Nuclear reactor, in particular liquid-metal-cooled compact nuclear reactor
10699816 ยท 2020-06-30
Assignee
Inventors
Cpc classification
G21C1/03
PHYSICS
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
G21C1/32
PHYSICS
G21C15/28
PHYSICS
International classification
G21C1/03
PHYSICS
G21C1/32
PHYSICS
Abstract
The present invention relates to a nuclear reactor (1), in particular a liquid-metal-cooled reactor, provided with a separation structure (5) between hot header (6) and cold header (7), narrower in the upper portion (16) for containment of the headers of the fuel assemblies and wider in the lower element (14) at the active part (4) of the core, with a variously shaped connecting element (15) between the lower element (14) and the upper element (16), and with heat exchangers (11) positioned between the upper portion (16) of said separation structure (5) and the reactor vessel (2), which engage on the connecting element (15) via vertical ducts (20) for being fed with hot primary fluid leaving the core (4).
Claims
1. A liquid-metal-cooled nuclear reactor, comprising: a reactor vessel; a core having an active part; a hot header above the core and in which a primary fluid circulates for cooling the core, the primary fluid being a liquid metal; fuel assemblies; a separation structure supporting the fuel assemblies; a cold header surrounding the hot header and in which the primary fluid circulates for cooling the core, the colder header separated from the hot header by the separation structure; at least one heat exchanger configured to remove heat from the primary fluid via a secondary fluid; wherein the separation structure has a substantially amphora-like shape and includes: a lower element placed around the core at a certain radial distance from the active part of the core such that the liquid metal interposed between the lower element and the active part of the core provides a neutron shielding function that reduces neutron damage of the separation structure to predetermined acceptable limits; and an upper element located above the core, the upper element having a reduced radial extent with respect to the lower element, and being joined to the lower element by a connecting element; wherein the connecting element is equipped with penetrations from which vertical ducts extend to connect to one or more heat exchangers positioned between the upper element of the separation structure and the reactor vessel, for feeding the at least one heat exchanger with hot primary fluid leaving the core; wherein the connecting element and the upper element of the separation structure constitute a radial constraint of an inactive upper part of the fuel assemblies of the core.
2. The reactor according to claim 1, wherein the connecting element between the lower element and the upper element of the separation structure includes a plate.
3. The reactor according to claim 1 wherein: the connecting element includes radially extending lobes, the penetrations being positioned on the radially extending lobes; and the vertical ducts for feeding the at least one heat exchanger engage the penetrations positioned on radially extending lobes.
4. The reactor according to claim 3, further comprising one or more free volumes for installation of one or more auxiliary components of the reactor, each of the free volumes being positioned between portions of the connecting element without the radially extending lobes and the reactor vessel, and also between portions the amorpha-like shape of the separation structure and the reactor vessel.
5. The reactor according to claim 1, wherein the primary fluid contained within the upper element of the separation structure is substantially stagnant.
6. The reactor according to claim 1, wherein the secondary fluid includes water brought to steam in the at least one heat exchanger that is a steam generator.
7. The reactor according to claim 6, wherein the liquid metal includes a heavy liquid metal.
8. The reactor according to claim 7, wherein the heavy liquid metal includes lead.
9. The reactor according to claim 1, wherein the lower element acts as an element of hydraulic containment of the core.
10. The reactor according to claim 1, wherein the at least one heat exchanger, includes a steam generator.
11. The reactor according to claim 1 wherein the upper element having the reduced radial extent with respect to the lower element is generally cylindrical.
12. The reactor according to claim 1 wherein the connecting element extends outwardly between the upper element to the lower element.
13. The reactor according the claim 12, wherein the connecting element extends generally perpendicular from the upper element to the lower element.
14. The reactor according to claim 12 wherein the connecting element is generally horizontal and the vertical ducts extend vertically directly from the connecting element.
