Abstract:
A device for guiding a nuclear reactor control cluster comprises guide tubes provided in the fuel assemblies, and in the upper internals, a tubular casing having an upper closure with a hole for passing the cluster drive shaft, horizontal guide plates spaced apart along the casing and cut out so as to let the spider pass and to guide the elements of the cluster, and split tubes for guiding individual elements for protecting the elements from the action of the coolant. Openings are provided immediately below the plates at the top of each internal between the guide plates. The guide tubes in a lower portion of the casing are devoid of openings other than to a slit for passage of a spider carrying the cluster.
Abstract:
A method is disclosed for controlling a PWR comprising a plurality of control bars selectively and individually positioned in the reactor core. The current value of an operating parameter indicative of the power level (for instance the average temperature of the core) is measured as well as the current positions of the control bars and the axial power offset in the core. When the difference between the current value of the operating parameter and the set value exceeds a predetermined deadband interval or the axial power offset in the core exceeds a reference value, the amount by which the reactivity of the core should be modified is computed. Through a simulation process on a model of said reactor, it is determined which ones of the bars may be moved and which are the amounts of travel to be given to the bars for bringing the difference within the deadband and the offset toward the reference value while minimizing a core enthalpy increase factor.
Abstract:
A high temperature nuclear control rod assembly comprises a plurality of substantially cylindrical segments flexibly joined together in succession by ball joints. The segments are made of a high temperature graphite or carbon-carbon composite. The segment includes a hollow cylindrical sleeve which has an opening for receiving neutron-absorbing material in the form of pellets or compacted rings. The sleeve has a threaded sleeve bore and outer threaded surface. A cylindrical support post has a threaded shaft at one end which is threadably engaged with the sleeve bore to rigidly couple the support post to the sleeve. The other end of the post is formed with a ball portion. A hollow cylindrical collar has an inner threaded surface engageable with the outer threaded surface of the sleeve to rigidly couple the collar to the sleeve. the collar also has a socket portion which cooperates with the ball portion to flexibly connect segments together to form a ball and socket-type joint. In another embodiment, the segment comprises a support member which has a threaded shaft portion and a ball surface portion. The threaded shaft portion is engageable with an inner threaded surface of a ring for rigidly coupling the support member to the ring. The ring in turn has an outer surface at one end which is threadably engageably with a hollow cylindrical sleeve. The other end of the sleeve is formed with a socket portion for engagement with a ball portion of the support member. In yet another embodiment, a secondary rod is slidably inserted in a hollow channel through the center of the segment to provide additional strength. A method for controlling a nuclear reactor utilizing the control rod assembly is also included.
Abstract:
A mounting system for removably mounting the lower flange of the control rod guide tube over an opening in the upper core plate of a nuclear reactor is disclosed. The system includes a pair of resilient pin members and a pair of reinforcing pin members. The resilient pin members are mounted in a passage formed through first opposing sides of the guide tube lower flange. They are resiliently receivable in first bores formed on first opposing sides of the upper core plate to permit deflection thereof when the guide tube is subject to normal shear loads. The resilient pin members bear substantially all of the normal shear load to which the guide tube is subjected. The reinforcing pin members are mounted on the second opposing side of the guide tube lower flange. They are receivable in second bores formed on the second opposing sides of the upper core plate with a clearance. The reinforcing pin members bear substantially all of the abnormal shear load that exceeds the normal shear load. The clearance between the reinforcing pin members and the second bores limits the deflection of the resilient pin members. After the resilient pin members deflect the distance limited by the clearance, the reinforcing pin members bear any additional abnormal shear loads and prevent the additional abnormal shear loads from bearing on the resilient pin members.
Abstract:
A pressurized water reactor of an advanced design comprises, in vertically spaced relationship, a lower barrel assembly having lower and upper core plates, an inner barrel assembly and an axially removable calandria assembly having a lower calandria plate. A plurality of rod guides are cantilever-mounted in parallel axial relationship within the inner barrel assembly and, specifically, are rigidly mounted at the lower ends thereof to the upper core plate. Axially extending sleeves are affixed to the upper ends of the rod guides and telescopingly receive therein generally cylindrical supports which are affixed to and depend downwardly from the lower calandria plate and define alignment axes for the respectively associated rod guides. Links are secured at first ends to the mount and extend radially therefrom at angularly displaced positions, second, free ends of the links being free to move in pivotal rotation from a normal, downward and radially inward position to an upward and radially outward position, when engaged by receiving means formed in the upper ends of the sleeves as the calandria assembly is moved into assembled relationship with the inner barrel assembly. In the assembled relationship, the links, moved fully to the upward and radially outward positions, produce resilient, lateral loading between the respective sleeves and cylindrical mounts and maintain alignment of the associated sleeves and rod guides with the respective alignment axes.
