CA1326717C - Heating reactor system with an afterheat removal circuit and use of the latter for boiling water reactors and pressurized water reactors - Google Patents
Heating reactor system with an afterheat removal circuit and use of the latter for boiling water reactors and pressurized water reactorsInfo
- Publication number
- CA1326717C CA1326717C CA000614208A CA614208A CA1326717C CA 1326717 C CA1326717 C CA 1326717C CA 000614208 A CA000614208 A CA 000614208A CA 614208 A CA614208 A CA 614208A CA 1326717 C CA1326717 C CA 1326717C
- Authority
- CA
- Canada
- Prior art keywords
- reactor
- heat exchanger
- control
- vortex chamber
- connection
- 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.)
- Expired - Fee Related
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Classifications
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
Abstract In heating reactors which in particular operate according to the principle of internal natural circulation, an afterheat removal circuit is connected to an intermediate circuit via at least one flow rate regulating unit which maintains a minimum flow through the afterheat removal cooler during afterheat removal operation. The intermediate circuit connects a first heat exchanger inside the reactor to a second heat exchanger via a hot and a cold line, the cold line containing a pump. According to the invention, a controllable element of power fluidics, a so-called vortex chamber valve with three hydraulic connections for the supply, control and outlet current, is used as the flow rate regulating unit, whereby the influx pipe of the afterheat removal circuit is connected to the hot line of the intermediate circuit via an internally controllable current path of the vortex chamber valve and the hydraulic connection for the control current is connected to the cold line on the delivery side of the pump of the intermediate circuit. The invention also relates to use of the afterheat removal circuit with a vortex chamber valve in boiling water reactors or pressurized water reactors which serve to generate driving steam for steam turbo-generator units.
Description
---i` 13267~7 The invention relates to a heating reactor system, particularly for light-water reactors, comprising a nuclear reactor having a reactor pressure vessel, said reactor pressure vessel containing a volume of water as primary coolant, a core o~
said nuclear reactor belng located within said volume of water and comprising a first heat exchanger and a second heat exchanger connected to one another via an intermediate circuit for a secondary coolant, and an afterheat removal circuit, which contains an afterheat removal cooler, connected to the intermediate circuit via cooler connection pipes in the form of influx pipes and reflux pipes and with at least one flow rate regulating unit inserted in the cooler connection pipes.
Such heating reactor system is known and illustrated in Figure 3 on page 29 of the periodical "Nuclear Europe", 11-12/1987, pages 28 to 30, whereby the afterheat removal coolers, particularly air coolers, are not connected directly to the lines of the intermediate circuit, but indirectly via an intermediate heat exchanger. The intermediate heat exchanger is ~or its part connected to the hot or the cold secondary coolant line of the intermediate circuit via an output pipe and via a return pipe in which shut-off valves are disposed. The known heating reactor system is intended for a thermal power output of 5 MW.
The present invention relates to heatin~ reactor systems with a thermal power output in the range of approximately S to ~00 MW. It starts wlth the consideration that all sub~systems in such a heating reac~or system must be designed as simply as possible without forfeiting safety. If valves or drive pumps are provided in an afterheat removal circuit, ~hen not only their actual price~
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but also the power supply (possibly emergency power supply) and monitoring of such units is reflected in the books. Moreover, the safety-related contol mechanisms must be redundant.
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said nuclear reactor belng located within said volume of water and comprising a first heat exchanger and a second heat exchanger connected to one another via an intermediate circuit for a secondary coolant, and an afterheat removal circuit, which contains an afterheat removal cooler, connected to the intermediate circuit via cooler connection pipes in the form of influx pipes and reflux pipes and with at least one flow rate regulating unit inserted in the cooler connection pipes.
Such heating reactor system is known and illustrated in Figure 3 on page 29 of the periodical "Nuclear Europe", 11-12/1987, pages 28 to 30, whereby the afterheat removal coolers, particularly air coolers, are not connected directly to the lines of the intermediate circuit, but indirectly via an intermediate heat exchanger. The intermediate heat exchanger is ~or its part connected to the hot or the cold secondary coolant line of the intermediate circuit via an output pipe and via a return pipe in which shut-off valves are disposed. The known heating reactor system is intended for a thermal power output of 5 MW.
The present invention relates to heatin~ reactor systems with a thermal power output in the range of approximately S to ~00 MW. It starts wlth the consideration that all sub~systems in such a heating reac~or system must be designed as simply as possible without forfeiting safety. If valves or drive pumps are provided in an afterheat removal circuit, ~hen not only their actual price~
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la 20355-299~
but also the power supply (possibly emergency power supply) and monitoring of such units is reflected in the books. Moreover, the safety-related contol mechanisms must be redundant.
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2 20365-2g94 Star~ny with a heating reactor system according to the opening paragraph, ~he present invention is based on the object of designing the afterheat removal clrcuit in such a way that the heating reactor can be swltched from normal operation ~o afterheat removal operation without the conventional shut-off valves or control valves, i.e. without valves which have so-called valve cones or seals which are mechanically pressed against a valve seat with a valve tappet or the like (closed position) or are lifted from this seat (open posltion). Moreover, it should be possible to switch the coollng of the core from normal operation to afterheat removal operation without such fittinys ln such a way that a so-called passive and at the same time inheren~ly safa a~terheat removal circuit is provlded, i.e. different from the known heating reactor sys~em according to "Nuclear Europe" wherein by opening the conventional valves the secondary medium of ~he intermedlate circuit is guided via the a~terheat removal cooler during afterheat removal.
In a heating reactor system which an afterheat removal clrcuit of the klnd defined above the ob;ect is solved in accordance with the present invention by providing a vortex chamber valve as the ~low ra~e regulating unit.
Vortex chambar valves are purely ~luidic elements tha~
opera~e solely on the basis of flow effect~, th~t have no movable parts and that do no re~uire any auxiliary energy outside the system. Reference ls made in this connec~ion to the arti~la "Konstruktlon und Leistung von Wirbelgeraten" (Design and powar of vortex devices) by H. ~rombach in the perlodlcal "messen ~ s~euern - regeln", VEB Verlay Technlk Berlin, Volume 11, November 1~78, 132~717 3 203~S-2994 pages 638 - 6g2, particularly payes 641 and 642.
The advantage that can be achieved with the present invention can be seen primarily therein ~hat so-called motor fittings ~remote-controllable, motor-driven valves) or other conventional valves comprising seal and valve seat in multiple arrangement are unnecessary. The afterheat removal clrcuit with the vortex chamber valve ensures the automatic, inherently safe change-over by hydraulic or fluidlc means without mechanically moved parts.
According to a preferred embodiment of the present invention the vortex chamber valve in a heating reactor system with a pump in the intermediate circuit is provided with a supply connection, a control connection and an outlet connection, whereby the supply connection is connected to the hot line, the outlet connection is connec~ed to the cold line via the afterheat ramoval cooler and the control connection on the delivery side of the pump is likewise connected to the cold line of the intermediate circuit The change-over to afterheat removal opexation according to the prinaiple of natural circulation thereby occuræ
automatically through the vortex chamber valve when the pump in the intermediate circuit is stopped. To this end, the vortex chamb~r valve is advantageously lnserted in the influx pipe of the afterheat removal cooler. Accordlng to fur~her advantag~ous embodiments, the first heat ~xehanger is arranged in the volume of ~ater at a dlstance above the upper edge of the core and can be heated on the primary ~ide by the primary coolant and the pipes o~
the lnterm~diate circuit connected on the secondary ~lde to the heat exchanger tubes of the first heat exchanger ara guided to the , . ~ .
