EP0500656A1 - Reacteur nucleaire refroidi par metal liquide - Google Patents

Reacteur nucleaire refroidi par metal liquide

Info

Publication number
EP0500656A1
EP0500656A1 EP90916698A EP90916698A EP0500656A1 EP 0500656 A1 EP0500656 A1 EP 0500656A1 EP 90916698 A EP90916698 A EP 90916698A EP 90916698 A EP90916698 A EP 90916698A EP 0500656 A1 EP0500656 A1 EP 0500656A1
Authority
EP
European Patent Office
Prior art keywords
reactor
tank
heat
nuclear reactor
core
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Withdrawn
Application number
EP90916698A
Other languages
German (de)
English (en)
Inventor
Heinz-Wilhelm Hammers
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Siemens AG
Siemens Corp
Original Assignee
Siemens AG
Siemens Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Siemens AG, Siemens Corp filed Critical Siemens AG
Publication of EP0500656A1 publication Critical patent/EP0500656A1/fr
Withdrawn legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G21C13/087—Metallic vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • 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

Definitions

  • the present invention relates to a liquid metal-cooled nuclear reactor for a nuclear power plant based on the module principle in a reactor cavern equipped with cooling surfaces with a reactor tank which contains a reactor core, one or more heat exchangers and primary pumps and which is surrounded by a double tank.
  • the total output of a nuclear power plant should no longer be achieved with a single large reactor, but with several small reactors. In this way, the nuclear power plant can continue to be operated with reduced output in the event of a reactor failure, inspection or maintenance.
  • nuclear power plants that consist of several modular reactors with an individual output of approx. 200 MW each can have some disadvantages in terms of fuel consumption and breeding rate, but considerable Have advantages in construction and operation.
  • a modular reactor can completely release its residual heat via its surface.
  • Reactor tank is conventionally arranged in a second, so-called double tank containing inert gas, supported at its lower end on a foot ring and guided at its upper end with a ring in a removable support ring which rests on the upper edge of a concrete reactor cavern.
  • the double tank is designed to hold the liquid sodium in the event of damage to the reactor tank.
  • US Pat. No. 4,650,642 describes a nuclear reactor which, above all, dissipates the residual heat after an extremely unlikely meltdown and is intended to prevent damage to the environment.
  • a thick and cast steel shell anchored in the bottom is provided below the reactor tank, which is intended to accommodate the reactor core melted through the reactor tank.
  • the cylindrical side wall of this shell which is provided as a double tank, touches either thermal insulation or a cooling jacket which is surrounded by a biological shield made of concrete.
  • Cast steel containers of this type and size are very heavy and expensive and cannot be cast in one piece. They must therefore be chopped together from several pieces.
  • Essential characteristic of this Nuclear reactor is a water / steam cooling system below the reactor. Double tank and cavern are only one component.
  • the double tank and cooling surfaces cannot be repaired from the outside and can hardly be dismantled.
  • this reactor should avoid the repeatedly discussed possibility that cracks in the tank or in the structure progress, that the core lowers and the control rods suspended from the lid are pulled out of the core, by stacking the essential parts one above the other on the bottom of the Reactor cavern resting. In this way, relative movements between the reactor core and control rods in the event of an earthquake are reduced or avoided entirely, which means that considerable expenditure for safety measures can be avoided.
  • this reactor can emit its entire heat to cooling surfaces in the reactor cavern via the surface of its reactor tank and through its double tank, but these must be correspondingly reliable due to their high safety significance. This reliability is achieved through multiple redundancy of the entire cooling system, through emergency power supply and / or through operation in natural circulation. These measures are associated with special costs.
  • the object of the present invention is to provide a removable, liquid-metal-cooled nuclear reactor for a nuclear power plant based on the module principle in a reactor cavern equipped with cooling surfaces with a reactor tank which contains a reactor core, one or more heat exchangers and primary pumps and which is surrounded by a double tank in which the secondary heat first saved and then to the environment is delivered.
