The present invention relates to a nuclear reactor, in particular a compact liquid-metal-cooled nuclear reactor, equipped with one of more primary heat exchangers.
In particular, the present invention relates to a reactor where the primary heat exchangers, in which the heat produced in the core is transferred from a primary fluid (liquid metal) to a secondary fluid (water), are installed inside the main reactor vessel that also houses the core, namely in the volume that, with the components of the reactor contained therein, is called “primary system”. A hydraulic separation structure containing the core internally delimits a volume called the hot header and a volume on the outside called the cold header.
Italian Patent Applications No. MI2005A001752 and No. MI2007A001685 show a reactor of this type, wherein a substantially cylindrical separation structure delimits a central hot header and an annular cold header, which surrounds the hot header; the cold header houses a plurality of integrated heat-exchange units, each of which includes a pump and one or two heat exchangers; each integrated unit has an inlet connected to the hot header through specially provided ducts for the primary fluid.
However, these solutions, like others generically similar with heat exchangers of different configuration, are not devoid of drawbacks, especially in terms of dimensions, in particular due to the complexity of the canalization system of the primary fluid and inadequate utilization of the spaces. The pump-exchanger units must be housed outside the separation structure between the hot header and cold header, but said structure has a relatively large diameter because it contains the core and usually the neutron shielding elements of the structure. The pump-exchanger units are thus installed in a circumferential position with respect to the centre of the reactor, with a consequent increase in the diameter of the reactor vessel, which contains all the components of the primary system.
Documents US2013/266111, EP0308691 and JPH06174871 usefully have a separation structure of smaller diameter in the upper part and larger diameter in the lower part. In these solutions, the refrigerant fluid exiting from the core rises inside the separation structure to its upper edge, where the direction reverses to top-down feed the heat exchanger units. Similarly, these solutions are not without drawbacks, such as the constructional complexity of the zone of fluid direction reversal and the risk of entraining blanket gas that, in the case where the refrigerant fluid is a liquid metal, could cause accidental positive reactivity insertions in the core.
The object of the present invention is to provide a nuclear reactor, in particular a liquid-metal-cooled nuclear reactor, which overcomes the indicated drawbacks of known solutions and has both constructional and safety advantages.
The present invention thus concerns a nuclear reactor, in particular a liquid-metal-cooled nuclear reactor, as defined in the appended claim 1, and, for its auxiliary characteristics and plant configurations, in the dependent claims.
The invention is described in the following non-limitative example of embodiment, with reference to the figures in the accompanying drawings, in which:
Referring to
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).
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.
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.
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.
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.
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.
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.
Except for the portion perforated for engagement of the cylindrical elements 19, element 14 and element 15 can be axisymmetric or, as indicated in
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.
A solution is shown in
The advantages of the present invention clearly emerge from the foregoing description:
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.
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.
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.
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.
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.
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.
Number | Date | Country | Kind |
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GE2015A0036 | Mar 2015 | IT | national |
Filing Document | Filing Date | Country | Kind |
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PCT/IB2016/051503 | 3/17/2016 | WO | 00 |
Publishing Document | Publishing Date | Country | Kind |
---|---|---|---|
WO2016/147139 | 9/22/2016 | WO | A |
Number | Name | Date | Kind |
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5178821 | Gluntz | Jan 1993 | A |
5737379 | Erbes | Apr 1998 | A |
8418532 | Nam | Apr 2013 | B2 |
20080310575 | Cinotti | Dec 2008 | A1 |
20100290579 | Cinotti | Nov 2010 | A1 |
20130266111 | Young | Oct 2013 | A1 |
Number | Date | Country |
---|---|---|
4432705 | Jul 1995 | DE |
0308691 | Mar 1989 | EP |
2150255 | Apr 1973 | FR |
2995123 | Mar 2014 | FR |
1977066188 | Jun 1977 | JP |
1978006797 | Jan 1978 | JP |
H06174871 | Jun 1994 | JP |
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Encyclopedia Britannica. Pressurized-Water Reactor page. Nuclear Energy. 2012. https://www.britannica.com/technology/pressurized-water-reactor. |
Italian Application MI2001A001752 English Translation and Drawings. |
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International Search Report and Written Opinion for International Application No. PCT/IB2016/051503 dated Jun. 21, 2016. |
Number | Date | Country | |
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20180061513 A1 | Mar 2018 | US |