In a heating reactor system which an afterheat removal clrcuit of the klnd defined above the ob;ect is solved in accordance with the present invention by providing a vortex chamber valve as the ~low ra~e regulating unit.
Vortex chambar valves are purely ~luidic elements tha~
opera~e solely on the basis of flow effect~, th~t have no movable parts and that do no re~uire any auxiliary energy outside the system. Reference ls made in this connec~ion to the arti~la "Konstruktlon und Leistung von Wirbelgeraten" (Design and powar of vortex devices) by H. ~rombach in the perlodlcal "messen ~ s~euern - regeln", VEB Verlay Technlk Berlin, Volume 11, November 1~78, 132~717 3 203~S-2994 pages 638 - 6g2, particularly payes 641 and 642.
The advantage that can be achieved with the present invention can be seen primarily therein ~hat so-called motor fittings ~remote-controllable, motor-driven valves) or other conventional valves comprising seal and valve seat in multiple arrangement are unnecessary. The afterheat removal clrcuit with the vortex chamber valve ensures the automatic, inherently safe change-over by hydraulic or fluidlc means without mechanically moved parts.
According to a preferred embodiment of the present invention the vortex chamber valve in a heating reactor system with a pump in the intermediate circuit is provided with a supply connection, a control connection and an outlet connection, whereby the supply connection is connected to the hot line, the outlet connection is connec~ed to the cold line via the afterheat ramoval cooler and the control connection on the delivery side of the pump is likewise connected to the cold line of the intermediate circuit The change-over to afterheat removal opexation according to the prinaiple of natural circulation thereby occuræ
automatically through the vortex chamber valve when the pump in the intermediate circuit is stopped. To this end, the vortex chamb~r valve is advantageously lnserted in the influx pipe of the afterheat removal cooler. Accordlng to fur~her advantag~ous embodiments, the first heat ~xehanger is arranged in the volume of ~ater at a dlstance above the upper edge of the core and can be heated on the primary ~ide by the primary coolant and the pipes o~
the lnterm~diate circuit connected on the secondary ~lde to the heat exchanger tubes of the first heat exchanger ara guided to the , . ~ .
outside through the wall of the reactor pressure vessel. If the cover of the reactor pressure vessel is to be kept ~ree of such penetrations, then it is advi~able that the pipes connected on the secondary side to the heat exchanger tubes of the first heat exchanger penetrate the casing wall of the reactor pressure vessel below the closure head.
The arrangement for the reactor pressure vessel of the heating reactor sys~em and the first and second heat exchangers can be even more compac~ in tha~ the second heat exchanyer is also arranged integrally within the space enclosed by the reactor pressure vessel, preferably within the steam plenum. In this case an output pipe as well as a return pipe, which are connected to the heat exchanger tubes of the second heat exchanger, are advisably guided to the outside through the wall of the reactor pressure vessel and are connected to an external hea~ supply network. To keep the cover of the reactor pressure vessel free, it is al30 advisable that the outlet pipe and the return pipe penetrate the caslng wall of the reactor pressure vessel below the closure head flange Accordiny to another broad aspect of the present invention there ls provlded a heating reactor system, particularly for llght-water reactors, comprising a first heat exchanger and a second heat exchanger connec~ed to one another vla an intermediate circult for the secondary coolant and with the additional features of an afterheat removal circuit which contains an afterheat removal cooler and which i5 connected to the secondary side of a heat exchanger arranged in the reactor pressure vessel via cooler connec~ion pipes ln the form of an influx pipe and a reflux pipe, ~3~
hereby a vortex chamber valve is inserted in he cooler connection pipes as a flow rate regulating unit and whereby the heat exchanger is a condenser arranged in the steam plenum o~ the reactor pressure vessel.
This heating reactox system also solves ~he object on which the present invention is based and which was explained at the beginning. Such a heating reactor system is preferred for smaller heating reactors with a thermal reactor output in a range betwean approximately 5 and 50 MW, whereas the heating reactor system according to the flr~t embodiment is suitable for heating reactors with an average or higher thermal power output particularly in the range of S0 to 200 MW. Even in this embodiment of ~ha heating reactor system the lnternally controllable current pa~h of the vortex chamber valve formed between the control connection and the outlet connection iæ
advisably inserted in the inilux pipe of the afterheat removal cooler.
In this embodiment of the heating reactor system two advantageous possibilities present themselves ~or controlling the vortex chamber valve. One embodiment provide~ that an adiustable throttle is inserted in the return pipe of an external heat supply network, the delivery side of this throttle belng connected to a control pipe leading to the control connection of the vortsx chamber valve, and that the reflux pipe of the afterheat removal cooler is connected to a pipe branch on the side of the throttle facing away from the delivery side. The change over to afterheat removal operation occurs automatically in ~his case through the vor~ex chamber valve if the pump operating normally in the ~.., ~L3~67~7 "-external heat supply network is switched off.
The second ad~antageous embodiment provi~es that a control current pump lying in a control current path is connected to the reflux plpe vla a suc~ion plpe and to the control connection of the vortex chamber valve vla a pressure pipe, whereby a control pressure blocking or sharply throttling the internally controllable current path of the vor~ex ahamber valve is generated by the control current pump during normal operation of the heating reactor and whereby means are provided for ~topping the pump during shutdown of ~he heating reactor. The pump is a so-called continuous runnlng pump of low power and ls only provided to generate pressure for the control current. The means for stopping the pump during shutdown of the heatlng reactor can preferably be realized by in~errupting the power supply ~or the motor driving the control current pump if the control rods of the heating reactor are in the shutdown position (fully inserted in the reactor core).
Use o~ the afterheat removal circuit with the vortex chamber valve o~ the first embodiment within the framework of a first ~asic exemplary embodiment oi the heating xeac~or system for removing decay heat in a boiling water reactor or a pressurized water reactor which serve to generate drlving steam for a ~team turbo generator unlt also forms the ~ubject matter of the present invention. A pressure of approximately 15 bar normally prevails in the reactor pressure ves3el in a heatlng reactor, a pressure of approximately 70 bar prevails in a boiling water reactor and a pre~sure of approxlmately 150 bar prevails in a pre~surized water reactor. On accoun~ of the higher operatlng pressure in the . ~
~.i ` `:
~32~7~7 reactor pressure vessel the walls of this vessel as well as the walls of the pipiny and componen~ connected thereto which are subjected to this pressure are thlcker. This must be taken into consideration if, for the afterheat removal, one or a pIurality of heat exchangers are accommodated inside a reactor pressure vessel and the pipes on the secondary side of this heat exchanger are guided to the outside through the wall of the reactor pressure vessel and are also connected as influx pipe and reflux pipe to an afterheat removal cooler together with the associated vortex chamber valve.
