Patent Application
20150155059
The present subject matter of the teachings described herein relates generally to nuclear reactors, and more particularly nuclear reactors having coolant flowing through pressure tubes.
Commercial nuclear power plants are known. Based on the mechanical design of the pressure retaining components of the reactor core, commercial nuclear reactors can be grouped as either “pressure-vessel” or “pressure-tube” type reactors. Examples of a pressure-vessel type reactor are Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). In these reactor designs nuclear fuel is contained in a large pressure vessel. Where a fluid moderator is used, the coolant and the moderator fluid are the same fluid and thus there is no need to maintain two different fluids separated from one another within the pressure vessel. The single fluid can be supplied to the pressure vessel using an inlet plenum and withdrawn from the vessel using an outlet plenum. In such designs there is no need to isolate a coolant fluid from a separate or different moderator fluid, consequently the plenums need not feed a plurality of separate, sealed fuel channels.
In some pressure vessel designs moderator and coolant are separated through the use of flow channels, but these flow channels are not pressurized (i.e. do not form a pressure boundary) and some leakage between the coolant and the moderator is acceptable because both the coolant and the moderator are the same fluid.
Traditional, horizontal type pressure-tube nuclear reactors are known. Some existing commercial pressure-tube type reactors include a plurality of individual fuel channels extending horizontally through a low-pressure vessel containing a heavy water moderator. Nuclear fuel bundles are placed within the pressure tube inside the fuel channel. A coolant fluid is circulated through the pressure tube and is heated by nuclear fission.
Existing reactor designs, both of the pressure-vessel and pressure-tube type, cannot readily be adapted for use with a supercritical water, as the coolant and heat transfer medium. For a supercritical fluid, this specification and the present invention propose a configuration of pressure tubes, suitable for use with such a fluid. To reach a supercritical state, the coolant fluid will be maintained at high pressures (for example at pressures greater than 23 MPa) and at elevated temperatures. Existing pressure tube designs cannot withstand such high pressures without significantly increasing the pressure tube wall thickness to accommodate increased operating loads and decreased material strength. Simply increasing the thickness of the pressure tube thickness may not be feasable due to tube spacing requirements and decreased reactor efficiency. Also, existing pressure tube materials can be prone to increased corrosion and wear when exposed to supercritical water.
Creating large-diameter pressure vessels for existing reactor designs to withstand high pressures and correspondingly high temperatures can be costly and may be limited by the existing manufacturing capabilities. It may be desirable that the supercritical coolant does not contact the pressure vessel walls that are exposed to the full operating pressure and temperature.
Coolant feeder pipes (coolant inlet pipes and coolant outlet pipes) in some existing commercial pressure tube type reactors are an integral part of the primary heat transport system, connecting the in-reactor fuel channels to the headers with heat transport pipes. The reactor core commonly has separate calandria tubes, providing passages for the pressure tubes through the low-pressure calandria vessel, and the pressure tubes extend through the calandria tubes. Garter springs maintain spacing between each pair of a calandria tube and a pressure tube, and define an annulus.
This summary is intended to introduce the reader to the more detailed description that follows and not to limit or define any claimed or as yet unclaimed invention. One or more inventions may reside in any combination or sub-combination of the elements or process steps disclosed in any part of this document including its claims and figures.
According to one broad aspect of the teachings described herein, a nuclear fuel bundle positionable within a nuclear reactor fuel channel assembly has an axial direction and a lateral direction and may include a first end face and a second end face axially spaced apart from the first end by a bundle length. A plurality of elongate nuclear fuel elements may be supported by at least one spacer. The fuel elements may extend in the axial direction and may be generally parallel to and laterally spaced apart from each other. The plurality of fuel elements and spacer may be sized to be removably received within the fuel channel assembly. A coolant tube passage may extend axially through the fuel bundle between a first aperture in the first end face and a second aperture in the second end face. The coolant tube passage may be sized to removably receive a coolant fluid downflow tube provided in the fuel channel assembly, the tube passage extending from the first end face to the second end face to enable the coolant fluid downflow tube to pass through the fuel bundle and to enable the plurality of fuel elements to laterally surround the coolant fluid downflow tube when the fuel bundle is received within the fuel channel assembly.
The coolant tube passage may be laterally surrounded by the plurality of fuel elements and the coolant tube passage may be laterally centred in the fuel bundle.
The spacer may include a spacer passage aperture axially intermediate the first aperture and the second aperture and the tube passage may extend through the spacer passage aperture.
The coolant tube passage may have a passage axial cross-sectional area that is greater than the axial cross-sectional area of at least some of the fuel elements.
The passage axial cross-sectional area may be greater than the axial-cross sectional area of each of the fuel elements, and/or may be at least about 150% the axial cross-sectional area of at least one of the fuel elements.
The fuel bundle may have an axial bundle cross-sectional area and the coolant tube passage may have an axial passage cross-sectional area. The axial passage cross-sectional area may be between about 10% and about 50% of the axial bundle cross-sectional area.
The fuel bundle may include a central bundle axis and a first set of the fuel elements may be positioned on a common circumference about the central bundle axis to form a first ring of fuel elements. The first ring of fuel elements may be concentric with the central bundle axis.
The tube passage may be positioned laterally within the first ring of fuel elements.
The coolant tube passage may extend along a tube passage axis that is laterally centred within the first ring of fuel elements and is co-axial with the central bundle axis.
The fuel bundle may have a generally round axial cross-sectional shape and may be rotationally symmetrical about a fuel bundle axis extending in the axial direction.
According to another broad aspect of the teachings disclosed herein, a fuel bundle may have an axial direction and a lateral direction and may include a plurality of axially extending fuel elements connected to each other by at least one spacer. The fuel elements may be generally parallel to and laterally spaced apart from each other. The plurality of fuel elements may include a plurality of first fuel elements having a first axial cross-sectional area and a plurality of second fuel elements having a second axial cross-sectional area. The second cross-sectional area may be different than the first cross-sectional area.
The first fuel elements may be laterally inboard of the second set of fuel elements.
The second cross-sectional area may be smaller than the first cross-sectional area.
The fuel bundle may have a generally round axial cross-sectional shape.
The fuel bundle may be rotationally symmetrical about a fuel bundle axis extending in the axial direction.
A plurality of first fuel elements may be positioned on a first common circumference about a fuel bundle central axis to form a first ring of fuel elements and a plurality of second fuel elements are positioned on a second common circumference about the fuel bundle central axis to form a second ring of fuel elements concentric with and laterally outboard of the first ring of fuel elements.
The fuel bundle may have a first end face and a second end face axially spaced apart from the first end by a bundle length and a coolant tube passage extending axially through the fuel bundle between a first aperture in the first end face and a second aperture in the second end face. The coolant tube passage may be sized to removably receive a coolant fluid downflow tube provided in a fuel channel assembly.
The tube passage may extend from the first end face to the second end face to enable the coolant fluid downflow tube to pass through the fuel bundle and the plurality of fuel elements to laterally surround the coolant fluid downflow tube when the fuel bundle is received within the fuel channel assembly.