  • Reactor cavern with a reactor tank which contains a reactor core, a heat exchanger and primary pumps and which is surrounded by a double tank made of cast iron serving as a heat store and of several interconnected and stacked rings and a base.
  • This double tank can also have approximately the same shape in the bottom area as a double tank previously welded together from ferritic or austenitic steel sheets. However, it has an eight to ten times greater wall thickness, so that its heat capacity is sufficient to store the residual heat of the reactor for hours and to release it by radiation and convection to the cooling surfaces in the reactor cavern. Due to the large storage effect, the subsequent cooling systems can start up slowly, and can even be switched off or repaired for a limited time. The effort previously made for the immediate availability of the cooling system can thus be considerably reduced, which leads to cost savings.
  • This double tank can be removed for inspection or repair or for disposal with little effort.
  • the double tank consist of a spheroidal graphite cast iron, also called spherulitic cast iron.
  • This material according to DIN 1693 is approved in the core technology for the production of transport containers for fuel elements.
  • transport containers have already been shown to be able to withstand a fall from higher heights and higher temperatures for a long time.
  • this heat accumulator can be provided with ribs to improve the heat transfer without great effort.
  • the additional costs that result from the much greater weight of the cast Doppelta ⁇ ks are by the considerably lower price of cast iron compared to the price of welded sheet steel containers.
  • the double tank has considerable advantages for external influences due to its large wall thickness.
  • Critical buckling pressure against external pressure surges and penetration protection are many times higher than with a thin-walled steel tank, so that additional protective measures outside the double tack can be omitted or reduced.
  • the rings which can be releasably connected and stacked one above the other and the base are reinforced at their contact points and can be screwed together remotely.
  • the heavy double tank consists of several parts, each of which can be manufactured, tested, transported and assembled individually.
  • the rings and the base each have two ring-shaped seals in their contact points, between which a test bore is arranged, which leads to the outside. This means that the seals can be monitored from outside.
  • FIGS 1 to 5 show embodiments of the invention.
  • FIG. 1 shows a vertical longitudinal section through a nuclear reactor according to the invention, including its arrangement in a cavern.
  • Figures 2 and 3 each show a cross section through
  • FIG. 4 shows an enlarged representation of the lower left part from FIG. 1.
  • Figure 5 shows a further enlarged view
  • the reactor tank 1 is surrounded by a double tank 2 and is located in a reactor cavern 3 which has cooling surfaces 4 on its inside.
  • the bottom 5 of this The cavern is designed as a supporting platform 6 and, centered on top of one another, supports the double tank 2 consisting of several rings 2a and a bottom 2b, the reactor tank 1, on which there is a supporting plate 7, which is laterally connected to an external flow guide 8, on which there is a grating plate 9 consisting of two through pipe sockets 10 connected perforated plates 9a and 9b, these pipe sockets 10 transfer the weight of the core elements 11 onto the support plate 7.
  • the reactor core 12 which is shown only schematically in FIG. 1 but later in more detail in FIG. 4, is surrounded all around by a multi-part metallic shield 13, which in turn is surrounded by an inner flow guide 14 and is connected to a shaft 15 in a lockable manner above the core.
  • the flow guide 14 is extended upwards through a chimney 23 which is initially of a plurality of electromagnetic 'pumps 16, 17 and it is surrounded by a heat exchanger 18 as part of a secondary circuit not shown. This secondary cooling circuit transports the reactor heat to a steam circuit to supply steam turbo generators.
  • the heat exchanger 18 can be composed of a single annular tube bundle or of a plurality of partial tube bundles connected in parallel. Not shown, but also possible, is the use of mechanical pumps, the pump shafts between the tube bundles of the heat exchanger 18 being guided upwards to the drive motor via the ring cover 21. In the upper region, the shaft 15, the chimney 23 and the inner jacket of the heat exchanger 18 initially have small holes 19 distributed uniformly over the circumference. In addition, the shaft 15 has larger slots 20, through which, as well as through the holes 19, the one rising from the reactor core 12 hot sodium can flow to the heat exchanger 18. This is together with the active part 16 of the electromagnetic pumps on one
