GB2552054A - Nuclear Power Plant - Google Patents

Nuclear Power Plant Download PDF

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Publication number
GB2552054A
GB2552054A GB1707123.4A GB201707123A GB2552054A GB 2552054 A GB2552054 A GB 2552054A GB 201707123 A GB201707123 A GB 201707123A GB 2552054 A GB2552054 A GB 2552054A
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Prior art keywords
reactor
components
reactor vessel
access region
vessel
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Application number
GB1707123.4A
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GB2552054B (en
GB201707123D0 (en
Inventor
Dodd David
Blake Matthew
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Rolls Royce Power Engineering PLC
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Rolls Royce Power Engineering PLC
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Publication of GB201707123D0 publication Critical patent/GB201707123D0/en
Publication of GB2552054A publication Critical patent/GB2552054A/en
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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/19—Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/003—Remote inspection of vessels, e.g. pressure vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/006—Details of nuclear power plant primary side of steam generators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • G21D5/12—Liquid working medium vaporised by reactor coolant
    • Y—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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

A nuclear reactor comprising: a reactor vessel 12 having a head; a plurality of components 16,26 including a plurality of heat exchangers 16 are provided external to and closely coupled to the reactor vessel 12, such that the distance between connection points of the reactor vessel 12 to the components 16,26 are spaced to be less than or equal to half the diameter of the reactor vessel 12; where the components 16,26 are arranged such that an access region is defined between the components 16,26, the access region having a width greater than the diameter of the reactor vessel head. Also disclosed is a nuclear reactor wherein the distance between the connection points of the reactor vessel 12 and the components 16,26 are spaced to be less than or equal to 3 metres. There may be four heat exchangers 16 provided, the heat exchangers 16 being steam generators. One of the components may be a pressuriser 26. The reactor may be configured to have a net output of less than or equal to 700 MWe.