According to another broad aspect of the teachings described herein, a fuel channel assembly for a nuclear reactor may have an axial direction and a lateral direction and may include an inner conduit received within an outer conduit. The outer conduit may have an outer upper end connectable to a coolant outlet and an outer lower end axially spaced apart from the outer upper end. The inner conduit may have an inner upper end connectable to a coolant source and an inner lower end axially spaced apart from the inner upper end and disposed within the outer conduit to enable coolant to circulate from the coolant source to the coolant outlet through both the inner and outer conduits. A fuel bundle chamber may be defined between an inner surface of the outer conduit and an outer surface of the inner conduit. The fuel bundle chamber may at least partially laterally surround the inner conduit and may be configured to receive at least one nuclear fuel bundle. The fuel bundle chamber may fluidly connect the inner lower end and the outer upper end to enable the coolant to flow upward through the fuel bundle chamber from the inner lower end to the outer upper end.
The outer conduit and inner conduit may be of generally circular axial cross-section and the inner conduit may be concentric with the outer conduit and the fuel bundle chamber is generally annular.
A pressure tube may surround at least a portion of the outer conduit. The pressure tube may have an open pressure tube upper end to receive the outer conduit and the inner conduit and a closed pressure tube lower end configured to be submerged in a moderator and enclosing the inner and outer lower ends.
A thermal insulator may be disposed laterally between the outer conduit and the pressure tube to inhibit heat transfer from the outer conduit to the pressure tube.
The inner upper end may be disposed axially outside the outer conduit.
When the fuel channel assembly is installed within the nuclear reactor the inner upper end may be disposed above the outer upper end.
When the fuel channel assembly is installed within the nuclear reactor the inner lower end may be adjacent the outer lower end.
The inner conduit and outer conduit may be co-axial.
The inner conduit may be made of a first material and the outer conduit may be made from a second material. The first material may have a different neutron absorption cross-section than the second material.
The inner upper end may be disposed axially within the outer conduit and may be positioned axially intermediate the outer conduit upper end and the outer conduit lower end.
The outer conduit may have a sidewall comprising at least one coolant inlet aperture to enable coolant fluid to pass through the outer conduit sidewall. The at least one coolant inlet aperture may fluidly connect the inner upper end to the coolant source.
The inner upper end may be coupled to the outer conduit and when the fuel channel assembly is vertically installed in the nuclear reactor the inner conduit may be suspended from and at least partially supported by the outer conduit.
According to another broad aspect of the teachings described herein, a fuel channel assembly for a nuclear reactor may have an axial direction and a lateral direction may include a coolant inlet fluidly connectable to an inlet plenum to receive a flow of coolant, a coolant outlet downstream from the coolant inlet and fluidly connectable to an outlet plenum and a fuel chamber fluidly intermediate the coolant inlet and the coolant outlet. An inner conduit may be received within an outer conduit. The outer conduit may have an outer conduit first end providing the coolant outlet, and an outer conduit second end axially spaced apart from the outer conduit first end. The inner conduit may have a first inner conduit end providing the coolant inlet and an inner conduit second end axially spaced apart from the inner conduit first end and in fluid communication with the outer conduit second end to enable coolant to circulate from the coolant source to the coolant outlet through both the inner and outer conduits. A fuel chamber may be defined between an inner surface of the outer conduit and an outer surface of the inner conduit. The fuel chamber may at least partially laterally surround the inner conduit and may be configured to receive at least one nuclear fuel bundle. The fuel chamber may fluidly connect the second inner conduit end and the first outer conduit end to enable the coolant to flow upward through the fuel chamber from the inner conduit second end to the coolant outlet.
According to another broad aspect of the teachings described herein, a method of extracting thermal energy from a nuclear fuel bundle in a vertically oriented fuel channel assembly may include the steps of a) directing a flow of coolant fluid at a first temperature in a first direction within a coolant conduit passing through the fuel bundle, b) redirecting the flow of coolant fluid in a second direction substantially opposite the first direction through a chamber containing the fuel bundle and contacting the fuel bundle with the coolant fluid thereby transferring thermal energy from the fuel bundle to the coolant fluid and heating the coolant fluid to a second temperature that is greater than the first temperature.
According to another broad aspect of the teachings described herein, a fuel assembly for a pressure-tube nuclear reactor may include an inner conduit received within an outer conduit. The outer conduit may have an outer conduit first end providing a coolant outlet fluidly connectable to an outlet plenum, and an outer conduit second end axially spaced apart from the outer conduit first end. The inner conduit may have a first inner conduit end providing a coolant inlet fluidly connectable to an inlet plenum and upstream from the coolant outlet and an inner conduit second end axially spaced apart from the inner conduit first end and in fluid communication with the outer conduit second end to enable coolant to circulate from the coolant source to the coolant outlet through both the inner and outer conduits. A fuel chamber may be fluidly intermediate the coolant inlet and the coolant outlet. The fuel chamber may be defined between an inner surface of the outer conduit and an outer surface of the inner conduit. The fuel chamber may fluidly connect the second inner conduit end and the first outer conduit end to enable the coolant to flow upward through the fuel chamber from the inner conduit second end to the coolant outlet. A fuel bundle may be disposed in the fuel chamber and may at least partially laterally surround the inner conduit. The fuel bundle may include a first end face and a second end face axially spaced apart from the first end by a bundle length. The fuel bundle may also include a plurality of elongate nuclear fuel elements supported by at least one spacer. The fuel elements may extend in the axial direction and may be generally parallel to and laterally spaced apart from each other. A passage may extend axially through the fuel bundle between the first end face and the second end face. The passage may be sized to removably receive the inner conduit and the inner conduit passing axially through the fuel bundle.
According to another broad aspect, a pressure-tube nuclear reactor may include an outer shell vessel for containing a moderator at a first pressure and a coolant inlet plenum provided above the moderator. The reactor may include a coolant outlet plenum and one of the coolant inlet plenum and coolant outlet plenum may be within the other of the coolant inlet plenum and the coolant outlet plenum. The reactor may include a plurality of fuel channel assemblies for a coolant fluid at a second, higher pressure. The fuel channel assemblies may be fluidly connected at inlet ends thereof the coolant inlet plenum. The fuel channel assemblies may be mounted within the outer shell vessel and may be surrounded by the moderator. Outlet ends thereof may be fluidly connected to the coolant outlet plenum to enable the coolant fluid to circulate from the coolant inlet plenum through the fuel channel assemblies to the coolant outlet plenum. Each fuel channel assembly may extend in an axial direction and may include an outer conduit. The outer conduit may have an upper end and a lower end axially spaced apart from the upper end. An inner conduit may be disposed at least partially within the outer conduit. The inner conduit may have an upper end and a lower end, wherein one upper end of one of the inner and the outer conduits is in communication with the coolant inlet plenum and the other upper end of the other of the inner and outer conduits is in communication with the coolant outlet plenum. Coolant may flow from the coolant inlet plenum through said one upper to the lower ends of the inner and outer conduits and through the other upper end to the coolant outlet plenum. A fuel bundle chamber may be defined between an inner surface of the outer conduit and an outer surface of the inner conduit. The fuel bundle chamber may at least partially laterally surround the inner conduit and may be configured to receive at least one nuclear fuel bundle. Coolant flow in the fuel bundle chamber passes through the fuel bundle. The plurality of fuel channel assemblies maintaining separation between the coolant fluid circulating within the fuel channel assemblies and the moderator.