  • Ring cover 21 attached, which is independent of the instrumentation cover 22 can be mounted because it is carried by the shaft 15.
  • the shaft 15 connects the shield 25 to the instrumentation cover 22 and contains both the linkage 24 for the regulation and shutdown and the lines for the instrumentation of the reactor core 12.
  • Instrumentation cover 22 is sealed with respect to the ring cover 21 by inflatable seals which are not shown here but which are customary in the case of liquid-metal-cooled nuclear reactors, so that axial movement of the components against one another is possible.
  • a lifting and turning device for the cover 22 which is also known in nuclear reactors and is therefore not shown here, is arranged, which is required when changing the core element.
  • FIG. 4 shows, with the same designations as in FIGS. 1 to 3, how the base 2b, the reactor tank 1, the support plate 7 and the grid plate 9 are stacked centered one above the other on the support platform 6 at the base 5 of the reactor cavern 3.
  • the reactor core 12 consisting of the core elements 11 is initially surrounded by a multi-part metallic shield 13, which in turn is surrounded by a flow guide 14, which also acts as a shield.
  • the shaft 15 and an additional axial shield 25 rest on the shield 13 above the core elements 11.
  • This shield 25 has vertical openings 26 for the passage of the coolant, for receiving the rods 24 and various core instrumentation and for changing the core elements 11.
  • Figure 5 shows a reinforced point of contact between a ring 2a and the bottom 2b, which are held together by remote-controlled screws 30.
  • a centering 31 is provided on the inside.
  • the hot sodium flows from the reactor core 12 upwards through the shaft 15 and through the holes 19 or slots 20 to the heat exchanger 18, where it emits its heat to the outside with a secondary cooling circuit, not shown. Then the cooled.
  • Sodium in the delivery gap of the electromagnetic pumps which is formed by an active part 16 and a passive part 17, is pressed downwards between the inner wall of the flow guide 8 and the outer wall of the flow guide 14 to the grid plate 9, from where it is in the usual way through slots in the Pipe socket 10 is passed into the lower end of the core elements 11 to absorb their heat. If the pumps fail, the sodium flows in the same way in natural circulation, also giving off its heat to the outside with a secondary cooling circuit. If this should fail, the heat via the tank 1 and the double tank 2 to the cooling surfaces 4 or to a circulating gas in the
  • the double tank 2 consisting of several rings 2a and a bottom 2b, has, for. B. with a diameter of 5 m, a wall thickness of 150 mm and consists of a spherulitic cast iron GGG according to DIN 1693.
  • Considerable amounts of heat can be stored in this wall and released to the cooling surfaces 4 with a time delay. Compared to the usual heat storage in concrete, much higher temperatures can be permitted.
  • a change machine known per se is moved over the cover 22, which removes the spent core elements 11 directly from the reactor core 12 and inserts new core elements.
  • the lifting and turning device mentioned above which can be removed for inspection or replacement, lifts the
  • the desired core element is then pulled into a bottle sealed to the outside. If a repair to heat exchangers or pumps is necessary, a special component change bottle is moved over the ring lid 21, with which the ring-shaped heat exchanger 18 with the active parts 16 of the electromagnetic pumps attached to it can also be replaced in an inert and sealed atmosphere.
  • Exchangeable bottles of this type are known and customary in order to inspect or replace heat exchangers and pumps in the liquid metal-cooled nuclear power plants mentioned at the outset.
  • the dimensions of the modular reactor according to the invention also allow the shaft 15 or the parts 7, 8, 9, 10, 13, 14, 17 and 23 or even one surrounding the reactor core in this way entire reactor tank 1 and the individual rings 2a and the bottom 2b of the double tank to be replaced.
  • the remaining module reactors of the same nuclear power plant are kept in operation during such repairs as well as during the core element change, so that a high availability of the nuclear power plant is ensured.

