摘要:
The present invention provides novel fuel assemblies for use with PWR nuclear reactors and power plants, and in particular, VVER nuclear reactors. The fuel assemblies offer enhanced structural stability, skeletal rigidity, and distortion (bow and twist) resistance to support high burn-up fuel management. Each fuel assembly may include a plurality of fuel rods, a plurality of control rods and guide thimbles, at least one instrumentation tube, and a plurality of grids. At least one fuel rod is replaced with a structural support replacement rod made from zirconium (Zr) alloy, stainless steel, or any other suitable material. The structural support replacement rod may be hollow or solid. The structural support replacement rods are preferably disposed at or about the periphery, and in some cases, the corners of the geometric array, which is preferably a hexagon or square.
摘要:
An apparatus is disclosed for determining pressurization in a nuclear fuel rod and the like by measuring the increase in diameter of the fuel rod occasioned by the internal pressurization of the rod, and which includes an elongate receiving member having front and rear ends and an axial opening extending therein. A gauge is positioned in the axial opening and is adapted to coaxially surround the fuel rod and then measure an increase in diameter of a fuel rod caused by a pressure increase within the rod. The gauge is formed from a substantially C-shaped bracket having inner and outer surfaces, spaced distal end portions and a more thin medial portion, and with a strain gauge mounted on both the inner and outer medial surfaces. A microprocessor is connected to the strain gauges so that changes in electrical output from the strain gauges can be measured to determine the increase in diameter of the fuel rod upon pressurization of the fuel rod.
摘要:
A nuclear fuel assembly component such as a control rod that has a cylindrical insert such as neutron absorbing material that is closely received within a cladding that is sealed at either end with end caps. The cylindrical member has grooves formed in its side wall extending from an upper surface to a lower surface to permit air to escape from the cladding as the cylindrical member is loaded into the cladding during manufacture.
摘要:
A nuclear fuel assembly having a tube-in-tube control rod guide tube design that incorporates an end plug that extends axially upward to an elevation above the lower most grid where it is sealed at its upper end to the lower end of the control rod guide tube. The guide tube lower end plug has a threaded recess in its upper surface that mates with a corresponding dashpot end plug threaded extension that is formed as an insert in the lower end of the guide tube. A hole formed through the outer wall of the guide tube end plug at the elevation of the lower portion of the recess provides a positive inspection port for assuring the proper seating of the dashpot. A method of manufacture of such a fuel assembly is also disclosed.
摘要:
A reconstitutable control assembly has a spider structure which supports control rods by detachable attachment joints. Each attachment joint includes a hollow connecting finger on the spider structure and an elongated detachable split upper end plug on each control rod. The split upper end plug includes a pair of separate upper and lower plug portions. The upper plug portion has upper, middle and lower sections, whereas the lower plug portion has upper, middle and lower segments. The upper section of the upper plug portion is rigidly attached to the connecting finger on the spider structure, whereas the lower segment of the lower plug portion is rigidly connected to the control rod. Also, the lower section of the upper plug portion and the middle segment of the lower plug portion have complementary threads defined thereon for rigidly threadably attaching the upper and lower plug portions to one another. Two embodiments of locking features can be used in conjunction with the upper and lower plug portions for locking them together so as to resist their unthreading from one another.
摘要:
An advanced gray rod control assembly (GRCA) is for a nuclear reactor. The reactor has a plurality of fuel assemblies each including numerous elongated fuel rods supported in an organized array by substantially transverse support grids, and a plurality of guide thimbles disposed through the support grids and along the fuel rods. The GRCA includes a spider assembly structured to provide controlled insertion of gray rod assemblies within the thimbles of the fuel assembly, thereby controlling the rate of power produced by the reactor. Each gray rod assembly includes an elongated tubular member, a first end plug, a second end plug, a substantially pure silver neutron-absorber disposed within the tubular member, and a support tube surrounding the neutron-absorber within the tubular member to resist silver-swelling. Delta-power of the reactor is improved by minimizing the exposed surface area of the absorber and distributing it among all of the rods of the GRCA.
摘要:
A double enclosure top nozzle subassembly for a nuclear fuel assembly includes an upper structure having a top plate and an outer depending peripheral sidewall enclosure, a lower structure having a lower adapter plate and an inner upstanding peripheral sidewall enclosure disposed below the top plate and within the outer sidewall enclosure. The outer and inner sidewall enclosures are slidably movable relative to one another as the top plate moves toward and away from adapter plate. A plurality of resiliently-yieldable biasing devices, such as leaf springs extend between and engage the top plate and lower adapter plate. Interengagable structure on the lower and upper edges of the respective outer and inner sidewall enclosures limit movement of the top plate and lower adapter plate away from one another so as to retain the outer and inner sidewall enclosures in sliding contacting relationship together. The leaf springs are movable between compressed and expanded states in response respectively to application and removal of a hold-down force on the upper structure in the direction of the lower structure for permitting and causing movement of the top plate toward and away from the adapter plate and thereby the top nozzle subassembly between compressed and expanded conditions.
摘要:
An expandable top nozzle subassembly for a nuclear fuel assembly includes an upper structure having a top plate and a depending peripheral sidewall enclosure, a lower adapter plate disposed below the top plate and within the enclosure with the adapter plate and sidewall enclosure being slidably movable relative to one another so as to move the top plate toward and away from adapter plate, and a plurality of resiliently-yieldable biasing devices extending between and engaging the top plate and lower adapter plate. Interengagable structure on a lower edge of the enclosure and on a peripheral edge of the adapter plate capture and retain the adapter plate within the enclosure upon movement of the enclosure relative to the adapter plate which moves the top plate away from the adapter plate. The biasing devices in the form of coil springs are movable between compressed and expanded states in response respectively to application and removal of a hold-down force on the upper structure in the direction of the adapter plate for permitting and causing movement of the enclosure relative to the adapter plate so as to move the top plate toward and away from the adapter plate and thereby the top nozzle subassembly between compressed and expanded conditions.
摘要:
A fuel assembly in a nuclear reactor has a spectral shift apparatus including a plurality of displacer rods for controlling reactivity in the assembly and an apparatus for refurbishing the displacer rods for reuse. Each displacer rod contains a quantity of water equivalent to a small fraction of the rod volume. Also, the spectral shift apparatus includes a manifold with a central plenum and a rupturable disk connected to the manifold. The manifold is connected in flow communication with the displacer rods. The disk which seals the displacer rods as well as the manifold plenum is rupturable at a given pressure differential thereacross so as to allow entry of the moderator/coolant liquid into the manifold and rods. Also, a screen adjacent the disk restricts it to rupturing in one direction only. The spectral shift refurbishing apparatus includes a charging tool insertable within the manifold plenum and separate air and water conduits interconnecting the manifold and upper and lower portions of the respective displacer rods in flow communication so as to provide respective entrance paths for air under pressure from the charging tool to the upper rod portions and separate exit paths for liquid from the lower rod portions to the charging tool such that introduction of air under pressure along the entrance paths will force liquid from the rods along the exit paths until the level of the liquid within the rods lowers to the level of the conduits in their lower portions.
摘要:
A high energy absorption top nozzle for a nuclear fuel assembly that employs an elongated upper tubular housing and an elongated lower tubular housing slidable within the upper tubular housing. The upper and lower housings are biased away from each other by a plurality of longitudinally extending springs that are restrained by a longitudinally moveable piston whose upward travel is limited within the upper housing. The energy imparted to the nozzle by a control rod scram is mostly absorbed by the springs and the hydraulic affect of the piston within the nozzle.