The inlet plenum may below the outlet plenum, and at least a portion of the outer conduit extends through the inlet plenum.
The outlet plenum may be below the inlet plenum and at least a portion of the inner conduit may extend through the outlet plenum.
The outlet plenum may be received within the inlet plenum.
Coolant contained within the inlet plenum may circulate around the exterior of the outlet plenum. The inner and outer conduits may be configured so that coolant enters the one inner end at a first velocity and exits the other inner end at a second velocity that is greater than the first velocity. The second velocity may be at least twice as fast as the first velocity.
The reactor may also include a pressure tube surrounding at least a portion of the outer conduit. The pressure tube may have an open pressure tube upper end to receive the outer conduit and the inner conduit and a closed pressure tube lower end submerged in the moderator and enclosing the inner and outer lower ends.
A tubesheet may be positioned between the moderator and the coolant inlet plenum and the coolant outlet plenum and each fuel channel assembly may pass through a respective opening in the tubesheet.
Each pressure tube may include a first portion and a second portion positioned below the first portion and spaced apart from the first portion by an axial offset distance. The first portion may have a first portion upper end in fluid communication with the coolant outlet plenum and a first portion lower end sealed to the tubesheet. The second portion may include an upper end sealed to the tubesheet and in fluid communication with the lower end of the first portion and comprising the closed pressure tube lower end submerged in the moderator.
The second portion of each pressure tube may include a laterally outwardly extending shoulder portion bearing against a complementary seat portion on the tubesheet. The engagement between the shoulder portion and the seat portion may transfer at least some of the weight of the pressure tube to the tubesheet.
The first portion may be formed from a different material than the second portion.
A rim at the lower end of the first portion may be welded to the tubesheet and may provide a fluid tight connection between the tubesheet and the first portion.
The upper end of the first portion may be coupled to a wall of the coolant outlet plenum and may provide a fluid tight connection between the wall of the coolant outlet plenum and the first portion.
According to another broad aspect of the teachings described herein, a nuclear reactor may include a vessel for containing a moderator at a first pressure and a plurality of fuel channel assemblies for a coolant fluid at a second, higher pressure and fluidly connected at inlet ends thereof to a coolant supply conduit, the fuel channel assemblies adapted to receive nuclear fuel bundles and to be mounted within the vessel and surrounded by the moderator, and outlet ends thereof being fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channel assemblies to the coolant outlet conduit, the plurality of fuel channel assemblies maintaining separation between the coolant fluid circulating within the fuel channel assemblies and the moderator. An active moderator cooling circuit may extend between an active moderator inlet to extract the moderator from the vessel, an active moderator return for returning the moderator to the vessel, a pump for driving an active flow of moderator fluid between the active inlet and the active outlet and a heat exchanger provided in the active flow to extract heat from the active flow of moderator fluid. A passive moderator cooling circuit may extend between a passive inlet positioned toward the top of the vessel, a passive return positioned toward the bottom of the vessel and a heat exchanger provided between the passive inlet and the passive return.
According to another broad aspect, a pressure-tube nuclear reactor may include an outer shell vessel for containing a moderator at a first pressure and a coolant inlet plenum provided above the moderator. The reactor may include a coolant outlet plenum and one of the coolant inlet plenum and coolant outlet plenum may be within the other of the coolant inlet plenum and the coolant outlet plenum. The reactor may include a plurality of fuel channel assemblies for a coolant fluid at a second, higher pressure. The fuel channel assemblies may be fluidly connected at inlet ends thereof the coolant inlet plenum. The fuel channel assemblies may be mounted within the outer shell vessel and may be surrounded by the moderator. Outlet ends thereof may be fluidly connected to the coolant outlet plenum to enable the coolant fluid to circulate from the coolant inlet plenum through the fuel channel assemblies to the coolant outlet plenum. Each fuel channel assembly may extend in an axial direction and may include an outer conduit. The outer conduit may have an upper end and a lower end axially spaced apart from the upper end. An inner conduit may be disposed at least partially within the outer conduit. The inner conduit may have an upper end and a lower end, wherein one upper end of one of the inner and the outer conduits is in communication with the coolant inlet plenum and the other upper end of the other of the inner and outer conduits is in communication with the coolant outlet plenum. Coolant may flow from the coolant inlet plenum through said one upper to the lower ends of the inner and outer conduits and through the other upper end to the coolant outlet plenum. A fuel bundle chamber may be defined between an inner surface of the outer conduit and an outer surface of the inner conduit. The fuel bundle chamber may at least partially laterally surround the inner conduit and may be configured to receive at least one nuclear fuel bundle. Coolant flow in the fuel bundle chamber passes through the fuel bundle. The plurality of fuel channel assemblies maintaining separation between the coolant fluid circulating within the fuel channel assemblies and the moderator. A passive moderator cooling circuit may extend between a passive inlet positioned toward the top of the outer shell vessel, a passive return positioned toward the bottom of the outer shell vessel and a heat exchanger provided between the passive inlet and the passive return.
The drawings included herewith are for illustrating various examples of articles, methods, and apparatuses of the teaching of the present specification and are not intended to limit the scope of what is taught in any way.
In the drawings:
a is a side view of a portion of a fuel assembly;
b is an enlarged view of a portion of
c is an enlarged view of a portion of
d is an enlarged view of a portion of
e is a side view of a portion of another example fuel assembly;
a is a schematic cross-sectional view of an example of a fuel bundle in a fuel channel assembly;
b is a schematic cross-sectional view of another example of a fuel bundle in a fuel channel assembly;
c is a schematic cross-sectional view of an example of known fuel bundle in a known fuel channel assembly;
d is a schematic cross-sectional view of another example of a fuel bundle in a fuel channel assembly;
Elements shown in the figures have not necessarily been drawn to scale. Further, where considered appropriate, reference numerals may be repeated among the figures to indicate corresponding or analogous elements.
Various apparatuses or processes will be described below to provide an example of an embodiment of each claimed invention. No embodiment described below limits any claimed invention and any claimed invention may cover processes or apparatuses that differ from those described below. The claimed inventions are not limited to apparatuses or processes having all of the features of any one apparatus or process described below or to features common to multiple or all of the apparatuses described below. It is possible that an apparatus or process described below is not an embodiment of any claimed invention. Any invention disclosed in an apparatus or process described below that is not claimed in this document may be the subject matter of another protective instrument, for example, a continuing patent application, and the applicants, inventors or owners do not intend to abandon, disclaim or dedicate to the public any such invention by its disclosure in this document.