If, in ~he second embodiment, a condenser is provlded for the afterheat removal circuit of a heating reactor system and if a separate small pump, a so-called continuous running pump, is inserted to generate the control pressure for ~he control current connection of the vortex chamber valve, then a further advantageou~ use results for this embodlment for removing decay heat in a boillng water reactor or a pressurized water reactor which serYe to generate driving steam for a ~eam turbo-genera~or unlt.
To further explain the sub~ect matter of the present invention and its further advantage , reference i3 made here below to Figures 1 to 9 of the drawings which illustrate several exemplary embodi~ents as well as the basic design and function of a vortex chamber valve. Shown therein in stmplified illustration are, :L32~7~7 ~- 8 - 20365-2994 igure 1: a three-line heating reactor system in sim-plified illustration, whereby each of the three lines in the intermediate circuit can be automatically connected to an afterheat removal cooler via a vortex chamber valve in the event of emergency cooling (first exem~
plary embodiment);
igure 2: detail of a single line for the intermediate circuit and the afterheat removal branch con-nected thereto with vortex chamber valve and afterheat removal cooler, whereby the heavy black lines denote the path o~ the secondary coolant during normal operation and whereby the reactor pressure vessel is illustrated somewhat differently than in Figure l;
igure 3: the subject matter of Figure 2 during after-heat removal operation, whereby the vortex chamber valve is connected through and in this case al80 the heavy black line~ denote the path of the secondary coolant;
igure 4: a perspective-schematic view of a vortex chamber valve with three connection pieces for the control, supply and outlet pipe;
igure 5: flow diagxam for the vortex chamber valve according to Figure 4;
igure 6: a common connection diagram for the vortex chamber valve according to Figure 4;
7~7 - 9 203~5-29 Figure 7: a second exemplary embodiment for a heating reactor system according to the inv~ntion, whereby the intermediate circuit is illus-trated with three lines, but for reasons of simplification the afterheat removal branch is illustrated with only one l;ne a3 in Fig-ure 2 and Figure 3;
Figure 8: a third exemplary embodiment for a heating reactor system according to the invention which for reasons of simplification is again Illustrated with only one line and in which the second heat exchanger is located within the reactor pressure vessel, as well as a condenser to which the afterheat removal branch can be connected via a vortex valve in the event of emergency cooling;
:~ Figure 9: a variant of the exemplary embodiment accord- ~ :
ing to Figure 8 in section, whereby a control : current path w~th a separate control current pump is provided to generate the control cur-:
rent pressure for .the vortex chamber valve.
The heating reactor ~ystem according to Figure 1 ~how3 an atomic heating reactor, identified as a whole by HR, comprising a reactor pressur2 vQssel 1, a reactor core 2 and a primary cool-ant in the form o light water circulated therein in natural cir-culation, the volume 3 of this water surrounding the reactor core 2 and it9 water level 3.0 located at a distance al from and above the upper edge ~.0 of the core. As the flow lines F1 with the 3L3~7~
- 10 - 20365-29g4 arrows fl show, the primary coolant flows in natural circulation without special circulating pumps, although the invention is not restricted to such an embodiment for natural circulation. Inter-nal or external circulating pumps can also be used to increase the amount of primary coolant circulated per unit of time. As usual, the reactor core comprises elongated fuel elements, whereby verti-cal cooling channels extending in the axial direction of the fuel elements are provided in and possibly between the fuel elements, the primary coolant flowing through these channels from bottom to top, whereby the coolant is heated and, since it is specifically lighter, flows upwards through the primary side of the first heat exchangers 4 on account of lift forces.
As illustrated, these heat exchangers 4 are preferably arranged in the volume 3 of water and, as mentioned, the primary coolant flows through and is heated on the primary side. On the ~econdary ~ide the ~econdary coolant of an intermediate circuit ZK
which is circulated by at least one pump 5, flows through these first heat exchangers 4 within the schematically illustrated heat exchanger tubes 4.1 according to the direction of arrow f2. Three first heat exchangers 4 and accordingly three lines zkl, ~k2 and zk3, connected thereto, of the intermediate circuit ZK, each with one circulating pump 5 for the secondary coolant and a second heat exchanger 6 are illustrated.
To operate the heating reactor sy~tem ~R it is necessary that at least one first heat exchanger 4 with at least one of the line~ zkl to zk3 and one of the second heat exchangers 6 as well as an as~ociated circulating pump 5 be provided. A triple arrangement is illustrated in order to demonstrate that the inter-mediate circuit ZK can have not only one, but two, three or even ~3:~7~7 ~ 203~5-29~4 more lines, depending on the size of a connected external heat supply network HN and the required quantity of heat, this also affecting the structural size of the reactor pressure vessel 1.
The second heat exchangers 6 are thus heated on the pri-mary side by the secondary coolant. Their heat exchanger tubes or pipe coils are again schematically illustrated and identified by reference numeral 6.1. A tertiary coolant of the heat supply net-work H~ flows through said heat exchangers on the secondary side.
They are connected for this purpose on the secondary side to out-put pipes 7a, 7b, 7c which are combined into ~ common output pipe 7 at the branch point 7.1 and are respectively connected on the return side to return pipes 8a, 8b, 8c of a heat supply network distributed from the common or main return pipe 8 to the individu-al second heat exchangers 6. The individual lines zkl to zk3 of the intermediate circuit ZK are each provided with a hot secondary coolant line 9.1 and a cold secondary coolant line 9.2. The hot line 9.1 connects the secondary side (or the outlet) of the heat exchanger tubes 4.1 of the ~irst heat exchangers 4 to the influx side or the inlets of the heat exchanger tubes 6.1 of the second heat exchangers 6. The cold secondary coolant line 9.2 in each case extends from the outlet of tha heat exchanger tubes 6~1 of the second heat exchanger 6 through the circulating pump S up to the inlet of the heat exchanger tubes 4.1 of the first heat ex-changer 4.
Afterheat removal coolers lOa, lOb~ lOc with their in-flux pipes 11 and reflux pipes 12 are respectively connected to the intermediate circuit llnes kl, ~k2 and zk3 of the intermedi-ate circuit ZK, whereby the aforenamed coolers lOa, lOb, lOc are ~32~717 identified as a whole by the afterheat removal cooler 10. The coolers 10 or lOa, lOb, lOc are preferably designed as air coolers, as is schematically illustrated. The influx pipe 11 of said cooler is in each case connected to the hot lina 9.1 via the internally controllable current path sO-eO of a vortex chamber valve WV whose hydraulic connection cO for the control cuxrent is connected via the control current pipe 13 to the cold secondary coolant line 9.2 ("cold line") on the delivery side of the pump 5 of the intermediate c~rcuit ZK. The xeflux pipe 12 of the cooler 10 is in each case connected to the cold line 9.2 of the interme-diate circuit lines zkl, zk~, zk3 on the delivery side of the pump 5. The operation of the vortex chamber valve WV will be explained in greater detail herebelow on the basis of Figures 2 and 3. If the heating reactor HR i5 shut down or its power reduced (absorber rods or control rods, not illustrated, are inserted into the reac-tor core 2 for this purpose), then it i8 the task of tha cooler 10 to remove the so-called decay heat of the heating reactor HR. It is thereby assumed that no more heat i5 required by the external heat supply network H~ and that the pumps 5 are no longer running.
