Patent Number: 043137954
Section: description

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Referring to FIG. 1, a schematic arrangement of the nuclear power plant of this invention designated generally by the reference numeral 10 is shown. The power plant is constructed with a large, elongated, high-pressure containment vessel 12 which is vertically oriented, with a substantial portion of the vessel located below ground level 14. The pressure vessel is segmented for ease of fabrication and for component assembly and disassembly when broken down for site transfer or retirement. Within a lower central segment 16 of the pressure vessel is located a reactor core 18 of the fast breeder, sodium cooled type. The reactor core is immersed in a molten sodium heat extractor medium 20 as in a conventional sodium reactor. The molten sodium extracts the heat of the thermal nuclear reaction and by conduction, transfers the heat throughout the extractor medium. However, instead of cycling the molten sodium to a conventional heat exchanger for production of steam, the molten sodium is simply confined by the pressure vessel and employed as a thermal bath into which is immersed a plurality of thermal conductor rods 22. The thermal conductor rods 22 are arranged in a geometric bundle, each rod spaced from its neighbor to maximize the effective surface area of the rod bundle. Therefore, in interfacing the substantial quantity of liquid sodium in an upper central segment 24 of the pressure vessel, the heat transfer is maximized. The elongated conductor rods 22 extend the length of the upper central segment 24 of the pressure vessel and pass through a seal and support gasket 26, which hermetically isolates an upper segment 28 of the pressure vessel from the upper central segment 24. The gasket 26 concurrently supports the conductor rods 22 in mutual displacement for the heat transfer optimization as noted above. The rods may be solid steel or iron rod stock or steel or iron tube encasing a more conductive aluminum core. The conductor rods extend through the gasket 26 into a chamber 30 defined by the upper segment 28 of the pressure vessel. The chamber 30 has an inlet fitting 32 and an enlarged outlet fitting 34 for cycling a gas, preferably superheated steam, through the chamber. During cycling through the chamber 30 on the path defined by the baffles 35, the gas encircles the conductor rods 22 and absorbs the heat transferred by the rods from the sodium bath. The added thermal energy substantially increases the heat content of the steam which is used to drive a multi-stage steam turbine 36 preferably designed for equal stage nozzle velocity and low pressure drive. A steam turbine utilizing the concepts disclosed in U.S. Pat. No. 4,178,125, issued Dec. 11, 1979, entitled Bucket-Less Turbine Wheel by Hector A. Dauvergne, can be economically designed for the contemplated low pressure and low temperature drive conditions which are encountered in the steam cycle of the present invention. The steam turbine is connected to the outlet fitting 32 of the upper segment 28 of the pressure vessel. The steam turbine drives a conventional on line electrical generator 38, and an on line gas compressor 40. A custom compressor can be designed, specially adapted for this cycle. However, since the steam is retained as a gas in the entire cycle a conventional gas compressor can be used with satisfactory results. The compressor compresses the expanded steam, from which a substantial portion of the thermal energy has been lost to power generation in the turbine, and partial condensation to a volume that is convenient to recycle to the pressure vessel chamber. To achieve the thermal economic advantages, a plurality of conventional heat pipes 41 or suitable condensors are incorporated adjacent the compressor inlet. The heat pipes 41 act as conditioners to isothermically reduce the latent heat for the gas compressor operation and transfer the heat by air fins 43 or to some other low temperature device for use. For optimum safety the power generation cycle can operate at relatively low temperatures and pressures. For example, with a molten sodium extractor medium at 1000.degree. F., the rods would heat to approximately 800.degree. F. in the chamber end of the pressure vessel. With steam pressure in the chamber at 166 psia, the superheated steam would drop to a temperature of approximately 287.degree. F. and pressure of 55 psia in the tubine exhaust. After heat is transferred by the heat pipes 41, and work is expended on the wet steam by the gas compressor, the wet steam would rise to a temperature of about 366.degree. F. and pressure of 167 psia in delivery pipe line 44 before entry into the heat chamber 30 of the pressure vessel for superheating to 800.degree. F. This cycle is shown in temperature-entropy graph of FIG. 3. The curve defines the wet steam zone under the curve. To the left the wet steam becomes saturated and to the right the steam becomes superheated. At point 1, the wet steam is still displaced from the saturation point at 0. It can therefore be compressed to point 2, causing a temperature increase and reach its limit before saturation. Heat is added to the saturated steam by the rods source and it will remain at constant temperature from point 2 to 3 where further heat addition will cause the steam to become superheated or dry steam rising in temperature to approach the temperature of the external heat source, point 4. Between point 4 and point 5 the steam is available for work where it falls in temperature and pressure until no further work can be practically removed. Before compressing, further heat is removed to relieve the burden on the compressor. The exemplar cycle would operate in the following parameters: ______________________________________ Point Temperature Pressure ______________________________________ 1 