This specification generally describes a pressure-tube type nuclear reactor having a relatively low-pressure moderator. For example, the moderator can be maintained at a pressure range of 0 MPa(g) to 2 MPa(g) and may be about 0.5 MPa(g). Optionally, the moderator may be a fluid or a solid. In the examples described herein the moderator is a heavy water fluid moderator. Alternatively, the moderator can be any suitable moderator, fluid or solid, including for example, a graphite based solid moderator. The teachings disclosed herein may be generally applicable to any pressure-tube type reactor.
According to one aspect of the described reactor, the pressure-tube reactor is configured such that a pressurized coolant fluid is circulated through the fuel channel assemblies. The coolant may be any suitable fluid, including, for example, light water, heavy water, molten salts, and molten metals and may be circulated as a liquid, gas, a mixed-phase flow and/or a super-critical fluid. The fuel channel assemblies include a pressure tube that is submerged within the moderator and serve as a pressure barrier between the low pressure moderator and the high pressure coolant. The coolant circulated within the fuel channel assemblies may be pressurized to pressures that are substantially higher than the pressure of the moderator, and may be, for example, may be any suitable pressure between about 8 MPa and about 26 MPa and/or may be up to about 30 MPa or higher.
The fuel channel assemblies can be arranged in any suitable pattern and/or orientation, including for example having circular, hexagonal, square or other suitable cross-sectional shapes. In the illustrated examples, the fuel channel assemblies are arranged generally vertically within the reactor core. Alternatively, the fuel channel assemblies may be arranged horizontally or at any other suitable angle based on alternative reactor core designs.
Referring to
In the illustrated example the calandria 102 is illustrated as being generally circular in axial cross-sectional shape. Alternatively, the calandria 102 may have any suitable configuration, and need not be cylindrical or have a circular axial cross-sectional shape.
Referring to
Referring to
One or more fluid ports can be provided in the plenum vessel 112 to allow coolant to flow in and out of the first plenum chamber 120. In the illustrated example, the plenum vessel includes 4 ports 122 spaced apart from each other around the sidewall 116. The ports 122 may be connected to any suitable conduits and/or pipes, and may include any suitable valves, flow regulators or other suitable apparatuses to control fluid flow through the ports. The number of ports 122 can depend on a variety of factors, including expected coolant flow rates, coolant pressure, coolant temperature, plenum size, piping costs, desire for redundant coolant supply and physical space constraints.
Referring to
Optionally, the second plenum 124 may be removable from the first plenum chamber 120. This may help facilitate inspection and maintenance of the second plenum 124, and may help facilitate access to the tubesheet 114, fuel channel assemblies 150 and other portions of the plenum vessel 112 disposed below the second plenum 124. In the illustrated example, the second plenum 124 is supported on a plurality of support brackets 134 extending from the sidewall 116. The support brackets 134 may be integrally formed with the sidewall 116, or may be separate members joined to the sidewall 116. The size and number of support brackets 134 may be selected based on a variety of factors, including the strength of the second plenum 124, the strength of the support brackets 134, and the material of the support brackets 134.
Referring also to
Referring to
Because pressure losses in the fuel channel assemblies 150 are higher than in the inlet plenum chamber 120, incoming coolant may divide reasonably uniformly into the plurality of fuel channel assemblies 150. However, if further control of coolant flow rates is desired, flow control apparatus (not shown), such as, for example orifice plates, may be used in some or all of the fuel channel assemblies.
Referring to
Referring to
Optionally, the pressure within the second plenum chamber 126 may be maintained at a pressure that is close to the operating pressure of the first plenum chamber 120. For example, the operating pressures in the first and second plenum 120, 126 may be within about 0.1-5 MPa of each other. In this configuration, the bottom wall 128, lid 132 and sidewall 130 need not be configured to carry a high pressure load. This may allow the bottom wall 128, lid 132 and sidewall 130 to have lower strength than the cover 118, sidewall 116 and tubesheet 114. Alternatively, the second plenum 124 may be configured to withstand a relatively large pressure differential.
In the illustrated example, the first plenum chamber 120 functions as a coolant inlet plenum, the ports 122 operate as coolant inlet ports, the second plenum chamber 126 functions as a coolant outlet plenum and its ports 154 (
Coolant may be supplied to the inlet plenum 120 at any suitable inlet temperature and inlet pressure. The combination of inlet temperature and pressure desired may be based on the properties of a given reactor core design and/or nuclear fuel type. Optionally, the plenum vessel 112 can be configured to handle liquid coolants, gas coolants, mixed-phase coolants and super-critical coolant conditions. For example, in some configurations the inlet temperature may be between about 100° C. and about 370° C. or more, and may be between about 260° C. and about 350° C. The inlet pressure may be between about 5 MPa and about 30 MPa or more, and may be between about 10 MPa and about 26 MPa. Optionally, the inlet conditions may be selected so that the incoming coolant remains sub-critical. This may help facilitate greater energy pickup from the fuel bundles 160 when the coolant flows through the fuel channel assembly 150.
The temperature and pressure of the coolant as it exits the fuel channel assemblies 150, and flows into the outlet plenum 124, may vary based on the quantity of heat transferred from the fuel bundles 160 and the amount of pressure drop generated as the coolant flows past the fuel bundles 160 in the fuel channel assembly 150. When operated in sub-critical conditions, the outlet temperature may be between about 290° C. and about 350° C. and the outlet pressure may be between about 8-12 MPa. When operated under supercritical coolant conditions, the outlet temperature may be between about 374° C. and about 675° C. (and may be about 625° C.) and the outlet pressure may be about 22-26 MPa. In other configurations, the outlet pressure may be between about 12 and about 22 MPa and may be greater than 26 MPa.
In some configurations, there may be a significant temperature difference between the coolant in the inlet plenum 120 and coolant in the outlet plenum 124. For example, under supercritical operating conditions, the temperature difference between the inlet plenum 120 and outlet plenum 124 may be between about 250-300° C., or more. Such temperature differences may impart significant thermal stresses in the second plenum lid 132, sidewall 130 and bottom wall 128. As it is located outside of the neutron field, the outlet plenum 124 may be made from a variety of suitable materials, including, for example stainless steel and nickel-based super alloys. Optionally, some or all of the outlet plenum 124 may be thermally insulated using any suitable techniques and/or materials to help limit heat transfer between the plenums 120, 124 and to help reduce thermal stresses on the second plenum 124. For example, the lid 132, sidewall 130 and bottom wall 128 may be coated with an insulating material and/or made from multiple layers. Alternatively, as the pressure difference between the plenums may be relatively small, the second plenum 124 may be formed from materials that have desirable thermal properties, including, for example refractory materials and ceramic-based materials, instead of highly thermally conductive metals.