This can be the case if the heating reactor ~R, whose fuel ale-ments are rearranged or replaced, is inspected if the heating reactor HR is shut down through a breakdown or if, for example, alteration, in~pection or repair worX is carried out in the exter~
nal heat supply network HN.
The reactor pressure vessel 1 is surrounded by a reactor containment shell 130, as is schematically indicated by the dash line. In case the reactor pressure vessel 1 leaks, the leakage water is collected in the contain~ent shell 130, whereby such a ~3~6717 large volume of water is selec~ed that the reactor core 2 is still covered if the liquid level in the vessels 1 and 130 is the same.
The steam plenum 14 is located above the water level 3. The dash-dot exterior line 15 indica~es which components and pipelines of the illustrated heating reactor system are surrounded by a con-crete casing of the reactor building or are accommodated under-ground in concrete buildings, whereby these concrete buildings are covered on the outside by heavy concrete casings and are also pro-tected against airplane crashes.
The present invention deals in particular with a heating reactor system with a thermal power output in the range of approx-imately 5 to 200 MW. All sub-systems must be designed as simply as possible in such a heating reactor system.
For the sake of clarity, the heating reactor system in Figure 2 is illustrated with only a one line intermediate circuit ZK. It is understood that two, three ox more lines ~kl, zk2, etc.
(as in Figure 1) could be provided. In Figure 2 and also the fol-lowing Figures the parts with the same ~unction as those in Figure 1 are identified by the same reference numerals.
In addition to the illu3tration in Figure 1, reference numeral~ rela ing to the cold line 9.2 were added in Figures 2 and 3 for a pipe section 9.21 between the second heat exchanger 6 and the pump 5, for a pipe section 9.22 between the pump 5 and a branch point 16 and for a pipe section 9~23 between the branch point 16 and the first heat exchanger 4. It can already be seen from Figure 1 that there are no conventional valves for the change-over to emergency cooling operation. Figure 2 shows in greater detail that the respective flow rate regulating units for ~3~6717 - 14 20365-29g4 the after heat removal branch 10, 11, 12 are designed as a vortex chamber valve WV comprising a hydraulic connection sO for the supply current sl, a connection cO or the control current cl and a connection eO for the outlet current el. The internally con-trollable current path sO-eO is thereby connected at the branch point 17 to the hot line 9.1 of the intermediate circuit ZK via the associated pipe section 11.1 of th~ influx pipe 11 of the cooler 10 and the hydraulic connection cO for the control current cl is connected at the branch point 18 to the delivery side of the pump 5 of the intermediate circuit.
A single such vortex chamber valve WV is schematically illustrated in Figures ~ to 6 for better understanding. Its hy-draulic connections sO, cO and eO and the fluid currents, namely the supply current sl~ control current cl and outlet current el, are identified exactly the same as in Figure 2. The radial vor-tex chamber valve WV illustrated by way of example in Figure 4 (there are also axial and conical vortex valves) consists of a flat, hollow cylindrical vortex chamber housing 19 containing a vortex chamber 19', a connection piece for the supply current sl or suppl~ connection sO 10wing radially into the vortex chamber 19i, a connec~on piece for the control current cl or control con-connection cO flowing tangentially into the vortex chamber 19' and a connection piece for the outlet currentel or an outlet connection eO arranged axially with respect to the rotational axis of the housingl9 or the vortex chamber 19', As illustrated, the outlet connection eO can be designed like a nozzle or Venturi tube in order to keep the pressure drop as small as possible. The supply current sl, illustrated by dash lines, ~26717 which is fed through the radially arranged supply connectlon sO, leaves the vortex chamber 19' through the axial outlet connection eO, whereby it is first of all assumed that no control current cl is flowing yet. The throttle effect of this vortex chamber valve WV is then relatively low and sl = el. If a control current cl, whose control pressure is about 5 to 10% higher -than the pressure of the supply current sl, is sent through the tangential control connection cO, then an increasingly intensive twisting flow is produced in the vortex chamber 19' as the quantity of control cur-rent increases. Its centrifugal force causes the build-up of a counterpressure in the vortex chamber 19' which can reduce and thus control the influx of supply current sl (or increase it again with decreasing control current cl). A relatively low maximum control current throughput of approximately 10 to 20% of the maxi-mum throughput of the supply current sl is enough to bring the supply current sl to a standstill. The control current cl flows from the tangential control connection cO in spirals to the axial outlet connection eO and this spiral flow continues in its connec-tion piece. The outlet current el can contain both the control current cl as well as the supply current sl. If, however, the throughpu~ of the control current cl reaches the designated maxi-mum of approximate]y 10 to 20% of the supply current sl, then the latter comes to a standstill. The outlet current el then only contains the control current cl so that then approximately 20% of the throughput of the to a large extent blocked supply current sl flow3.
Figure 4 shows the general view, Figure 5 æhows a simp]ified flow diagram and Figure 6 shows the circuit symbol ~ 3L32~7~7 obtained therefrom of the vortex chamber valve WV which can also be simply identified as a vortex valve.
Coming back to Figure 2: It illustrates th0 "normal operation" in which the secondary coolant of the intermediate cir-cuit ZK is circulated by the pump 5 - see arrow f2. The control connection cO (tangential control current cl) of the associated vortex chamber valve WV is connected to the delivery side of the pump 5 via pipe 13 and with its supply connection sO is connected at the branch point to the hot line 9.1 of the intermediate cir-cuit ZK via the pipe 11.1. If the pump 5 is running, then the supply current sl is almost stopped by the control current cl, i.e. flow via the cooler 10 is prevented. The low control current cl flows via the outlet connection eO as outlet current el and via the pipe 11.2 to the cooler 10, is cooled in the cooler 10 and then flows back to the branch point 16 via the reflux pipe ~ F
where it mlxes with the secondary coolant in the cold line 9.2 of the intermediate circuit ZK. Since almost no supply current sl flows during the operating condition illustrated in Figure 2, ~he correQponding reference numeral i8 placed in brackets and the a~-sociated arrow is illustrated by dash lines. Furthermore, due to the low throughput the outlet current el i8 only illustrated by dash lines.
Figure 3 shows the operatin~ condition "afterheat remov-al". Pump 5 is thereby switched off. The vortex chamber valve WV
has lost its blocking function since the control current cl (there is only natural circulation) is brought to a standstill on account of the pressure ratios. As is made clear by the arrow~ sl-el-f3, the ~econdary coolant of the intexmediate circuit ~K circulates 132~i7~l7 - 17 ~ 20365-2994 via the cooler 10. No or almost no control current cl is flowing any longerO Reference numeral cl is therefore placed in brackets and the associated arrow is illustrated by dash lines. However, the supply current sl, whose throughput is equal to that of the outlet current el, is flowing. Since the pump 5 is stopped, the flow stagnates at the primary side of the second heat exchanger 6 and in the pipe section 9.21 and the transfer pump (not illustrat-ed) provided for the heat supply network HN is also no longer working.