Description

(54) Title of the Invention: Nuclear Power Plant Abstract Title: Modular nuclear power plant (57) A nuclear reactor comprising: a reactor vessel 12 having a head; a plurality of components 16,26 including a plurality of heat exchangers 16 are provided external to and closely coupled to the reactor vessel 12, such that the distance between connection points of the reactor vessel 12 to the components 16,26 are spaced to be less than or equal to half the diameter of the reactor vessel 12; where the components 16,26 are arranged such that an access region is defined between the components 16,26, the access region having a width greater than the diameter of the reactor vessel head. Also disclosed is a nuclear reactor wherein the distance between the connection points of the reactor vessel 12 and the components 16,26 are spaced to be less than or equal to 3 metres. There may be four heat exchangers 16 provided, the heat exchangers 16 being steam generators. One of the components may be a pressuriser 26. The reactor may be configured to have a net output of less than or equal to 700 MWe.
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Nuclear power plant
Technical Field
The present disclosure concerns a nuclear reactor, in particular a close coupled nuclear reactor, and/or a nuclear power plant.
Background
A nuclear power plant generally includes a nuclear reactor, a primary circuit, a heat exchanger, a secondary circuit, and a turbine. The primary fluid in the primary circuit is heated by the nuclear reactor. The primary fluid flows to the heat exchanger, where it heats secondary fluid in the secondary circuit. The heated secondary fluid is then used to drive the turbine to generate electricity.
Conventional nuclear power plants can have a power output of approximately 1600MWe. However, the footprint and capital costs of conventional nuclear power plants are high.
To reduce the required footprint and/or to reduce the capital cost, small or medium modular reactors (SMRs) can be used.
Small or medium modular reactors (SMRs) can produce up to approximately 700MWe. They are referred to as modular reactors because they are assembled from modular units. The economy of scale that can be achieved from modular construction means that SMRs can be a more economically viable option than a conventional nuclear power plant that has high capital costs.
When a nuclear power plant is in operation, maintenance work and refuelling of the reactor vessel often needs to take place.
Often SMRs are integral reactors that have the steam generator and key primary components formed integrally with the reactor vessel. However, integral reactors can lead to significant design challenges and make maintenance and refuelling operations more complex. To simplify maintenance operations a close coupled reactor can be provided. A close coupled reactor has heat exchangers, such as steam generators, and other key components provided outside but adjacent to the reactor vessel.
Summary
According to a first aspect there is provided a close coupled nuclear reactor comprising a reactor vessel having a head and a plurality of components provided external to and coupled to the reactor vessel. The plurality of components may include a plurality of heat exchangers. The components are arranged such that an access region is defined between the components, the access region having a width greater than the diameter of the reactor vessel head.
In this way the reactor vessel head can be moved laterally between the heat exchangers for maintenance. Moving the head laterally is easier and safer than lifting the head vertically over the heat exchangers (and other components).
The heat exchangers may be steam generators
The access region is a volume defined between the reactor vessel and at least one component mounted external to the reactor pressure vessel, for example, between the reactor vessel and at least one heat exchanger. The access region is free from obstruction.
The heat exchangers are fluidly and mechanically coupled to the reactor vessel.
Close coupled nuclear reactor is a term of art that designates a type of reactor. The skilled person understands a closed coupled reactor to be a reactor where the heat exchangers (e.g. the steam generators) are provided separate to and external to the reactor vessel, and the heat exchangers are coupled to the reactor vessel with minimal spacing between heat exchanger and the reactor vessel. For example, the separation between the connection points (e.g. nozzles) of the heat exchangers and the reactor vessel may be less than or equal to half the diameter of the reactor vessel, and/or for example, less than or equal to 3m.
The depth of the access region may extend at least to a position aligned with a lower edge of the reactor vessel head when the head is positioned on the reactor vessel.
Two, three or more heat exchangers may be provided, for example four heat exchangers may be provided.
The distribution of the components about the reactor vessel may be such that the spacing between the components is not equal. For example, the distribution of the heat exchangers (e.g. steam generators) about the reactor vessel may be such that the spacing between the heat exchangers is not equal.
The reactor may be configured for at least 300 MWe. The reactor may be configured for at least 400MWe. The reactor may be configured for less than or equal to 700MWe.
One of the plurality of components may be a pressuriser.
The pressuriser may be positioned and/or dimensioned to extend to a greater height than the reactor vessel.
The access region may be defined directly between the pressuriser and one of the plurality of heat exchangers.
The access region may be defined directly between two of the heat exchangers.
The pressuriser may be diametrically opposed to the access region.
The heat exchangers may be positioned and/or dimensioned such that they extend to a greater height than the reactor vessel.
Providing steam generators that extend to a position higher than the reactor vessel can be beneficial for plant performance.
The reactor may be a pressurised water reactor.
In a second aspect there is provided a nuclear power plant comprising the nuclear reactor according to the first aspect.
The skilled person will appreciate that except where mutually exclusive, a feature described in relation to any one of the above aspects may be applied mutatis mutandis to any other aspect. Furthermore except where mutually exclusive any feature described herein may be applied to any aspect and/or combined with any other feature described herein.
Drawings
Embodiments will now be described by way of example only, with reference to the Figures, in which:
Figure 1 is a schematic of a nuclear power plant;
Figure 2 is a perspective view of a reactor of a nuclear power plant;
Figure 3 is a plan view of the reactor of Figure 2; and
Figures 4 and 5 are plan views of alternative reactors.
Description
Referring to Figure 1, a nuclear power plant is indicated generally at 10. The plant includes a nuclear reactor 11, a primary circuit 14, a heat exchanger which in this example is a steam generator 16, a secondary circuit 18 and a turbine 20. The primary fluid in the primary circuit is heated by the nuclear reactor. The nuclear reactor includes a nuclear reactor vessel that houses nuclear fuel. The primary fluid then flows to the steam generator, where it heats secondary fluid in the secondary circuit. The heated secondary fluid is then used to drive the turbine 20.
Referring now to Figures 2 and 3, the reactor is a close coupled reactor. The reactor vessel 12 is a substantially cylindrical vessel. The vessel has a base and a head 22 that together with a cylindrical body define an enclosed volume of the vessel. The head 22 can be removed from the reactor vessel for refuelling and maintenance.
In the present example, the reactor is a pressurised water reactor. Accordingly, a pressuriser 26 is provided to ensure that the primary fluid (in this case water) in the reactor vessel is maintained as liquid in the reactor and prevented from boiling. The pressuriser 26 is dimensioned and positioned so as to extend to a greater height than the reactor vessel. Such an arrangement can improve performance of the reactor.
In the example shown in Figures 2 and 3, four steam generators 16 are provided. The steam generators are provided external to the reactor vessel 12. The steam generators are coupled (e.g. fluidly and mechanically) to the reactor vessel, such that primary fluid can flow from the reactor vessel to the steam generator. The steam generators may be coupled using one or more pipes 24. The steam generators include a connector 17 (which may be referred to as a nozzle), and the reactor vessel 12 includes a plurality of connectors 23 (which may be referred to as nozzles). The pipes 24 extend between the connectors 23 and the connectors 17. The steam generators are spaced from the reactor vessel by a minimum distance S, for example, the steam generators may be for example less than or equal to 3m, for example 0.5 m from the reactor vessel. In exemplary embodiments, the steam generators may be spaced from the reactor vessel may a distance S that is less than or equal to half the diameter D of the reactor vessel. The steam generators are dimensioned and positioned such that they extend to a greater height than the reactor vessel. Such an arrangement can improve performance of the reactor vessel.
The steam generators 16 are unevenly distributed around the reactor vessel 12. That is, the steam generators are not positioned equidistant apart from each other. The steam generators and the pressuriser are positioned more towards one diametrical side of the reactor vessel than to an opposing diametrical side. In this way, an access region 28 is defined. In the present example, the pressuriser is diametrically opposite the access region 28, and a steam generator is provided either side of the pressuriser. However, in alternative embodiments the pressuriser may be provided at any suitable position, for example adjacent the access region.
The access region has a width W that is greater than the diameter D of the reactor vessel head 22. Preferably the width of the access region is at least equal to the diameter of the reactor vessel head plus a suitable clearance. The access region is free from obstruction. The depth of the access region extends at least to a position aligned with a lower edge of the reactor vessel head when the head is positioned on the reactor vessel. The access region has a radial extent that extends beyond a radial extent of the steam generators. For example, it may be considered that the access region is a volume of free space that provides unhindered and direct access to the reactor vessel.
In use, when maintenance or refuelling is required, the head 22 of the reactor vessel 12 can be lifted slightly and then moved laterally, as indicated by arrow 30. The access region 28 is dimensioned such that the head of the reactor can be removed laterally rather than needing to lift the reactor head upwards and over the steam generators and/or pressuriser, which is more complex and risks damage to the components of the reactor.
Provision of an access region means that access for maintenance and refuelling can be further improved. Without the access region, maintenance and refuelling would be a more complex task particularly because the steam generators and pressuriser extend above the reactor vessel.
In the described example, four steam generators are provided, but in alternative embodiments any suitable number of steam generators may be coupled to the reactor vessel. For example, three steam generators may be provided, as shown in Figure 4, or two steam generators may be provided, as shown in Figure 5. In Figure 5, the spacing between the steam generators is equal in both circumferential directions, but the spacing between the steam generators and pressuriser when considered as a complete group of components is uneven.
In the present example the reactor is a pressurised water reactor (PWR), but in alternative embodiments the reactor may be an alternative technology type, for example, a gas cooled reactor, or liquid metal reactor.
It will be understood that the invention is not limited to the embodiments abovedescribed and various modifications and improvements can be made without departing from the concepts described herein. Except where mutually exclusive, any of the features may be employed separately or in combination with any other features and the disclosure extends to and includes all combinations and sub10 combinations of one or more features described herein.