Heated coolant extracted from the outlet plenum 124 can be used to generate electrical power. Optionally, the heated coolant fluid can be used to directly drive suitable steam turbine generators (not shown). This may help improve the efficiency of a nuclear power generation station as the heated coolant may remain at a high temperature when it reaches the turbines. Alternatively, the heated coolant may be used to heat a secondary circuit, for example via a steam generator, and the turbine generators may be driven by steam in the secondary circuit. Configuring the system to include a steam generator and secondary circuit may help increase the safety of the power generation system, but may reduce overall efficiency.
In the illustrated example, the tubesheet 114, in combination with the pressure tubes 162 (
Optionally, the tubesheet 114 can be formed in a generally dome or hemi-spherical shape to help resist the operating pressures of the coolant. The cover 118 may have a similar dome or hemi-spherical shape. Alternatively, the tubesheet 114 and/or cover 118 may have any other suitable shape, including, for example a generally flat or planar configuration.
The plenum vessel 112 is located outside the region of reactor core neutron flux, and need not be formed from a material having a low neutron absorption cross-section. Optionally, the plenum vessel 112 can be formed from any suitable material that can withstand the operating temperatures and pressures of the coolant, including, for example stainless steel, steel alloys and other ferrous metals. The thickness of the tubesheet 114, sidewall 116 and cover 118 can be selected to provide a desired strength to contain the high pressure coolant, and may be based on the material used to form the plenum vessel 112. Optionally, different portions of the plenum vessel 112 may be formed from different materials.
In the illustrated example the tubesheet 114 and sidewall 116 are integrally formed together. This may eliminate the need for connecting the sidewall 116 to the tubesheet 114 and to seal such a connection with a seal capable of withstanding high pressures. Alternatively, the sidewall 116 and tubesheet 114 may be formed as separate members. In some examples, some or all of the cover 118, side walls 116 and tubesheet 114 can have a wall thickness between 0.05 m and 1.0 m, or more, and in some examples may have a thickness of between about 0.4 m and about 1.0 m.
Optionally, the cover 118 may be connected to the sidewall using releasable or detachable fasteners, such as studs 166, so that the cover 118 may be detachable from the sidewall 116 (
In addition to containing and routing coolant, some or all of the cover 118, sidewall 116, tubesheet 114 and the volume of coolant retained within the plenum vessel 112 can provide radiation shielding at the top of the reactor 100. In some examples the inlet plenum 120 and coolant can provide a sufficient or desired level of radiation shielding so that the reactor 100 does not require a separate upper shield member. In other examples, the reactor can include a separate upper shield, for example a neutron shield as known in the art (not shown), to provide a desired or required level of radiation shielding toward the top of the reactor. A separate shield, if desired, can be located in any suitable location as known in the art, including, for example, between the tubesheet 114 and the calandria 102 and above/surrounding the cover 118. In the illustrated example, there may be about 0.5 m to about 1 m or more of fuel-free moderator surrounding the fuel-filled space within the calandria 102. This moderator may act as a reflector and may provide shielding. The tubesheet 114 itself may also act as an additional shield member.
Referring to
Each fuel channel assembly 150 is sized to accommodate one or more nuclear fuel bundles 160 (see for example
In the illustrated example, each fuel channel assembly 150 includes a pressure tube (for example pressure tube 162,
Referring to
The fuel bundle chamber 176 is configured to receive corresponding nuclear fuel bundles 160. The fuel assembly 151 has a fuel channel assembly axis 178 (
Referring to
Referring to
Referring to
In this example, the coolant downflow tube 172 and liner tube 174 are generally circular in axial cross-sectional shape and are concentric with each other. In this configuration, the fuel bundle chamber 176 is generally annular in shape and is configured to receive generally cylindrical fuel bundles 160. Alternatively, the coolant downflow tube and liner tube may have any other suitable cross-sectional shape and the fuel bundle chamber may have another shape.
The pressure tube 162 is sealed to the tubesheet 114 and forms part of the pressure boundary between the high pressure coolant and the lower pressure moderator. In the illustrated example, the pressure tube 162 has an upper end 192 (
Referring to
Referring to
In the illustrated example, the upper portion 188 of the liner tube 174 has an upper diameter 210, that is smaller than the lower diameter 206, and the coupling 186 provides a transition between the lower diameter 206 and upper diameter 210. Optionally, the upper diameter 210 may be selected so that it is smaller than the outer diameter 208 of the fuel bundle 160. Alternatively, the upper diameter 210 may be generally equal to or larger than the lower diameter 206.
Providing a smaller upper diameter 210 may affect the flow of coolant within the liner tube 174. For example, the narrowing of the liner tube 174 may increase the velocity of the coolant as it flows through the upper portion 188, relative to the lower portion 184. If the upper diameter 210 is smaller than the fuel bundle outer diameter 208, providing a coupling 186 that is separable from the lower portion 184 may help facilitate insertion and/or removal of the fuel bundle 160 from the lower portion 184. Once assembled, the liner tube 174, coolant downflow tube 172 and fuel bundle 160 may be manipulated as a single unit for insertion into and/or removal from the pressure tube 162.
Referring to
The liner tube 174 may be formed from any suitable material that has sufficient mechanical strength and is able to withstand the outlet coolant conditions (optionally high temperature and high pressure). Optionally, as the lower portion 184 is to be positioned within the reactor core and exposed to neutron flux, the lower portion 184 may be made from a material that has a desirably low neutron absorption cross-section, including, for example, zirconium alloys.
Optionally, some or all of the liner tube 174 may be insulated to help inhibit heat transfer across the sidewall 214. Insulating the liner tube 174 may help reduce thermal stresses on the liner tube 174, and may help reduce transfer of heat from the liner tube 174 to other components of the fuel channel assembly 150, such as the surrounding pressure tube 162. In the illustrated example, the pressure tube 162 is submerged in the moderator which is at a relatively lower temperature, while the coolant flowing through the fuel channel assembly 150 is heated to a substantially hotter temperature. Reducing the heat transfer from the liner tube 174 to the surrounding pressure tube 162 may help reduce the thermal gradient, and resulting stresses, faced by the pressure tube 162.
Referring to
Optionally, the insulator 216 may be fixedly attached to the liner tube 174, or may be separable or removable from the liner tube 174. Fixing the insulator 216 to the liner tube 174 may help simplify handling and position of the liner tube 174 and insulator 216 within the pressure tube 162. Providing the insulator 216 as a separate member may allow for the insulator 216 to be separately positioned, inspected and/or replaced independent of the liner tube or other fuel channel assembly components. The insulator 216 may be formed from any suitable material having desired heat insulating properties, and optionally desirable neutron absorption-cross section properties, including, for example ceramic materials and refractory materials. Optionally, the insulator 216 may be provided in two or more separate elements/parts.