The heating reartor system according to Figure 7 corre-sponds in principle to that according to Figures 1 to 3. Added to this embodiment are two isolating valves 20a, 20b connected di-rectly in front of and after the pump 51 pressure vessels 21 re-spectively connected to the cold lines 9.2 of the intermediate circuit ZK, a non-return flap 107 in the branch 9.21, and in the six lines zkl to zk6 illustrated of the intermediate circuit ZK
motor-actuated control flaps or spool valves 105 provided in the hot line 9.1 and control flaps or spool valves 106 provided in the cold line 9.2. The non-return flap 107 allows a primary-side flow through the second heat exchanger 6 only in direction f2. The isol~ting valves 20a, 20b are used to separate the pump 5 from the remainins network during maintenance or repair work. The first heat exchangers 4 are modified ~omewhat in comparison to those in Figures 1 to 3. Their heat exchanger tubes 4.1 are divided into two partial tube bundles or pipe coils 4.11 and 4.12 connected parallel to one another. In addition, it can be seen that the pipes for the hot line 9.1 and the cold line 9.2 of the intermedi-ate circuit ZK leaving the first heat exchangers 4 are guided to ~32~7~7 - 18 - 20365-2~94 the outside through the casing wall 103 of the reactor pressure vessel 1 below its closure head flange connection 101, 102.
Flange 101 is part of the vessel base portion 1.1 and flange 102 is part of the closure 1.2.
The exemplary embodiments according to Figures 1 to 7 are based on a circuit arrangement wherein the afterheat removal branch 11, 10, 12 is connected to the hot or cold line 9.1, 9.2 on the secondary side of the first heat exchanger 4~ I~ the heat ex-changers 4 are arr~nged within the reactor pressure vessel 1 at a sufficiently large distance from the reactor core 2, then activa-tion of the secondary coolant is relatively low and having the secondary coolant act on the afterheat removal branch is justi-fied. In principle, it is also possible, however, to provide separate condensers in the steam plenum 14 of the reactor pressure vessel 1 for afterheat removalO
The heating reactor system illustrated in Figure 8 is preferably suitable for a thermal power output in the range of 5 to 50 MW. The reactor building is again identified by reference numeral 15 and it is illustrated somewhat more clearly that it consists of concrete walls. It is arranged underground in a cor-responding chamber 22 in the ground 23. The afterheat removal branch with its influx pipe 11, the cooler 10 and the reflux pipe 12 is connected to the hot line 25.1 of a condenser 24 via the vortex chamber valve WV, namely its controllable current path (sO-eO) between the supply connection sO and the outlet connection eO, and to the cold line 25.2 of the condenser 24 at the connec-tion point 26 of the reflux pipe 12. The condenser 24 is arranged in the steam plenum 14 of the reactor pressure vessel 1. The path of the steam rising in the volu~e of water 3 is schematically il-lustrated by the flow path F2 and the direction arrows f4. The steam flows through the primary side of the condenser 24~and, if the condenser 24 is cooled on the secondary side, releases its vaporization heat via the heat exchanger tubes 24.1 to the ter-tiary medium flowing therein, whereby the steam condenses and flows back into the volume o4 water 3 in accordance with flow arrows f5.
The second heat exchanger 6 - in this exemplary embodi-ment of a so called integral design - is also arranged in the steam plenum 14, i.e. also within the space enclosed by the reac-tor pressure vessel 1. For this reason the output pipe 7 and the return pipe 8 of the heat supply network HN penetrate the wall of the reactor pressure vessel 1, namely preferably the casing wall lU3, and are connected to the outlet end or the inlet end of the heat exchanger tubes 6.1 of the second heat exchanger 6. On their way to or from the second heat exchanger 6 the output and return pipe~ also penetrate the wall of the reactor containment shell 130 and the wall of the reactor building 15. The individual penetra-tion po1nts, seen from the outside in, are identified by reference numerals 7a, 7b and 7c for the output pipe 7 and by reference numerals 8a, 8b and 8c for the return pipe 8. The penetration point 7c, 8c of the output and return pipes 7, 8 are arranged below the pressure-sealed closure head flange connection 101, 102.
The secondary side of the first heat exchanger 4, i.e. the inlet and outlet endR of its heat exchanger tube~ 4.1, is connected to the primary side of the second ~integral) heat exchanger 6 via the hot and the cold secondary coolant line 9~1 or 9.2. For this ~ ~32~7~7 - 20 - ~0365-2994 reason the secondary coolant flows around the outside of the heat exchanger tubes 6.1 of the second heat exchanger 6, the tertiary medium of the heat supply network ~N flowing throu~h these tubes 6.1 during normal operation.
A motor-driven, remote-controllable valve 27 or 28 is inserted in each of the two pipes 7 and 8 (output and return pipe) within the reactor building 15 and preferably outside the contain-ment vessel 130. These valves 27, 28 can also be isolatin~ valves since they can completely separate the secondary side of the second heat exchanger 6 from the heat supply network if they are in the closed position. An adjustable throttle 29 connected in series to the valve 28 and preceding it is located in the return pipe 8, this throttle generating, on account of the pressure drop formed at it, a control pressure for the control current cl during normal heating operation. The control current comprises a partial current of the liquid heating medium branched o~f in front of the throttle 2g, this heating medium being fed to the control connec-tion cO of the vortex chamber valve WV via the control pipe 30 connected at the input side of the throttle 29.
The illustration in Yigure 8, just as the illustrations in Figures 1 to 7, is schematic, i.e. supports and holders ~or the containment ve~sel 130, the reactor pressure vessel 1, the first and second heat exchangers ~ and 6, the condenser 24, the valves 27l 28 and the throttle 29 as well as for the reactor core 2 are ~ot illustrated. The volume in the space 108 between the reactor pressure vessel 1 and the reactor containment vessel 130 on the one hand and the volume of water 3 on the other hand are determined in such i326717 a way that in the event of a leak in the wall of the reactor pres-sure vessel 1 the liquid level for the (now reduced) volume of water 3 will adjust to the volume of water in the space 108 such that the reactor core 2 at any rate remains covered with primary coolant.
The reflux pipe 12 ends via a pipe branch 12.1 at the connection point 31 between the valve 28 and the throttle 29.
During normal operation, i.e. when the heating medium in the heat supply network, not illustrated in greater detail, flows in accor-dance with the arrows f6 ~output) and f7 (return), the throttle 29 throttles down to such an extent that the dynamic pressure at its input side acts as control pre~gure on the control connection cO
of the vortex chamber valve WV, namely ~uch that the controllable current path sO-eO is to a large extent blocked so that no appre-ciable supply current sl can be built up via the hot line 25.1 of the conden~er 24. A first portion of the heating medium thus flows directly to the second heat exchanger 6 via the throttle 29 and the valve 28 and a second ~smaller, during normal operation) portion flows via the control pipe 30 and the control connection-outlet connection section cO-eO of the vortex chamber valve WV as well as via the influx pipe 11 into the cooler 10 where it is cooled down somewhat urther and then flows through the reflux pipe 12 back to the connection point 31 and from there tc the second heat exchanger 6. During this operating condition the con-denqer ~4 contributes almost nothing or nothing appreciable to the steam cooling since the supply current sl which can flow via the section sO-eO of the vortex chamber valve WV is very small. The arrows sOl in dash lines identify thi~ low power flow which is fed ~32~717 - 22 - 2~365-29 and maintained by the heating medium (tertiary medium).
