Abstract:
An emergency core coolant system for cooling the nuclear core of a nuclear reactor. A storage tank having a supply of coolant fluid therein is positioned outside of the reactor vessel and communicates through conduit means to an inactive plenum within the reactor vessel. Two distribution means are provided within the reactor vessel to flow couple the inactive plenum to the nuclear core, the two distribution means communicating with the inactive plenum at two different vertical elevations. Normally closed valve means is interposed in the conduit means and is operable to be opened in the event of an emergency to introduce coolant fluid in the tank means into the inactive plenum. The coolant fluid in the inactive plenum is then distributed to the nuclear core by the two distribution means.
Abstract:
A guide structure for aligning fuel assemblies forming a nuclear core of a nuclear reactor and for guiding a plurality of control elements for telescoping movement within guide channels of fuel assemblies. Two spaced tube sheets, rigidly connected by a plurality of hollow tubes extending therebetween, are supported by a support means relative to the nuclear core with each of the hollow tubes being in alignment with a guide channel of the fuel assemblies. A plurality of yoke means, each of which interconnects at least two of a plurality of control elements situated within some of the hollow tubes, are provided whereby the interconnected control elments telescopingly move as a unit within the guide channels.
Abstract:
A hydraulic actuator for a nuclear reactor control rod assembly which may be positioned entirely within a reactor pressure vessel. The actuator is characterized by a lift piston which cooperates with the fuel assembly upper end fitting, at the lower end of the piston guide cylinder, and with a lift buffer assembly, at the upper end of the cylinder, to provide for both lifting of the control rod and for holding the control rod at the two limits of motion thereof.
Abstract:
1. In a nuclear reactor, the reactor including a pressure vessel with a fuel assembly disposed therein and means for circulating a coolant under pressure through the vessel, the fuel assembly comprising a plurality of fuel elements containing fissionable material, an improved control system comprising: a plurality of guide tubes for movable neutron absorber elements extending through the fuel assembly, said guide tubes terminating within the pressure vessel; upper end filtering means, the upper end of each guide tube being terminated in said upper end fitting means, said upper end fitting means including a tubular extension for each guide tube, the upper end of said tubular extensions defining valve seats; buffer means positioned in the pressure vessel above and axially aligned with each of said end fitting means tubular extensions; tubular hydraulic cylinder defining means extending between the upper end of each of said tubular extensions and said buffer means; actuator piston means disposed for movement in each of said tubular cylinder defining means, each of said actuator piston means having an upper surface cooperating with said buffer means for valving action and a lower surface cooperating with said upper end fitting means defined valve seat to perform a valving action; neutron absorber element means disposed for movement in each of the guide tubes; means mechanically coupling each of said actuator piston means to associated absorber element means whereby the absorber element means may be moved relative to the fuel elements; means located externally of the pressure vessel for generating a control pressure; a plurality of control lines penetrating the pressure vessel, said control lines being commensurate in number with the actuator piston means and extending from said control pressure generating means to respective of said control pressure to the upper surfaces of said actuator piston means; valve means disposed in each of said control lines for selectively applying said control pressure to said hydraulic cylinder defining means through said buffer means to said upper surface of said actuator piston means whereby said absorber elements may be individually adjusted between positions commensurate with full insertion into and full retraction from the fuel assembly; and means for applying the pressure vessel internal coolant pressure to the lower surfaces of said actuator piston means.
Abstract:
A NUCLEAR REACTOR FUEL ASSEMBLY CONTAINING A PLURALITY OF SPACED, PARALLEL FUEL RODS IS PROVIDED WITH FLOW DEFLECTOR VANES THAT OPERATE ON THE LIQUID COOLANT FLOWING ALONG CHANNELS BETWEEN ADJACENT FUEL ELEMENTS TO PROMOTE MIXING OF THE COOLANT AND ALSO TO PRODUCE MORE EFFECTIVE CONTACT OF THE FUEL ROD SURFACES WITH THE LIQUID. THE VINES ARE OF PARTUCULAR CONFIGURATION AND ARE INTEGRALLY FORMED ON TWISTED, THIN METAL RIBBON STRIPS, THE RIBBON STRIPS CAN BE INDIVIDUALLY DISPOSED BETWEEN ADJACENT ROWS OF FUEL ELEMENTS OR INTERCONNECTED TO FORM A GRID-LIKE STRUCTURE THROUGH WHICH THE FUEL ELEMENT EXTEND.
Abstract:
The removable head of a pressure vessel enclosure for a nuclear reactor is penetrated by a bundle of hydraulic control lines. The vessel top head is provided with a single aperture and a connector assembly is installed in the aperture; the connector assembly providing leak proof coupling of external control lines to corresponding internal control lines of the bundle.
Abstract:
A flow twister for coolant fluid flowing longitudinally in channels between spaced parallel nuclear reactor fuel rods positioned laterally by a grid of intersecting grid members extending transversely of and between said rods. The twister is a twisted metallic tab of cruciform cross section positioned at a grid intersection and located in and extending longitudinally of a channel an having one end secured to a grid and the other end free.
Abstract:
Control line penetration of a nuclear reactor pressure vessel is achieved through the side of the vessel below the junction of the vessel main barrel portion and the reactor head. The control lines enter the pressure vessel in the form of a bundle of conduits at a point which is out of the main coolant flow path and the control lines are provided with disconnect means internally of the vessel.