Patent Number: 052251500
Section: description

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Referring to the perspective drawing of FIG. 1 and the cross section of FIG. 2, an integrated head package 22 is provided for a nuclear reactor. The reactor includes a reactor vessel 24 containing nuclear fuel rods carried in a plurality of fuel assemblies 26 between an upper core plate 28 and a lower core plate 32. Each of the fuel assemblies 26 has certain thimble tubes occupying gaps in the pattern of fuel rods, aligned to guide tubes which extend between an upper support plate 34 (shown in FIG. 3) and the upper core plate 28. Control rods 36 as well as instrumentation tubes 42 are movably mounted to be extendable though penetrations 44, 48 in the reactor vessel head 50. The reactor vessel head 50 is a substantial structure, and must withstand pressures in the reactor vessel 24 on the order of 150 bars or about 2,200 psi. The head 50 is sealingly clamped to the reactor vessel 24 by bolts 54. The penetrations 44 for the control rod positioning mechanisms 56 and the penetrations 48 for the instrumentation tubes 42 are capable of withstanding such pressures. Examples of appropriate penetration or seal structures are disclosed, for example, in U.S. patent U.S. Pat. No. 4,983,351--Tower et al; U.S. Pat. No. 3,853,702--Bevilacqua et al, etc. The mechanism 56 for raising and lowering the control rods 36 relative to the fuel assemblies 26 includes control rod positioning shafts 58, which pass through the penetrations 44 in the reactor vessel head 50. A control rod drive coupled to the control rod positioning shafts 58 is disposed above the reactor vessel head 50, but is not shown in order to simply the drawing. The instrumentation tube structures 42 contain sensor arrangements such as a plurality of axially spaced sensors responsive to neutron and gamma radiation, and preferably at least one temperature sensor. The instrumentation tubes 42 can be lowered into certain of the thimble tubes in the fuel assemblies 26 which are not occupied by control rods 36, for placing the sensors in proximity with the fuel rods as well as the coolant in the reactor vessel 24. Electrical couplings for the sensor arrangements extend upwardly through the reactor vessel head 50, the instrumentation tubes 42 and/or their electrical connections likewise passing through penetrations 48 in the reactor vessel head 50 such that the sensor arrangement is retractable relative to the fuel assemblies 26. In the area above the reactor vessel head 50, a seismic support plate 62 is arranged at a space from the reactor vessel head. The seismic support plate 62 provides means for restraining the top of the control rod drive mechanism pressure housing. The seismic support plate 62 must remain precisely positioned relative to the fuel assemblies 26 in the reactor core, so that the control rod positioning shafts 58 always align with their respective thimbles, permitting correct positioning of the control rods 36 even in the event of a seismic disturbance. This preserves the possibility that the reactor can be "scrammed" by fully inserting the control rods 36 into the fuel assemblies 26 to provide maximum damping of nuclear flux. Normally, it would be necessary to couple the seismic support plate 62 to the vessel head 50 by a number of lift rods; however, according to the invention the seismic support plate 62 and the reactor vessel head 50 are coupled by a structurally sound shroud 70, which also provides shielding advantages and provides a means for cooling the mechanisms disposed over the vessel head 50. The shroud 70 is attached to the reactor vessel head 50 and substantially encloses the control rod guide mechanism 56 and at least a portion of the instrumentation tube structures when retracted. The shroud 70 and the reactor vessel head 50 to which the shroud 70 is attached form a structural element of sufficient strength to support the vessel head 50, the control rod guide mechanism 56 and the instrumentation tube structure 42. This arrangement enables the whole integrated head package 22 to be removed from the reactor as a unit for servicing the contents of the reactor vessel 24. At its bottom 72, adjacent the reactor vessel head 50, the shroud 70 is substantially thicker than at its top 74. For example, the shroud 70 can be on the order of five inches (13 cm) thick at the bottom 72, and three inches (8 cm) thick at the top 74. The shroud 70 is shaped as a cylindrical tube, and is attached by welding or bolts to the reactor vessel head 50. The bottom edge of the shroud can be reinforced or provided with a structure which assists in effecting the structural attachment of the shroud and the vessel head. As shown in FIGS. 1 and 2, the bottom edge of the shroud can have a flange 76 providing an attachment to the vessel head 50, preferably