If the two isolating valves 27, 28 are closed in the course of inspection or repair work and/or if a fuel element i5 replaced and if the external pumps (not illustrated) conveying the heating medium are thereby accordingly also switched off, then the control pressure in the control pipe 30 drops to such an extent that the throttle effect of the control current cl stops. The section sO-eO of the vortex chamber valve WV is unblocked since its flow resistance is reduced considerably, resulting in a closed cooling circuit which i5 in addition induced by the forced heating of the medium in the heat exchanger tubes 24.1 of the con-denser 24, namely because the first and second heat exchangers 4 and 6 can no longer contribute to the removal of heat. The con-trol rods are inserted into the reactor core 2 during this after-heat removal op~ration and the condenser 24 is thus used to remove the decay heat. The tertiary medium flows via the hot line 2S.l, the ~ection sO-eO of the vortex chamber valve WV and the influx pipe 11 to ~he cooler 10, is cooled ~here (the cooler can be an air cooler or a water cooler) and, cooled of~, flows back to the heat exchanger tubes 24.1 of the conden~er 24 via the reflux pipe 12, the connection point 26 and the cold line 25.2. As can be seen, the removal of decay heat in the exemplary embodiment ac cording to Figure 8 can be induced without having to open addi~
tional valves in the afterheat removal branch 10, 11, 12. The vortex chambPr valve WV takes over the automatic change-over if the control pres~ure alls below a minimum value at its control connection cO and switche~ back to normal operation if the control pressure exceeds a miniumum value at the control connection cO.
~32~717 A variant of the heating reactor system according to Figure 8 is illustrated in Figure 9. The control pressure for the control connection cO of the vortex chamber valve WV is thereby generated not by throttling the flow in the return pipe 8 of the heat supply network, but by a control current pump 40 inserted in a control current path 41, 42, this control current pump being connected at connection point 26 to the reflux pipe 12 via a suc-tion pipe 41 and to the control connection cO of the vortex cham-ber valve ~ via a pressure pipe 42. During normal heating opera-tion of the illustrated heating reactor HR the control current pump 40 operates as a continuous running pump. The throughput pumped by it is relatively small so that a small control current pump is sufficient. During normal operation of the heating reac-tor HR a control pressure blocking or sharply throttling the in-ternally controllable current path sO-eO of the vortex chamber valve WV is generated by the control current pump 40. If the heating reactor HR is shut down - this occurs when the control rods, not illustrated, are fully inserted into the core of the heating reactor HR - then the control current pump 4n is al~o switched of. The means for stopping the control current pump 40 advantageou~ly depend for control on the command for insertion of the control rods (not illustrated). For example, an electrical command which, for example, cuts the power supply for the driYe motor of the control current pump 40 via a relay or an electronic switch can be derived from the electrical or hydraulic command for the complete insertion of ~he control rods and thus for the shutdown oE the heating reactor. On the other hand, when the heating reactor HR is restarted the relay or electronic switch is 3L~2671~
- 24 - 20365-29g4 controlled in such a way tha~ the motor is switched on again and the pump 40 begins to run. With the control current pump 40 switched o~f, the controllable current path sO-eO of the vortex chamber valve WV is opened for an unthrottled flow so that, as was already explained on the basis of Figure 8, natural circulation flow develops via the hot line 25.1 of the condenser 24, the open current path sO-eO, the influx pipe 11, the cooler lO, the reflux pipe 12 and the cold line 25.2 of the condenser 24 back to the heat exchanger tubes 24.1 of this condenser, the decay heat re-sulting in the heating reactor HR being removed by this natural circulation ~low. The heating reactor system according to Figure 9 corresponds otherwise to Figure 8. For this reason only one section is illustrated.
The afterheat removal circuit according to Figure 9 with its control current pump 40, the vortex chamber valve WV, the afterheat removal branch ll, 10, 12 and the connected condenser 24 can be advantageously used to remove the decay heat in a boiling water reactor or also in a pre~suri~ed water reactor, i.e. in those light-water reactors which serve to generate driving steam ~or a steam turbo-generator unit. Such a turbo-generator unit comprises a steam turbine on which the driving steam acts and a turbo-generator coupled to the steam turbine for generating elec-trical energy. In this case, one or a plurality of condensers are arranged within the stea~ plenum of the reactor, whereby the pipes for the hot and cold lines 25.1, 2S.2 connected to their heat ex-changer tubes 24.1 are guided to the outside through the wall o the reactor in corresponding pressure-3ealed penetrations.
It will be explained herebelow on the basis of Figure l that the afterheat removal circuit illustrated in Figures 1 to 7 is also suitable for removing the decay heat in a boiling water reactor or a pressurized water reactor. For the explanation, ref-erence is made herebelow only to the two lines zkl of the inter-mediate circuit ZK. It is understood, however, that more than one pair of lines zkl can be used for afterheat removal~
According to the exemplary embodiment, the second heat exchanger 6 on the secondary side of the first heat exchanger 4 is replaced by a pipe section 50, illustrated by dash lines, connect-ing the two secondary coolant lines 9.1, 9.2. As a result the secondary coolant is circulated by the pump 5 during normal opera-tion of the reactor (not illustrated) to generate the control pressure for the control connection cO of the vortex chamber valve WV. This pump 5, just as the control current pump 40, then oper-ates as a continuous running pump to genexate the control pres-sure. Since an external heat supply network HN is not connected in this case, the pipes for the hot and cold line 9.1~ 9.2 can be hortened. Ths controllable current pa~h sO-eO of the vortex valve WV is blocked or sharply throttled, as was already e~plained several times. A control command for ~witching off the drive motor of the pump S is only given when the control rods in the boiling water or pressurized water reastor are moved into the com~
pletely shutdown position and the controllable current path of the vortex chamber valve WV is thus opened; afterheat removal opera-tion in the natural circulation flow begins immediately. The secondary coolant heated in the heat exchanger tubes 4.1 of the ~irst heat exchanger 4 flows via the hot line, the pipe section 11.1, the current path sO-eO of the vortex chamber valve WV, the ~326717 - 26 - 20365-~,9g4 influx pipe 11, the cooler lOa and the reflux pipe 12 back to the cold line 9.2 and rom there to the heat exchanger 4, whereby the secondary coolant is continuously cooled in the cooler lOa and the decay heat is thus removed. In this exemplary embodiment the first,heat exchanger 4, disposed in the volume of water 3 of the boiling water or pressurized water reactor, is utilized a~ a heat sink for the removal of decay heat. The two pipes 9.1 and 9.2 for its hot and cold line ~ust again be guided pressure-sealed to the outside through the wall of the reactor pressure vessel. These pipe penetrations can be provided in the cover or the casins wall of the reactor pressure vessel, not illustrated.
In acordance with the second embodiment for using the afterheat removal circuit with a vortex chamber valve for boiling water or pressurized water reactors, the pump 5 i~ dispensed with in accordance with the exemplary embodiment according to Figure 9.