Claims (13)

Claims
1. A nuclear reactor comprising:
a reactor vessel having a head; and a plurality of components provided external to and closely coupled to the reactor vessel such that the distance between connection points of the reactor vessel and components are spaced to be less than or equal to half the diameter of the reactor vessel, the plurality of components including a plurality of heat exchangers, wherein the components are arranged such that an access region is defined between the components, the access region having a width greater than the diameter of the reactor vessel head.
2. The reactor according to claim 1, wherein two, three or more heat exchangers are provided.
3. The reactor according to claim 2, wherein four heat exchangers are provided.
4. The reactor according to any one of the previous claims, wherein the distribution of the components about the reactor vessel is such that the spacing between the components is not equal.
5. The reactor according to any one of the previous claims, wherein the reactor is configured for less than or equal to 700 MWe.
6. The reactor according to any one of the previous claims, wherein one of the plurality of components is a pressuriser.
7. The reactor according to claim 6, wherein the pressuriser is positioned and/or dimensioned to extend to a greater height than the reactor vessel.
8. The reactor according to claim 6 or 7, wherein the access region is defined directly between the pressuriser and one of the plurality of steam generators.
9. The reactor according to claim 6 or 7, wherein the access region is defined directly between two of the steam generators.
5
10. The reactor according to any one of the previous claims, wherein the steam generators are positioned and/or dimensioned such that they extend to a greater height than the reactor vessel.
11. The reactor according to any one of the previous claims, wherein the 10 reactor is a pressurised water reactor.
12. A nuclear reactor comprising:
a reactor vessel having a head; and a plurality of components provided external to and closely coupled to the 15 reactor vessel such that the distance between connection points of the reactor vessel and components are spaced to be less than or equal to 3 metres, the plurality of components including a plurality of heat exchangers, wherein the components are arranged such that an access region is defined between the components, the access region having a width greater than
20 the diameter of the reactor vessel head.
13. A nuclear power plant comprising the nuclear reactor according to any one of the previous claims.
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Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4416846A (en) * 1978-08-10 1983-11-22 Kraftwerk Union Aktiengesellschaft Nuclear power plant with cooling circuit
US5790619A (en) * 1997-01-15 1998-08-04 Combustion Engineering, Inc. Drain system for a nuclear power plant

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4416846A (en) * 1978-08-10 1983-11-22 Kraftwerk Union Aktiengesellschaft Nuclear power plant with cooling circuit
US5790619A (en) * 1997-01-15 1998-08-04 Combustion Engineering, Inc. Drain system for a nuclear power plant

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GB2552054B (en) 2019-01-02
GB201707123D0 (en) 2017-06-21

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