Pressurized water reactor with upper vessel section providing both pressure and flow control
10047749 ยท 2018-08-14
Assignee
Inventors
Cpc classification
F04D29/606
MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
Y02E30/30
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
G21C19/28
PHYSICS
F04D7/08
MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
G21C1/32
PHYSICS
Y10T29/49229
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
International classification
G21C19/20
PHYSICS
F04D7/08
MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
G21C1/08
PHYSICS
G21C1/32
PHYSICS
G21C19/28
PHYSICS
Abstract
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central riser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum. A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.
Claims
1. A method comprising: installing a reactor coolant pump comprising a pump motor, a driveshaft, and an impeller on a pressurized water reactor (PWR) comprising a pressure vessel, a nuclear reactor core disposed in the pressure vessel, and an internal pressurizer located at the top of the pressure vessel, the installing including: mounting the pump motor at an opening of the pressure vessel with the mounted pump motor located outside of the pressure vessel and supported on the pressure vessel by a mounting flange, and an axis of rotation of the mounted pump motor being vertical, inserting the impeller inside the pressure vessel, and after the mounting and inserting, operatively connecting the inserted impeller to the mounted pump motor with the drive shaft, wherein a vertical height of the mounted pump motor overlaps the internal pressurizer; and no portion of the installed reactor coolant pump passes through the internal pressurizer.
2. The method of claim 1, wherein the drive shaft is operatively connected with the pump motor prior to the mounting and the mounting includes inserting the drive shaft into the opening of the pressure vessel.
3. The method of claim 1, wherein the opening of the pressure vessel is too small for the impeller to pass through, and the method further comprises: inserting the impeller inside the pressure vessel through a manway of the pressure vessel that is separate from the opening at which the pump motor is mounted.
4. The method of claim 1, wherein the opening of the pressure vessel includes a self-lubricating bearing and the mounting comprises: inserting the drive shaft into the opening of the pressure vessel such that the drive shaft is supported in the opening by the bearing.
5. The method of claim 1, wherein the mounting is performed before the inserting such that the pump motor is supported on the pressure vessel by the mounting flange before inserting the impeller inside the pressure vessel.
6. The method of claim 1, further comprising: subsequent to installing the reactor coolant pump on the PWR, replacing the impeller with a replacement impeller, the replacing including: removing the impeller from the pressure vessel without detaching the drive shaft from the motor and without dismounting the pump motor from the opening of the pressure vessel, and installing the replacement impeller on the drive shaft while the drive shaft remains attached with the motor and while the pump motor remains mounted at the opening of the pressure vessel by the mounting flange.
Description
BRIEF DESCRIPTION OF THE DRAWINGS
(1) The invention may take form in various components and arrangements of components, and in various process operations and arrangements of process operations. The drawings are only for purposes of illustrating preferred embodiments and are not to be construed as limiting the invention.
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DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS
(11) With reference to
(12) In its operating state, the pressure vessel 10 of the PWR contains primary coolant water that serves as primary coolant and as a moderator material that thermalizes neutrons. The illustrative PWR includes an integral pressurizer as follows. A separator plate 20 is disposed in the cylindrical pressure vessel 10. The separator plate 20 separates the pressure vessel 10 to define: (1) an internal pressurizer 22 containing a pressurizer volume disposed above the separator plate 20; and (2) a reactor vessel portion 24 defining a reactor volume disposed below the separator plate 20. The nuclear reactor core 16 and the control rod system is disposed in the reactor volume. The separator plate 20 restricts but does not completely cut off fluid communication between the pressurizer volume and the reactor volume. As a result, pressure in the pressurizer volume communicates to the reactor volume, so that the operating pressure of the reactor volume can be adjusted by adjusting pressure in the pressurizer volume. Toward this end, a steam bubble is maintained in the upper portion of the pressurizer volume, and the internal pressurizer 22 includes heater elements 26 for applying heat to increase the temperature (and hence increase pressure) in the internal pressurizer 22. Although not shown, spargers may also be provided to inject cooler steam or water to lower the temperature (and hence pressure) in the internal pressurizer 22. In a PWR the primary coolant water is maintained in a subcooled state. By way of illustrative example, in some contemplated embodiments the primary coolant pressure in the sealed volume of the pressure vessel 10 is at a pressure of about 2000 psia and at a temperature of about 300-320 C. Again, this is merely an illustrative example, and a diverse range of other subcooled PWR operating pressures and temperatures are also contemplated.