It is sufficient if the intermediate circuit lines zkl under con-sideration extend only up to the points 61, 62 indicated by the da~h lines. Instead of the pump 5 in the cold line 9.2, a control current pump 60 is disposed in this embodiment in the control cur-rent path 13. Thi~ pump 60 is lik~wise only illustrated by dash lines ~ince it is a variant within the framework of the use. The control current pump 60 is connected to ~he reflux pipe 12 via a suction pipe section 13.1 of the control current path 13 (or to the pipe section of the hot line 9.2 connected to it) and to the control connection cO of the vortex chamber valve WV via a pres-sure pipe section 13.2 of the control current path 13. As was already explained on the basis of ~'igure 9, a control pre~sure blocking or sharply throttling the internally controllable current ~326717 , ,~
- 27 - 20365-29g4 path sO-eO of the vortex chamber valve WV is generated by the con-trol current pump 60 during normal operation of the reactor (not illustrated). As well, means (not illustrated) which were already explained in greater detail on the basis of Figure 9 are again provided for stopping the control current pump 60 during shutdown of the reactor. The advantage of this embodiment lies therein that the throughput of the control current pump 60 amounts to ap-proximately only 10 to 20% of the throughput which the pump 5 must circulate. The control current pump can therefore be a relatively small pump.
The arrangement for the reactor pressure vessel of the heating reactor sys~em and the first and second heat exchangers can be even more compac~ in tha~ the second heat exchanyer is also arranged integrally within the space enclosed by the reactor pressure vessel, preferably within the steam plenum. In this case an output pipe as well as a return pipe, which are connected to the heat exchanger tubes of the second heat exchanger, are advisably guided to the outside through the wall of the reactor pressure vessel and are connected to an external hea~ supply network. To keep the cover of the reactor pressure vessel free, it is al30 advisable that the outlet pipe and the return pipe penetrate the caslng wall of the reactor pressure vessel below the closure head flange Accordiny to another broad aspect of the present invention there ls provlded a heating reactor system, particularly for llght-water reactors, comprising a first heat exchanger and a second heat exchanger connec~ed to one another vla an intermediate circult for the secondary coolant and with the additional features of an afterheat removal circuit which contains an afterheat removal cooler and which i5 connected to the secondary side of a heat exchanger arranged in the reactor pressure vessel via cooler connec~ion pipes ln the form of an influx pipe and a reflux pipe, ~3~
hereby a vortex chamber valve is inserted in he cooler connection pipes as a flow rate regulating unit and whereby the heat exchanger is a condenser arranged in the steam plenum o~ the reactor pressure vessel.
This heating reactox system also solves ~he object on which the present invention is based and which was explained at the beginning. Such a heating reactor system is preferred for smaller heating reactors with a thermal reactor output in a range betwean approximately 5 and 50 MW, whereas the heating reactor system according to the flr~t embodiment is suitable for heating reactors with an average or higher thermal power output particularly in the range of S0 to 200 MW. Even in this embodiment of ~ha heating reactor system the lnternally controllable current pa~h of the vortex chamber valve formed between the control connection and the outlet connection iæ
advisably inserted in the inilux pipe of the afterheat removal cooler.
In this embodiment of the heating reactor system two advantageous possibilities present themselves ~or controlling the vortex chamber valve. One embodiment provide~ that an adiustable throttle is inserted in the return pipe of an external heat supply network, the delivery side of this throttle belng connected to a control pipe leading to the control connection of the vortsx chamber valve, and that the reflux pipe of the afterheat removal cooler is connected to a pipe branch on the side of the throttle facing away from the delivery side. The change over to afterheat removal operation occurs automatically in ~his case through the vor~ex chamber valve if the pump operating normally in the ~.., ~L3~67~7 "-external heat supply network is switched off.
The second ad~antageous embodiment provi~es that a control current pump lying in a control current path is connected to the reflux plpe vla a suc~ion plpe and to the control connection of the vortex chamber valve vla a pressure pipe, whereby a control pressure blocking or sharply throttling the internally controllable current path of the vor~ex ahamber valve is generated by the control current pump during normal operation of the heating reactor and whereby means are provided for ~topping the pump during shutdown of ~he heating reactor. The pump is a so-called continuous runnlng pump of low power and ls only provided to generate pressure for the control current. The means for stopping the pump during shutdown of the heatlng reactor can preferably be realized by in~errupting the power supply ~or the motor driving the control current pump if the control rods of the heating reactor are in the shutdown position (fully inserted in the reactor core).
Use o~ the afterheat removal circuit with the vortex chamber valve o~ the first embodiment within the framework of a first ~asic exemplary embodiment oi the heating xeac~or system for removing decay heat in a boiling water reactor or a pressurized water reactor which serve to generate drlving steam for a ~team turbo generator unlt also forms the ~ubject matter of the present invention. A pressure of approximately 15 bar normally prevails in the reactor pressure ves3el in a heatlng reactor, a pressure of approximately 70 bar prevails in a boiling water reactor and a pre~sure of approxlmately 150 bar prevails in a pre~surized water reactor. On accoun~ of the higher operatlng pressure in the . ~
~.i ` `:
~32~7~7 reactor pressure vessel the walls of this vessel as well as the walls of the pipiny and componen~ connected thereto which are subjected to this pressure are thlcker. This must be taken into consideration if, for the afterheat removal, one or a pIurality of heat exchangers are accommodated inside a reactor pressure vessel and the pipes on the secondary side of this heat exchanger are guided to the outside through the wall of the reactor pressure vessel and are also connected as influx pipe and reflux pipe to an afterheat removal cooler together with the associated vortex chamber valve.
If, in ~he second embodiment, a condenser is provlded for the afterheat removal circuit of a heating reactor system and if a separate small pump, a so-called continuous running pump, is inserted to generate the control pressure for ~he control current connection of the vortex chamber valve, then a further advantageou~ use results for this embodlment for removing decay heat in a boillng water reactor or a pressurized water reactor which serYe to generate driving steam for a ~eam turbo-genera~or unlt.