Landscapes

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

Abstract

Un réacteur nucléaire refroidi par métal liquide, destiné à une centrale nucléaire modulaire, est logé dans une caverne de réacteur (3) pourvue de surfaces de refroidissement (4). Le réacteur comprend une cuve (1) qui renferme un coeur (12), un ou plusieurs échangeurs de chaleur (18) et des pompes primaires. Elle est entourée d'une double cuve (2) en fonte qui fait office d'accumulateur de chaleur et qui est constituée d'une pluralité d'anneaux superposés (2a) et d'un socle (2b). Cet agencement simplifie la structure et facilite le fonctionnement, le contrôle et la réparation ou le remplacement. La fabrication de la double cuve (2) en fonte offre des avantages appréciables pour la conception de l'installation complète, s'agissant des influences externes. La fonction accumulateur de chaleur offre des avantages appréciables pour la conception des systèmes de dissipation thermique des surfaces de refroidissement (4).
EP90916698A 1989-11-17 1990-11-15 Reacteur nucleaire refroidi par metal liquide Withdrawn EP0500656A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3938345 1989-11-17
DE3938345A DE3938345A1 (de) 1989-11-17 1989-11-17 Fluessigmetallgekuehlter kernreaktor

Publications (1)

Publication Number Publication Date
EP0500656A1 true EP0500656A1 (fr) 1992-09-02

Family

ID=6393784

Family Applications (1)

Application Number Title Priority Date Filing Date
EP90916698A Withdrawn EP0500656A1 (fr) 1989-11-17 1990-11-15 Reacteur nucleaire refroidi par metal liquide

Country Status (5)

Country Link
US (1) US5229067A (fr)
EP (1) EP0500656A1 (fr)
JP (1) JPH06501769A (fr)
DE (1) DE3938345A1 (fr)
WO (1) WO1991007758A1 (fr)

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US5465280A (en) * 1994-06-08 1995-11-07 Wedellsborg; Bendt W. Pressure vessel apparatus
US5544210A (en) * 1995-07-11 1996-08-06 Wedellsborg; Bendt W. Pressure vessel apparatus for containing fluid under high temperature and pressure
US6259760B1 (en) * 1999-09-08 2001-07-10 Westinghouse Electric Company Llc Unitary, transportable, assembled nuclear steam supply system with life time fuel supply and method of operating same
US7139352B2 (en) * 1999-12-28 2006-11-21 Kabushiki Kaisha Toshiba Reactivity control rod for core
JP2003028975A (ja) * 2001-07-10 2003-01-29 Central Res Inst Of Electric Power Ind 原子炉
JP3909700B2 (ja) * 2003-03-04 2007-04-25 独立行政法人 日本原子力研究開発機構 原子炉容器の熱荷重緩和装置
US6763645B2 (en) * 2003-05-14 2004-07-20 Stanley F. Hunter Protecting building frames from fire and heat to avoid catastrophic failure
ITRM20070256A1 (it) * 2007-05-07 2008-11-08 Susanna Antignano Impianto nucleare supersicuro e a decommissioning semplificato/facilitato.
FR2925973B1 (fr) * 2007-12-28 2010-01-01 Areva Np Cuve reacteur d'un reacteur nucleaire a neutrons rapides de type a boucles
US8571167B2 (en) * 2009-06-01 2013-10-29 Advanced Reactor Concepts LLC Particulate metal fuels used in power generation, recycling systems, and small modular reactors
US8767902B2 (en) * 2010-02-22 2014-07-01 Advanced Reactor Concepts LLC Small, fast neutron spectrum nuclear power plant with a long refueling interval
US20120307956A1 (en) 2010-02-05 2012-12-06 Singh Krishna P Nuclear reactor system having natural circulation of primary coolant
US8584692B2 (en) 2010-10-06 2013-11-19 The Invention Science Fund I, Llc Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid
US8781056B2 (en) * 2010-10-06 2014-07-15 TerraPower, LLC. Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid
US9008257B2 (en) 2010-10-06 2015-04-14 Terrapower, Llc Electromagnetic flow regulator, system and methods for regulating flow of an electrically conductive fluid
JP6850128B2 (ja) 2014-04-14 2021-03-31 アドバンスト・リアクター・コンセプツ・エルエルシー 合金のマトリックス中に分散したセラミック核燃料

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Title
See references of WO9107758A1 *

Also Published As

Publication number Publication date
JPH06501769A (ja) 1994-02-24
DE3938345A1 (de) 1991-05-23
US5229067A (en) 1993-07-20
WO1991007758A1 (fr) 1991-05-30

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