(13) The reactor core 16 is disposed in the reactor volume, typically near the lower end 14 of the pressure vessel 10, and is immersed in the primary coolant water which fills the pressure vessel 10 except far the steam bubble of the internal pressurizer 22. (The steam bubble also comprises primary coolant, but in a steam phase). The primary coolant water is heated by the radioactive chain reaction occurring in the nuclear reactor core 16. A primary coolant flow circuit is defined by a cylindrical central riser 30 disposed concentrically with and inside the cylindrical pressure vessel 10, and more particularly in the reactor volume. Heated primary coolant water rises upward through the central riser 30 until it reaches the top of the riser, at which point it reverses flow and falls through a downcomer annulus 32 defined between the cylindrical central riser 30 and the cylindrical pressure vessel 10. At the bottom of the downcomer annulus 32 the primary coolant water flow again reverses and flows back upward through the nuclear reactor core 16 to complete the circuit.
(14) In some embodiments, an annular internal steam generator 36 is disposed in the downcomer annulus 32. Secondary coolant water flows into a feedwater inlet 40 (optionally after buffering in a feedwater plenum), through the internal steam generator 36 where it is heated by proximate primary coolant in the downcomer annulus 32 and converted to steam, and the steam flows out a steam outlet 42 (again, optionally after buffering in a steam plenum). The output steam may be used for driving a turbine to generate electricity or for some other use (external plant features not shown). A PWR with an internal steam generator is sometimes referred to as an integral PWR, an illustrative example of which is shown in Thome et al., Integral Helical Coil Pressurized Water Nuclear Reactor, U.S. Pub. No. 2010/0316181 A1 published Dec. 16, 2010 which is incorporated herein by reference in its entirety. While this publication discloses a steam generator employing helical steam generator tubes, other tube geometries including straight (e.g., vertical) once-through steam generator tubes, or recirculating steam generators, or U-Tube steam generators, or so forth are also contemplated.
(15) In embodiments disclosed herein, circulation of the primary coolant water is assisted or driven by reactor coolant pumps (RCPs) 50. With particular reference to
(16) Locating the RCPs 50 proximate to the internal pressurizer 22 places the openings in the pressure vessel 10 for passage of the drive shafts 56 at elevated positions. This elevated placement reduces the likelihood of substantial primary coolant loss in the event of a loss of coolant accident (LOCA) involving the RCPs 50. Moreover, the impellers 52 operate at the turnaround point of the primary coolant flow circuit, that is, at the point where the primary coolant water reverses flow direction from the upward flow through the central riser 30 to the downward flow through the downcomer annulus 32. Since this flow reversal already introduces some flow turbulence, any additional turbulence introduced by operation of the RCPs 50 is likely to be negligible. The RCPs 50 also do not impede natural circulation, which facilitates the implementation of various passive emergency cooling systems that rely upon natural circulation in the event of a loss of electrical power for driving the RCPs 50. Still further, the RCPs 50 are also far away from the reactor core 16 and hence are unlikely to introduce flow turbulence in the core 16 (with its potential for consequent temperature variability).
(17) On the other hand, the placement of the RCPs 50 at the elevated position has the potential to introduce turbulence in the primary coolant water flow into the internal steam generator 36. To reduce any such effect, in the embodiment of
(18) The RCPs 50 output impelled primary coolant water into the output plenum 62 which buffers flow from the pumps into the annular steam generator 36. The primary coolant flows from the outlet plenum 62 either into the steam generator tubes (in embodiments in which the higher pressure primary coolant flows inside the steam generator tubes) or into a volume surrounding the steam generator tubes (in embodiments in which the higher pressure primary coolant flows outside the steam generator tubes). In either ease, the primary coolant flow from the RCPs 50 into the steam generator 36 is buffered so as to reduce flow inhomogeneity. Additionally, because each RCP 50 outputs into the outlet plenum 62 and is not mechanically connected with an inlet of the internal steam generator 36, the failure of one RCP 50 is less problematic. (By comparison, if the RCPs are mechanically coupled into specific inlets of the steam generator, for example by constructing the pump easing so that its outlet is coupled with an inlet of the steam generator, then the failure of one RCP completely removes the coupled portion of the steam generator from use).
(19) Another advantage of the illustrative RCPs 50 is that they are mounted using small openings in the pressure vessel 10. In particular, in some embodiments the opening through which the driveshaft 56 passes is too small for the impeller 52 to pass through. Conventionally such an arrangement would be impractical, because conventionally the RCP is manufactured and installed as a unit by inserting the impeller through the opening in the pressure vessel.