287 55 2 366 166 3 366 166 4 800 166 5 287 55 ______________________________________ While the cycle of FIG. 3 defined by the numerals is provided as a primary exemplar, it is to be understood that variations therein are possible. Instead of removing a substantial portion of the heat from the work expended steam at point 5 to point 1, where compression to point 2 will still fall short of liquifying the steam, heat can be removed to alternate points (a) or (aa), for example. On compression, the added heat will not cause the steam to become superheated as the desired pressure is achieved, the steam rising to points (b) or (bb). This is still within the curve defining the points at which the steam becomes superheated. While the heat transfer means by the solid state conductor rods could be employed to boil water for a conventional steam generator-condensor cycle by introducing water to the heat chamber 30, the superheated steam cycle is preferred where safety is a primary consideration. By a simple common rotor/drive shaft 46 the three components of the power generating system, the turbine 36, the generator 38 and the compressor 40 can be most efficiently arranged. The disposal and storage features of the subject nuclear power plant are based on the premise that transportation of nuclear wastes is to be minimized and preferably avoided. It is proposed that the nuclear power plant be in the first instance located where it is desirable to temporarily store the nuclear wastes. By temporary storage, it is intended that such storage be for the period necessary to resolve the problem of permanent storage or deactivation of the radioactivity. It is also proposed that the plant itself be designed with an integral storage facility such that the nuclear waste is not removed from the reactor plant, further reducing transportation dangers. In the nuclear plant devised, the pressure vessel 16 has a lower segment 48 defining a chamber 50 which comprises a dump for multiple expended reactor cores 52. When the operating core 18 in the lower central segment 53 of the pressure vessel becomes reduced to the point it is no longer efficient, an upper slide valve 54 located immediately above the core 48 is extended by a screw mechanism 56 into the pressure vessel 16 to isolate the core and the immediately surrounding sodium medium. A lower slide valve 58 is then withdrawn by a similar screw mechanism 60 allowing the expended core and surrounding sodium medium to drop into the dump. The lower slide valve 58 is then replaced and a new core installed through control rod and access portion 62. The sodium is replenished and upper slide valve 54 withdrawn for resumed operation. The core 48 is shown only schematically and it is to be understood that it is to be of conventional design and mounted and installed in the pressure vessel in a conventional manner. For convenience of operation, control rods may adventageously be horizontally oriented for manipulation through the access port. The dump may contain a control medium for inhibiting further nuclear reaction and if desired may contain adequate control means to curtail a chain reaction in a core introduced into the dump by meltdown. An alternate structure to the storage chamber 50 of FIG. 1 can be incorporated with the power plant arrangement for longer term storage than is recommended with the pressure vessel segment 48. The storage structure 70 of FIG. 2 is designed for storage of wastes for a period of at least fifty years. Because of natural shifts in the earth, it is desirable to avoid elongated storage cannisters which may be subject to shear type forces that can cause a rupture of the cannister. Ideally, the container should be spherical such that shear forces are avoided and acting earth forces become compressive in nature. In FIG. 2, the lower central segment 53 of the pressure vessel 16, shown segmented, is connected to a sleeve 72, which is inserted into the uppermost of a series of spherically shaped container vessels 74. The upper container vessels 74 comprise conduits 75 and have an opening at the top and bottom through which wastes can pass to the bottom container vessel which comprises a spherical storage container 76. Each of the upper conduits 75 is seated on an integral flange 78 on the conduit 75 or container 76 below. The seating being spherical in contour and which may be precision ground is such that a seal is maintained even though adjacent vessels have shifted slightly. The conduits and storage container are preferably fabricated from concrete ceramic or glass to prevent deterioration. Below the container 76 is a support base 80 for supporting the column 82 formed in the container vessels 74. Surrounding the column 82 is a packing 84 of salt which prevents the introduction of moisture to the vicinity of the stored wastes. The salt packing also provides a lateral support to the column of floating container vessels. For stability, the salt packing 84 is encompassed by a peripheral layer of sand 86 and an outer layer of stone 88 before interfacing the local terrain 90. In this manner, the column can withstand relatively large shocks in the surrounding terrain and maintain its integrity. While there are additional controls and components necessary for on-site operation, these controls and components are known to those skilled in the art. The above disclosure is intended to present to those skilled in the art a system combining substantially conventional components into a novel arrangement for safe operation. While in the foregoing specification embodiments of the present invention have been shown in considerable detail for the purposes of making a complete disclosure of the invention, it will be apparent to those of ordinary skill in the art that numerous changes may be made in such details without departing from the spirit and principles of the invention.