including a collar member 82 which is welded to the vessel head 50 and to the flange 76 on the shroud 70, respectively. When it is necessary to remove the reactor head 50 for servicing the reactor contents, the control rods 36 are lowered and the instrumentation tubes 42 are retracted upwardly from the fuel assemblies. The lowermost portions of these structures are the most heavily irradiated because they are placed in close proximity to the fuel rods when the reactor is operational. The reactor vessel 24 is depressurized, and the reactor head 50 is unbolted from its attachment to the vessel. As shown in FIG. 3, a lifting apparatus such as the polar crane normally provided in the reactor containment building is then engaged with the integrated head structure 22, and the entire head structure is lifted away. A pedestal-like support over a pool of water can be provided to support the vessel head, the control rod drive mechanisms and the instrumentation tube structures. The thickest and therefore most effective shielding portions of the shroud protect against escape of radiation from the lowermost, most heavily irradiated portions. Preferably, the head structure includes a lifting rig 92 disposed over the seismic support plate 62, and attached thereto, with the withdrawn instrumentation tube connecting lines 86 passing along the spreader frame 84. At the top of the lifting rig 92, a clevis 88 or similar fitting is provided for coupling to the polar crane, e.g., using a connecting pin. The spreader frame, however, does not support the weight of the integrated head structure 22. For this purpose, a plurality of lift rods 92 couple between the crane clevis 88 and the seismic support plate 62. For example, three lift rods at 120.degree. spacing can be provided between the crane clevis 88 and the seismic support plate 62. The seismic support plate 62 is rigidly fixed to the top edge 94 of the shroud 70, and accordingly the force exerted by the polar crane or other lifting apparatus is applied at the seismic support plate 62 and top shroud edge 94 to lift the head structure 22 away from the reactor vessel 24. In the embodiment shown, the top edge 94 of the shroud 70 is thickened via buttress fittings 96 for each of the lift rods 92. The buttress fittings 96 comprise a downwardly opening channel enclosing over the inside and outside of the shroud 70 at the top 94. The uppermost portion of the buttress fittings is bored and threaded for receipt of a connecting bolt 97 that protrudes through the seismic support plate 62. Nuts 98 provided on the connecting bolt over and under the seismic support plate 62 allow accurate positioning of the seismic support plate 62 as well as a means for rigidly fixing the seismic support plate 62 to the shroud 70. The buttress fittings 96 can be welded to the shroud 70. The shroud 70 is made of steel or similar material which attenuates radiation. Although the shroud 70 in the embodiment shown has two stepwise variations in thickness, it would also be possible to provide additional steps, or a continuous decrease in thickness from the lower portion adjacent the vessel head 50 proceeding upwardly, whereby lower portions of the instrumentation tubes 42 and the like are preferentially shielded by the shroud. FIG. 3 shows the integrated head package 22 of the invention as engaged using the overhead crane or similar lifting apparatus 102, for example having a travelling winch 104. The lifting apparatus 102 is coupled to the clevis fitting 88 at the top of the head package 22. The reactor head 50 is unbolted from the reactor vessel and the entire head package 22 can be lifted away from the reactor, for example to be placed on support 110 therefor. The connection between the lifting apparatus is structurally secure due to the rigid connection defined by the clevis fitting 88, lift rods 92, seismic support plate 62, shroud 70 and reactor head 50. Insofar as the lower more irradiated portions of the instrumentation tubes 42 can be retracted to where they reside above the reactor head 50, the thicker lower section 72 of the shroud 70 shields against escape of radiation. This arrangement can be supplemented using a support structure as shown, having an internal shielded area 112 for the extreme lowermost portions 114 of the instrumentation tubes, which may still extend below the reactor head. The invention having been disclosed in connection with preferred embodiments, a number of variations according to the invention will now become apparent to persons skilled in the art. Whereas the invention is intended to cover a reasonable range of variations in addition to the preferred embodiments discussed in detail, reference should be made to the appended claims rather than the foregoing specification, in order to assess the scope of the invention in which exclusive rights are claimed.