A separate upper insulator 224 (
In some configurations, the bottom wall 128 of the outlet plenum may be exposed to higher temperatures than the tubesheet 114 and may thermally expand in the lateral direction by a different amount than the tubesheet 114. Differences in thermal expansion between the bottom wall and the tubesheet may cause the apertures 148 in the bottom wall 128 to laterally shift relative to the corresponding apertures 164 in the tubesheet 114. Such shifts may cause slight misalignment between the bottom wall apertures 148 and the tubesheet apertures 164, which may exert bending forces portions of the fuel channel assembly 150, for example the pressure tube 162, extending between the apertures 148, 164. Optionally, the connection between the pressure tube 162 and the bottom wall 128 can be configured to accommodate for such misalignment. Referring to
In the illustrated example, the upper end 228 of the pressure tube 162 is sealingly connected to the bottom wall 128 of the outlet plenum 124 using any suitable seal, including, for example, including rolled joints, welded joints, mechanical coupling and explosion bonding. Optionally, an upper portion 230 of the pressure tube 162, referred to as a pressure tube extension 230 (a portion of the pressure tube not submerged in the moderator) may be formed from a different material than the lower portion 232 of the pressure tube 162. For example, the lower portion 232 of the pressure tube 162 may be formed from a zirconium alloy (having a desirable neutron absorption cross-section) and the pressure tube extension 230 may be formed from stainless steel, or other non-zirconium based metals. Using different materials for the lower portion 232 of the pressure tube and the pressure tube extension 230 may allow each portion of the tube 162 to be formed from a material having different, desirable properties.
Optionally, the two portions 230 and 232 may be integrally formed so that the pressure tube 162 is of unitary one-piece construction. This may include pressure tubes 162 in which the portions 230 and 232 are different materials but are bonded in such a way that they cannot be readily separated from each other. Optionally, the two portions 230, 232 of the pressure tube 162 may be joined together using any suitable technique or mechanism. In the illustrated example, the lower portion 232 and the pressure tube extension 230 are joined via co-extrusion, which provides a bond of sufficient strength and produces a generally integrally formed pressure tube 162.
Alternatively, the two portions 230 and 232 may be separate members that are positioned adjacent each other and aligned to provide a generally continuous pressure tube 162a, but need not necessarily be directly coupled to each other. Referring to
In this embodiment, the pressure tube extension 230a is not directly joined to the lower portion 232a. In the illustrated example, a gap 231 is formed between the lower end of the pressure tube extension 230a and the upper end of the lower portion 232a. The gap 231 defines a height or offset spacing 233 between the two portions 230a and 232a. The size of the offset spacing 233 may be any suitable distance, including, for example between about 0 mm (no gap, where the portions touch each other but are not joined together) and about 25 mm or more. Optionally, some or all of the gap 231 may be filled with weldment or other materials, and the gap need not be a fully open channel or groove. Using this configuration separates the sealing (leak-tightness) aspects of the pressure tube 162a from the load bearing aspects of the pressure tube 162a. Separating the functional aspects of the pressure tube 162a may help simplify the design and construction of the pressure tube 162a and assembly of the reactor, and may help increase reliability of the fuel channel assembly.
In the illustrated embodiment, the pressure tube extension 230a is provided as a separate member that extends from the bottom wall 128 of the second plenum chamber 126 (see
The pressure tube extension 230a can be joined to both the bottom wall 128 and the tubesheet 114 using any suitable, fluid tight connection. This connection provides the liquid-tight seal between the fuel channel chamber 176 and the first plenum chamber 120. In the illustrated example, the lower rim 280 of the pressure tube extension 230a is welded to the tubesheet 114. The lower rim 280 may be welded around its outer perimeter (on the surface of the tubesheet 114), around its inner perimeter (within the apertures 164) or a combination of both locations.
The lower portion 232a of the pressure tube 162a is positioned within a corresponding opening 164 in the tubesheet 114. The upper end of the lower portion 232a is joined to the tubesheet 114 using any suitable joint. In the illustrated example, the upper end is pressure rolled to the tubesheet 114. The lower portion 232a of the pressure tube 162a includes a generally outwardly projection shoulder portion 235 that is configured to abut and bear against a corresponding seat portion 237 of the tubesheet 114. The weight of the pressure tube 162a, along with the contents of the pressure rube 162a including the fuel channel assembly and coolant, is at least partially carried by the shoulder 265 and transferred to the tubesheet 114 via the seat portion 237. Optionally, the shoulder 235 and seat 237 may carry all, or substantially all of the load/weight of the pressure tube 162a. In the example illustrated, both the shoulder portion 235 extends around the entire perimeter of the lower portion 232a, and includes an engagement surface 239 that is inclined relative to the fuel channel axis 170. The sear portion 237 includes a complimentary bearing surface 241, which is also inclined relative to the fuel channel axis 170. Alternatively, the shoulder portion 235 need not extend continuously around the perimeter of the lower portion 232a, and the engagement surface 239 (an complimentary bearing surface 241) may be in any suitable orientation and need not be inclined as illustrated.
Optionally, the material used to form the pressure tube extension 162 may be selected so that it has a thermal expansion co-efficient that is generally equal to, or is within about 5% to about 40% of the thermal expansion co-efficient of the bottom wall 128 of the outlet plenum 124. This may help reduce the magnitude of stresses at the joint between the pressure tube extension 230 and the bottom wall 128 caused by differences in the amount of thermal expansion between the bottom wall 128 and the pressure tube extension 230.
Referring to
Extending the coolant downflow tube 172 beyond the lower face 242 of the fuel bundle 160 may help balance the distribution of coolant flow within the fuel bundle chamber 176 before it reaches the lower face 242 of the fuel bundle 160. Optionally, one or more flow directors (not shown), including for example a baffle, vane, guide or other flow directing apparatus, may be provided axially between the lower face 242 of the fuel bundle 160 and the lower end 236 of the coolant downflow tube 172 to help modify or balance the coolant flow as it enters the fuel bundle chamber 176. Extending the coolant downflow tube 172 beyond the lower face 242 of the fuel bundle 160 may also help accommodate thermal expansion (lengthening) and/or creep of the fuel bundle 160 when the reactor 100 is in use, to help provide coolant flow to the lowermost portion of the fuel bundle 160.
Referring to
Referring to
Optionally, the coolant downflow tube 172 may be generally fluid tight along its length to transport coolant fluid from is upper end 234 to its lower end 236 without allowing a substantial amount of the coolant to escape and mix into the fuel bundle chamber 176, until the coolant exits the lower end 236 of the coolant downflow tube 172. Optionally, the thermal stresses in the coolant downflow tube 172 (and optionally any other portion of the fuel assembly 151 or fuel channel assembly 150) may be managed by applying a coating of heat resistant material 250 to the exterior surfaces of the conduit 172 (
Referring to
Referring to
In the illustrated example, coolant 190 flowing downwardly is substantially contained within the coolant downflow tube 172 and will not contact the fuel bundles 160. This configuration may help reduce the amount of heat transfer between the fuel bundles 160 and the coolant in the coolant downflow tube 172 so that the temperature of the coolant exiting the bottom 236 of the coolant flow tube 172 is within about 2° C. and about 50° C. degrees of the coolant in the inlet plenum 120. Optionally, the coolant downflow tube 172 may be insulated, in any suitable manner, to help further reduce the heat transfer between the coolant within the coolant downflow tube 172 and the fuel bundles 160 and coolant 198 flowing in the fuel bundle chamber 176. Optionally, the reactor 100 can be configured so that the velocity of coolant flowing downwardly within the coolant downflow tube 172 is between about 1 m/s and about 10 m/s, and in the illustrated example may be about 5 m/s.
