed by the flanges and the webs of the channels penetrate into the grooves of the rollers and the inner mast is guided and held in position by the rollers. The apparatus also includes an elongated tube within the inner mast movable vertically relative to the inner mast.

Abstract: A gas cooled nuclear reactor is permanently deactivated on occurrence of an emergency by pyrolytic deposition of boron or refractory or stable compounds of boron in the fluid channels of the fuel elements of the reactor. The boron is enriched in boron 10. The deposition takes place in so short a time interval as to preclude a major catastrophe by reason of penetration of water into the reactor. Carbon and/or nitrogen-containing boron compounds are injected directly into the reactor or compounds generated by reaction in the working fluid of the reactor between diborane and other boron hydrides with unsaturated compounds, such as acetylene and ammonia flow through the reactor. The compounds are carried by the working fluid through the core and are pyrolized in the heat of the core to produce more stable boron, or boron-carbon and boron-nitrogen compounds or metal borides which adhere to the walls of the channels in the fuel elements, deactivating the core.