Description
BRIEF DESCRIPTION OF THE DRAWINGS
(1) The invention is described in the following non-limitative example of embodiment, with reference to the figures in the accompanying drawings, in which:
(2)
(3)
(4)
BEST MODE FOR CARRYING OUT THE INVENTION
(5) Referring to
(6) The reactor vessel 2 houses pumps 10 and heat exchangers 11 through which the primary fluid 8 runs and which transfer the power generated in the core 4 to a secondary fluid circulating in an external secondary circuit (known and not shown).
(7) Preferably, the primary fluid 8 is a liquid metal and, in particular, a heavy liquid metal, for example lead or a lead-bismuth eutectic, while the secondary fluid is water (which vaporizes during the heat exchange with the primary fluid), and therefore the heat exchangers 11 are steam generators. A blanket gas is present above the primary fluid 8 in the reactor vessel 2.
(8) Various auxiliary devices are housed inside the separation structure 5, including support structures for instrumentation and control rods, not described for simplicity as they are known and not pertinent to the present invention.
(9) The separation structure 5 comprises a grid 12, of known design, supporting the fuel elements 13, a lower element 14 for hydraulic containment of the core 4 and opportunely shaped and starting at a certain radial distance from the active part of the core to reduce neutron damage of the structure to acceptable limits, and a connecting element 15 having different possible shapes, for example conical or plate-like, between the lower element 14 and an upper element 16.
(10) In this solution, the neutron shielding function is accomplished by the liquid metal interposed between element 14 and the outer ring of fuel elements 13, while the rings of shielding elements, usually placed between core and separation structure in known solutions, are reduced in number or totally eliminated.
(11) Element 16 is substantially cylindrical on the outside and of variable thickness, with an internal profile modelled to contain and radially constrain the remaining shielding elements, or in the case where they are totally eliminated, the outer ring of fuel elements in their inactive upper portion 17. This results in element 16 having a smaller radial extension with respect to element 14.
(12) The heat exchangers 11 are arranged entirely within the cold header 7 and are circumferentially spaced around the cylindrical upper portion 16 of the separation structure 5. Each pump-exchanger unit 21 engages on the connecting element 15; suitable sealing devices 18 (known and not shown for simplicity) are provided between the connecting element 15 and the cylindrical elements 19 integral with the heat exchangers 11 and which delimit the ducts 20 that feed the pump-exchanger units 21 with the hot primary fluid 8 leaving the core. In consequence, the volume inside element 16 is substantially stagnant, without fluid-induced vibration risks for the core's instrumentation and control systems contained therein.
(13) Except for the portion perforated for engagement of the cylindrical elements 19, element 14 and element 15 can be axisymmetric or, as indicated in
(14) The separation structure 5 can be appropriately supported according to known solutions in the lower part of the reactor vessel or in the upper part of the reactor's roof.
(15) A solution is shown in
(16) The advantages of the present invention clearly emerge from the foregoing description: The primary circuit of the reactor is a compact system. The rings of shielding elements of the separation structure 5 are reduced in number or completely eliminated, with advantages in economy and mechanical strength of the core's radial constraints.
(17) The elimination of the rings of shielding elements reduces the number of components to replace, simplifying the maintenance operations to be carried out and reducing reactor downtime.
(18) The radial positioning of the heat exchangers is not limited by the maximum size of the separation structure 5, but only by its element 16, which has a smaller diameter.
(19) The feed of the heat exchangers does not need a duct departing radially from the separation structure and is not performed from above the element 16, as contemplated in known solutions, but is performed vertically via a sealed device 18 between the cylindrical element 19 of the duct 20 that feeds the pump-exchanger unit 21 and the connecting element 15.
(20) The lobed shape of the lower element 14 and of the connecting element 15 of the separation structure 5 leave wide free volumes 24 between the less radially extended portions 23 of the lower element 14 and the connecting element 15 with respect to the reactor vessel 2 for the installation of more auxiliary components 25 of the reactor.
(21) The lobed shape of the lower element 14 and of the connecting element 15 of the separation structure 5 and the corresponding lobed shape of the cover 26 enable replacing the separation structure 5 without removing the reactor's auxiliary components 25.
(22) Finally, it is understood that numerous modifications and variants can be made regarding the reactor described and illustrated herein without departing from the scope of the appended claims.