Once expelled from the coolant downflow tube 172, the coolant will flow upward through the fuel bundle chamber 176 while contacting the fuel bundles 160. In this configuration, the coolant is flowing upwards (arrows 198) while it is being heated by the fuel elements 270. In some configurations, the coolant may enter the fuel bundle chamber 176 as a liquid and become a two-phase fluid and/or supercritical fluid as it is heated by the fuel bundle 160. Delivering relatively cool coolant to the bottom of the fuel bundle chamber 176, and configuring the coolant to flow upward while in contact with the fuel bundles 160 may help improve the thermal stability of the coolant flow and/or other unwanted flow effects. For example, as the coolant flows through the fuel bundle chamber 176 it is heated by contact with the fuel bundles 160. The heated fluid may be less dense and/or in a different phase than the incoming fluid which may tend to urge the heated fluid upward within the fuel bundle chamber 176. In the illustrated example, the pressure differential acting on the coolant also tends to urge the coolant to flow upward through the fuel bundle chamber 176. Configuring the fuel channel assembly so that the thermal and pressure forces tend to act in concert, e.g. both urge the coolant to flow upwards, may help stabilize the coolant flow. Optionally, the reactor 100 may be configured so that the velocity of coolant flowing upwardly through the fuel bundle chamber 176 (for example water or molten salts or metals) is between about 2 m/s and about 20 m/s or more, and in the illustrated example may be between about 15 m/s and about 20 m/s.
Referring to
In the illustrated example, portions of the liner tube 174 extending through the inlet plenum 120 are shrouded by the insulator and the pressure tube 162. A plurality of coolant apertures 254 are provided in the sidewall 256 of the pressure tube 162 to allow coolant fluid from the inlet plenum 120 to pass through the sidewall 256 and flow into the annular chamber 258 defined between the pressure tube 162 and the liner tube 174. The chamber 258 surrounds the inlet ports 212 in the liner tube sidewall 214, and coolant from the chamber 258 can flow into the ports 212 and into the coolant downflow tube 172.
The upper end of the chamber 258 is bounded by the flange 260 on the liner tube 174 that is connected to the pressure tube 162. In the illustrated example, the connection between the flange 260 and pressure tube 162 may be substantially sealed so that coolant in the chamber 258 is unlikely to flow upwards into upper chamber 264 instead of flowing down into the coolant downflow tube 172. In the illustrated example, the flange 260 is configured to rest on a supporting shoulder 266 on the pressure tube 162 and is threading engaged with the inner surface of the pressure tube 162. In this configuration, the connection between the flange 260 and the pressure tube 162 is the primary mechanical connection between the liner tube 174 and the pressure tube 162 and is adapted to support substantially all of the weight of the fuel assembly 151. Alternatively, the connection between the liner tube 174 and pressure tube 162 may be of any suitable configuration and optionally additional support members may be provided to help support the weight of the liner tube, fuel bundle and/or coolant downflow tube.
In the illustrated example, the lower end of the chamber 258 is not sealed with a fluid tight seal. Instead, annular gaps may be provided between the liner tube 174 and the insulator 216 and/or between the insulator 216 and the pressure tube 162. Providing such gaps may help facilitate insertion and removal of the liner tube 174 and/or insulator 216 within the pressure tube 162. The size of the gaps may be controlled by varying the relative sizes of the liner tube 174 and the pressure tube 162 and/or insulator 216. Preferably, the gap may be relatively small so that it will have a relatively higher flow resistance than the feeder conduits 252 such that it provides a torturous flow path for the coolant in the chamber 258 and only a small amount of coolant will exit the chamber 258 via the gap and flow into the annular space between the liner tube 174 and the pressure 162 tube and/or insulator 216.
While illustrated as generally oval apertures, the coolant apertures 254 may be of any suitable shape and configuration. For example, the coolant apertures 254 may be generally circular openings, an example of which is illustrated as apertures 254a in
Optionally, the coolant apertures 254 may be positioned toward the bottom of the inlet plenum (e.g. generally adjacent the tubesheet 114). Positioning the coolant apertures 254 toward the bottom of the coolant plenum may help facilitate coolant in the inlet plenum flowing into the fuel channel assemblies 150 by gravity in the event of power loss or during accident conditions and circulating through the channels 150 via natural circulation driven by the heating of the coolant within the fuel bundle chamber 176.
In the illustrated example, the fuel channel assemblies 150 are shown being generally constantly spaced apart from each other and being of generally the same size and shape. Alternatively, the fuel channel assemblies in the reactor 100 may be of different sizes and shapes, and may not be uniformly spaced within the reactor 100.
A schematic representation of coolant flow through reactor 100 and fuel channel assembly 150 is illustrated in
Referring to
In the illustrated example, the fuel bundle 160 includes a plurality of elongated nuclear fuel elements 270 that extend axially within the fuel bundle 160. Each fuel element 270 contains one or more pellets of nuclear fuel material. The nuclear fuel in the bundle 160 may be any fuel suitable for burning in a pressure-tube reactor, including, for example, natural uranium, enriched uranium, plutonium, thorium, mixtures thereof, and any other suitable, fissile fuel. In the illustrated example, the fuel bundle 160 is of generally circular axial cross-sectional area, and is generally rotationally symmetrical about axis 178.
The plurality of fuel elements 270 are connected to each other and supported by at least one spacer 272. Spacers 272 may be provided at desired intervals along the length of the fuel bundle, and may be provided on the end faces 242, 268 of the fuel bundle (where they may be referred to as end caps or end plates). In the illustrated example, the spacer 272 includes a plurality of ring members 274, each supporting a respective plurality of fuel elements 270. In this example, the fuel elements 270 are held generally parallel to and laterally spaced apart from each other. The fuel elements 270 and spacers 272 are sized and configured so that the outer diameter 208 of the fuel bundle 160 is within an acceptable range such that the fuel bundle 160 can be removably received within the liner tube 174.
In the present example, the fuel bundle 160 contains fuel elements 270a and 270b having different axial cross-sectional areas. In the illustrated example, the fuel elements are configured into three generally concentric rings. The fuel elements 270a in the two inner rings are generally the same size and the fuel elements 270b in the outer ring are smaller. Providing smaller fuel elements 270b in the outer ring may affect the heat transfer from the fuel bundle 160 to the coolant, and may affect the burn time and temperature of the fuel elements. The number of fuel elements 270 in the bundle, their relative sizes and relative positioning may be varied to achieve different fuel bundle performance characteristics. Optionally, the smaller fuel elements 270b may be located at an inboard position within the fuel bundle 160, or any other suitable position.