Abstract:
A gas-cooled high temperature reactor is provided having a core filled with spherical fuel elements, in combination with a graphite side reflector including at least one nose-like projection protruding radially into the reactor core from said graphite said reflector, the at least one nose-like projection including at least one vertically disposed cavity adapted to receive discrete absorber material elements introduced into said reactor core as well as a vertically disposed continuous opening which permits communication between said cavity and the core of the reactor, said opening having a maximum width adjacent said cavity which is less than the minimum dimension of said discrete absorber material elements in order to prevent passage of said elements into said continuous opening from said cavity.
Abstract:
A replacement station includes an old split-pin-assembly (OSPA) removal stand and a new split-pin-assembly (NSPA) installation stand. The removal stand includes a saw and a drill. With the guide tube to which the OSPA is secured in the removal stand, the saw severs each OSPA below the flange which engages the base of the lower counterbore in the lower guide tube (LGT) separating the OSPA into a pin fragment and a second fragment including the flange and the remainder of the split-pin with the nut threaded into it. The second fragment remains secured to the LGT after the sawing operation. The guide tube is rotated so that the drill is coaxial with the shank of the pin of the second fragment. The second fragment is separated into a third fragment including the flange and a fourth fragment including the remainder of the pin and the nut both removable from the LGT. The installation stand has NSPA blades in which the new split pins are mounted. The LGT sans the OSPA's is positioned on the installation stand. The new nuts are mounted and torqued into the split pins with a long-handled runner and a torque tool permitting a measured torque to be applied to the new nut. Then the cups on the nuts are crimped by a long-handled crimping assembly which has fixed crimping jaws that produce the crimping by moving parallel to the wall of the cup.
Abstract:
A cutting tool is manually operable from above the water level in a reactor cavity pool to sever locking cups from the socket-head cap screws which hold guide tubes to the upper support plate of the upper internals of the reactor. The tool includes a support assembly adapted to be mounted on the guide tube. A motor frame is mounted on the support assembly for limited vertical movement with respect thereto and carries a hydraulic motor coupled by a vertically depending shaft to a tubular cutter for rotating same about its axis. The shaft extends through an opening in the support assembly and through a locating tube which surrounds the cutter and is receivable over the associated locking cup when the support assembly is mounted in place. A drive screw is coupled to the frame and to a shaft which extends up to the coupling tube to a manually operable crank to effect vertical movement of the frame and the cutting means coaxially with respect to the locking cup to sever its top wall from its side wall.
Abstract:
Disclosed is a nuclear power plant comprising a high-temperature pebble bed reactor contained in a cylindrical steel pressure vessel in which an upper part of the cylindrical steel pressure vessel, which contains a heat utilization system, is retracted and equipped with a cover upon which circulating blowers are placed. The heat utilization system comprises, in a known manner, a single steam generator. The steam generator comprises at least two sub-systems independent of one another, with their own distributors and collectors, and with their own inlet and outlet lines. A first shut-down arrangement comprises a plurality of absorber rods insertable into bores of the side reflector from above and comprises rod drives arranged outside the steel pressure vessel in the area of its retracted upper part. A second shut-down arrangement comprises small absorber spheres for introducing into the core of the reactor, and several storage containers and annular conduits for said spheres. The storage containers are also arranged outside the steel pressure vessel in the area of its retracted upper part. Annular conduits for the introduction of the small absorber sphere are, however, disposed inside the steel pressure vessel and connected with channels provided in projections of the side reflector protruding into the core.
Abstract:
Anti-ejection device for nuclear reactor control rod.The reactor comprises a tight enclosure integral with the nuclear reactor vessel, the control rod being integral with the command bar. A system for manipulating the command bar comprises means for locking it. These means lock the command bar with respect to the tight enclosure for as long as the force exerted on this bar remains below a limit value. This limit value is at least equal to the force exerted on the command bar in the case of an accidental external cause urging the control rod to leave the reactor core. The device comprises means for obtaining a translation of the control rod, by exerting a force exceeding said limit value on the command bar.