(20) With reference to
(21) The RCP 50 can be installed as follows. The pump motor 54 is mounted at an opening of the pressure vessel 10 with the mounted pump motor 54 located outside of the pressure vessel 10 and supported on the pressure vessel 10 by a mounting flange 70. The impeller 52 is inserted inside the pressure vessel 10, far example via the opened closure 64. Then, after mounting the pump motor 54 and inserting the impeller 52, the inserted impeller 52 is operatively connected to the mounted pump motor 54 by the drive shaft 56. In some embodiments the drive shaft 56 is operatively connected with the pump motor 54 before the pump motor 54 is mounted at the opening of the pressure vessel 10. In such embodiments the mounting of the pump motor 54 includes inserting the drive shaft 56 into the opening of the pressure vessel 10. In such embodiments the opening of the pressure vessel suitably includes a self-lubricating graphalloy bearing 72, and the mounting comprises inserting the drive shaft 56 into the opening of the pressure vessel such that the drive shaft 56 is supported in the opening by the graphalloy bearing 72.
(22) By employing the illustrative embodiment in which the opening for the RCP 50 is too small for the impeller to pass, these openings are made small so as to minimize the likelihood and extent of a loss of coolant accident (LOCA) at these openings. In some contemplated embodiments, the openings may be 3 inches (7.62 cm) in diameter, or even smaller. Although not explicitly illustrated, it is to be understood that the mounting flange 70 may include a metal gasket, o-ring, or other sealing element to provide further sealing additional to the sealing provided by the graphalloy bearing 72.
(23) The number of RCPs 50 is selected to provide sufficient motive force for maintaining the desired primary coolant flow through the primary coolant circuit. Additional RCPs 50 may be provided to ensure redundancy in the event of failure of one or two RCPs. If there are N reactor coolant pumps (where N is an integer greater than or equal to 2, for example N=12 in some embodiments) then they are preferably spaced apart evenly, e.g. at 360/N intervals around the cylinder axis of the cylindrical pressure vessel 10 (e.g., intervals of 30 for N=12). The externally mounted pump motors 54 are advantageously spaced apart from the high temperature environment inside the pressure vessel 10. Nonetheless, substantial heat is still expected to flow into the pump motors 54 by conduction through the flanges 70 and by radiation/convection from the exterior of the pressure vessel 10. Accordingly, in the illustrative embodiment the RCPs 50 further include heat exchangers 74 for removing heat from the pump motors 54. Alternative thermal control mechanisms can be provided, such as an open-loop coolant flow circuit carrying water, air, or another coolant fluid. Moreover, it is contemplated to omit such thermal control mechanisms entirely if the pump motors 54 are rated for sufficiently high temperature operation.
(24) Another advantage of the illustrative configuration is that the pump motor 54 of the RCP 50 is mounted vertically, with the drive shaft 56 vertically oriented and parallel with the cylinder axis of the cylindrical pressure vessel 10. This vertical arrangement eliminates sideways forces on the rotating motor 54 and rotating drive shaft 56, which in turn reduces wear on the pump motor 54, on the graphalloy bearing 72, and on internal bearings supporting the drive shaft 56 within the pump motor 54.
(25) Yet another advantage of the illustrative configuration are that no portion the RCP 50 passes through the internal pressurizer volume. This simplifies design of the internal pressurizer 22 and shortens the length of the drive shaft 56. However, since conventionally the pressurizer is located at the top of the pressure vessel, achieving this arrangement in combination with vertically oriented pump motors 54 and vertically oriented drive shafts 56 entails reconfiguring the pressurizer. In the embodiment of
(26) Still yet another advantage of placing the RCPs 50 at the head of the pressure vessel is that this arrangement does not occupy space lower down in the pressure vessel, thus leaving that space available for accommodating internal CRDM units, a larger steam generator, or so forth.
(27) The embodiment of
(28) With reference to
(29) Unlike the internal pressurizer 22 of the embodiment of
(30) Since the closure 64 is omitted in the embodiment of
(31) With reference to
(32) With reference to
(33) The illustrative embodiments are examples of contemplated variations and variant embodiments; additional variations and variant embodiments that are not illustrated are also contemplated. For example, while the illustrative PWR is an integral PWR including the internal steam generator 36, in some contemplated alternative embodiments an external steam generator is instead employed, in which case the feedwater inlet 40 and steam outlet 42 are replaced by a primary coolant outlet port to the steam generator and a primary coolant inlet port returning primary coolant from the steam generator (alternative embodiment not shown). Moreover, while advantages are identified herein to not mechanically coupling the RCPs 50 to the internal steam generator, it is alternatively contemplated to couple the RCPs to the steam generator inlet, for example by replacing the outlet plenum 62 and illustrative pump casings 58 with pump casings having outlets directly connected with primary coolant inlets of the steam generator.
(34) The preferred embodiments have been illustrated and described. Obviously, modifications and alterations will occur to others upon reading and understanding the preceding detailed description. It is intended that the invention be construed as including all such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.