Alternatively, referring to
To facilitate insertion into the generally annular fuel bundle chamber 176, the fuel bundle 160 may include one or more conduits or passages to receive the coolant downflow tube 172. Referring to
In the illustrated example, the coolant tube passage 180 has a passage diameter 278 that is sized to be generally equal to or larger than the coolant downflow tube diameter 246. In this configuration, the passage 180 is sized to removably receive the coolant fluid downflow tube 172 provided in the fuel channel assembly when the fuel bundle is inserted into the fuel bundle cavity. Preferably, the tube passage 180 extends the entire length of the fuel bundle 160, from the first end face 242 to the second end face 268, to enable the coolant fluid downflow tube 172 to pass through the fuel bundle 160.
In the illustrated example, the passage 180 is generally centred within the bundle 160, e.g. is coaxial with the fuel bundle axis 182, and the plurality of fuel elements 270 are positioned to laterally surround the coolant fluid downflow tube 172 when the fuel bundle is received within the fuel channel assembly 150. When installed within the fuel bundle chamber 176, the fuel bundle 160 is coaxial with the coolant downflow tube 172, the liner tube 174 and the pressure tube 162. Alternatively, if intended to be used with differently configured fuel channel assemblies, the passage 180 may not be centered within the fuel bundle.
The passage 180 has an axial cross-sectional area that is less than the axial cross-sectional area of the complete fuel bundle. Optionally, the cross-sectional area of the passage may be between about 10% and about 50%, or more of the fuel bundle cross-sectional area. Optionally, the passage axial cross-sectional area that is greater than the axial cross-sectional area of at least some of the fuel elements. In the illustrated example, the passage cross-sectional area is between about 150% and about 400%, or more of the cross-sectional area of the fuel elements.
Referring to
Referring to
Referring to
Referring to
In this configuration coolant downflow tube 1172 can be removed from the liner tube 1174 without requiring disassembly of the liner tube 1174. This may enable all of the coolant downflow tubes 1172 to be removed from their respective liner tubes 1174 by lifting the outlet plenum 1124 out of the plenum vessel 1112, optionally without having to remove the lid 1132 of the outlet plenum 1124. Alternatively, the coolant downflow tubes 1172 may be removed by removing the lid 1132 of the outlet plenum 1124 and leaving the rest of the outlet plenum 1124 in place. This may help facilitate refuelling and maintenance of the liner tubes 1174 and/or pressure tubes 1162.
Alternatively, the coolant flow tubes 1172 and liner tubes 1174 may be connected to the outlet plenum 1124 to form a fuel assembly such that the whole assembly, including the fuel bundle 1160, coolant downflow tube 1172 and liner tube 1174, can be removed in a single operation, leaving the pressure tubes 1162 in place.
In the illustrated example, the coolant downflow tube 1172 can be formed from a material that is sufficiently flexible to allow a slight misalignment between the lid 1132 of the outlet plenum 1124 and the interior of the liner tube 1174 and the passage 1180 in the fuel bundle while the reactor 1100 is in use.
A schematic representation of the coolant flow through the reactor 1100 is show in
Referring to
In reactor 2100, the insulator 2216 in the fuel channel assembly 2150 is provided outside the pressure tube 2162 (e.g. between the pressure tube 2162 and the moderator). In this configuration, the pressure tubes 2162 will operate a higher temperature than the pressure tubes in reactors 100 or 1100 as they are directly exposed to the high temperature coolant flow. This design may be suitable for using in reactors in which the operating temperatures of the coolant flow are within the range of operability for the desired pressure tube material, which may be a zirconium based alloy. For traditional zirconium alloy pressure tubes, a practical upper limit for the operating temperature may be about 350° C. or less (at about 16.5 MPa saturation pressure). The use of an external insulator 2216 may help facilitate the use of a low temperature and low pressure moderator.
Optionally, under suitable operating conditions (for example when operating with sub-critical water coolant) the insulator 2216 may be a gas-filled chamber outside the pressure tube 2162. In such configurations, an additional calandria tube 2400 could be provided around the outside of the pressure tube 2162 and insulating gas 2402 provided within the annulus between the calandria tube 2400 and the pressure tube 2162. The gas 2402 may be any suitable gas, including, for example nitrogen and carbon dioxide. Providing a gas-filled annulus may also help facilitate pressure tube leak detection by monitoring quality and/or moisture content of the annulus gas.
Referring to
Optionally, the reactor 100 may include one or more moderator cooling systems to help maintain the temperature of the moderator in the event that it is needed to absorb heat from the fuel channel assemblies/pressure tube. In the illustrated example, the reactor includes an active cooling system 500 and an independent passive cooling system 502.
The active cooling system 500 includes a moderator outlet port 504, located toward the top of the calandria 102, to draw the relatively warm moderator into the active cooling loop 506. The loop also includes a pump 508 for circulating the moderator within the loop, a heat exchanger 510 for cooling the moderator to a desired temperature, and a moderator inlet port 512 provided toward the bottom of the calandria 102.
The passive cooling system 502 includes a moderator outlet port 514 located toward the top of the calandria 102, to receive relatively warm moderator fluid. As the moderator temperature rises, fluid within the inlet of the passive cooling loop 516 will tend to flow upward within vertical column 518. As the moderator level rises, the hydraulic head pressure within the column decreases, and may decrease to a level at which the moderator fluid boils and becomes a two-phase mixture. Moderator vapour continues to rise within the column, further reducing the static pressure in the column and promoting further boiling of the liquid within the column 518. The moderator vapour is then passed through a passive heat exchanger 520, optionally submerged in a secondary cooling pool 522 or air cooled, where it condenses and flows back into the calandria 102 via moderator inlet port 524. Additional moderator fluid may be provided by an optional moderator make up source 526 in communication with the passive loop 516, or optionally active loop 506.
While the moderator remains at an elevated temperature, thermal convective forces may auto-circulate fluid through the passive cooling circuit 502 without the need for active pumps or other drive mechanisms. Such passive cooling may be beneficial in instances where electrical power is not available.
What has been described above has been intended to be illustrative of the invention and non-limiting and it will be understood by persons skilled in the art that other variants and modifications may be made without departing from the scope of the invention as defined in the claims appended hereto.
This application claims the benefit of 35 USC 119 based on the priority of co-pending U.S. Provisional Patent Application 61/659,229 filed Jun. 13, 2012 and of co-pending U.S. Provisional Patent Application 61/659,219 filed Jun. 13, 2012, each of those applications being incorporated herein in their entirety by reference.
| Filing Document | Filing Date | Country | Kind |
|---|---|---|---|
| PCT/CA2013/050449 | 6/13/2013 | WO | 00 |
| Number | Date | Country | |
|---|---|---|---|
| 61659229 | Jun 2012 | US | |
| 61659219 | Jun 2012 | US |