To further explain the sub~ect matter of the present invention and its further advantage , reference i3 made here below to Figures 1 to 9 of the drawings which illustrate several exemplary embodi~ents as well as the basic design and function of a vortex chamber valve. Shown therein in stmplified illustration are, :L32~7~7 ~- 8 - 20365-2994 igure 1: a three-line heating reactor system in sim-plified illustration, whereby each of the three lines in the intermediate circuit can be automatically connected to an afterheat removal cooler via a vortex chamber valve in the event of emergency cooling (first exem~
plary embodiment);
igure 2: detail of a single line for the intermediate circuit and the afterheat removal branch con-nected thereto with vortex chamber valve and afterheat removal cooler, whereby the heavy black lines denote the path o~ the secondary coolant during normal operation and whereby the reactor pressure vessel is illustrated somewhat differently than in Figure l;
igure 3: the subject matter of Figure 2 during after-heat removal operation, whereby the vortex chamber valve is connected through and in this case al80 the heavy black line~ denote the path of the secondary coolant;
igure 4: a perspective-schematic view of a vortex chamber valve with three connection pieces for the control, supply and outlet pipe;
igure 5: flow diagxam for the vortex chamber valve according to Figure 4;
igure 6: a common connection diagram for the vortex chamber valve according to Figure 4;
7~7 - 9 203~5-29 Figure 7: a second exemplary embodiment for a heating reactor system according to the inv~ntion, whereby the intermediate circuit is illus-trated with three lines, but for reasons of simplification the afterheat removal branch is illustrated with only one l;ne a3 in Fig-ure 2 and Figure 3;
Figure 8: a third exemplary embodiment for a heating reactor system according to the invention which for reasons of simplification is again Illustrated with only one line and in which the second heat exchanger is located within the reactor pressure vessel, as well as a condenser to which the afterheat removal branch can be connected via a vortex valve in the event of emergency cooling;
:~ Figure 9: a variant of the exemplary embodiment accord- ~ :
ing to Figure 8 in section, whereby a control : current path w~th a separate control current pump is provided to generate the control cur-:
rent pressure for .the vortex chamber valve.
The heating reactor ~ystem according to Figure 1 ~how3 an atomic heating reactor, identified as a whole by HR, comprising a reactor pressur2 vQssel 1, a reactor core 2 and a primary cool-ant in the form o light water circulated therein in natural cir-culation, the volume 3 of this water surrounding the reactor core 2 and it9 water level 3.0 located at a distance al from and above the upper edge ~.0 of the core. As the flow lines F1 with the 3L3~7~
- 10 - 20365-29g4 arrows fl show, the primary coolant flows in natural circulation without special circulating pumps, although the invention is not restricted to such an embodiment for natural circulation. Inter-nal or external circulating pumps can also be used to increase the amount of primary coolant circulated per unit of time. As usual, the reactor core comprises elongated fuel elements, whereby verti-cal cooling channels extending in the axial direction of the fuel elements are provided in and possibly between the fuel elements, the primary coolant flowing through these channels from bottom to top, whereby the coolant is heated and, since it is specifically lighter, flows upwards through the primary side of the first heat exchangers 4 on account of lift forces.
As illustrated, these heat exchangers 4 are preferably arranged in the volume 3 of water and, as mentioned, the primary coolant flows through and is heated on the primary side. On the ~econdary ~ide the ~econdary coolant of an intermediate circuit ZK
which is circulated by at least one pump 5, flows through these first heat exchangers 4 within the schematically illustrated heat exchanger tubes 4.1 according to the direction of arrow f2. Three first heat exchangers 4 and accordingly three lines zkl, ~k2 and zk3, connected thereto, of the intermediate circuit ZK, each with one circulating pump 5 for the secondary coolant and a second heat exchanger 6 are illustrated.
To operate the heating reactor sy~tem ~R it is necessary that at least one first heat exchanger 4 with at least one of the line~ zkl to zk3 and one of the second heat exchangers 6 as well as an as~ociated circulating pump 5 be provided. A triple arrangement is illustrated in order to demonstrate that the inter-mediate circuit ZK can have not only one, but two, three or even ~3:~7~7 ~ 203~5-29~4 more lines, depending on the size of a connected external heat supply network HN and the required quantity of heat, this also affecting the structural size of the reactor pressure vessel 1.
The second heat exchangers 6 are thus heated on the pri-mary side by the secondary coolant. Their heat exchanger tubes or pipe coils are again schematically illustrated and identified by reference numeral 6.1. A tertiary coolant of the heat supply net-work H~ flows through said heat exchangers on the secondary side.
They are connected for this purpose on the secondary side to out-put pipes 7a, 7b, 7c which are combined into ~ common output pipe 7 at the branch point 7.1 and are respectively connected on the return side to return pipes 8a, 8b, 8c of a heat supply network distributed from the common or main return pipe 8 to the individu-al second heat exchangers 6. The individual lines zkl to zk3 of the intermediate circuit ZK are each provided with a hot secondary coolant line 9.1 and a cold secondary coolant line 9.2. The hot line 9.1 connects the secondary side (or the outlet) of the heat exchanger tubes 4.1 of the ~irst heat exchangers 4 to the influx side or the inlets of the heat exchanger tubes 6.1 of the second heat exchangers 6. The cold secondary coolant line 9.2 in each case extends from the outlet of tha heat exchanger tubes 6~1 of the second heat exchanger 6 through the circulating pump S up to the inlet of the heat exchanger tubes 4.1 of the first heat ex-changer 4.
Afterheat removal coolers lOa, lOb~ lOc with their in-flux pipes 11 and reflux pipes 12 are respectively connected to the intermediate circuit llnes kl, ~k2 and zk3 of the intermedi-ate circuit ZK, whereby the aforenamed coolers lOa, lOb, lOc are ~32~717 identified as a whole by the afterheat removal cooler 10. The coolers 10 or lOa, lOb, lOc are preferably designed as air coolers, as is schematically illustrated. The influx pipe 11 of said cooler is in each case connected to the hot lina 9.1 via the internally controllable current path sO-eO of a vortex chamber valve WV whose hydraulic connection cO for the control cuxrent is connected via the control current pipe 13 to the cold secondary coolant line 9.2 ("cold line") on the delivery side of the pump 5 of the intermediate c~rcuit ZK. The xeflux pipe 12 of the cooler 10 is in each case connected to the cold line 9.2 of the interme-diate circuit lines zkl, zk~, zk3 on the delivery side of the pump 5. The operation of the vortex chamber valve WV will be explained in greater detail herebelow on the basis of Figures 2 and 3. If the heating reactor HR i5 shut down or its power reduced (absorber rods or control rods, not illustrated, are inserted into the reac-tor core 2 for this purpose), then it i8 the task of tha cooler 10 to remove the so-called decay heat of the heating reactor HR. It is thereby assumed that no more heat i5 required by the external heat supply network H~ and that the pumps 5 are no longer running.
This can be the case if the heating reactor ~R, whose fuel ale-ments are rearranged or replaced, is inspected if the heating reactor HR is shut down through a breakdown or if, for example, alteration, in~pection or repair worX is carried out in the exter~
nal heat supply network HN.
The reactor pressure vessel 1 is surrounded by a reactor containment shell 130, as is schematically indicated by the dash line. In case the reactor pressure vessel 1 leaks, the leakage water is collected in the contain~ent shell 130, whereby such a ~3~6717 large volume of water is selec~ed that the reactor core 2 is still covered if the liquid level in the vessels 1 and 130 is the same.
The steam plenum 14 is located above the water level 3. The dash-dot exterior line 15 indica~es which components and pipelines of the illustrated heating reactor system are surrounded by a con-crete casing of the reactor building or are accommodated under-ground in concrete buildings, whereby these concrete buildings are covered on the outside by heavy concrete casings and are also pro-tected against airplane crashes.
The present invention deals in particular with a heating reactor system with a thermal power output in the range of approx-imately 5 to 200 MW. All sub-systems must be designed as simply as possible in such a heating reactor system.
For the sake of clarity, the heating reactor system in Figure 2 is illustrated with only a one line intermediate circuit ZK. It is understood that two, three ox more lines ~kl, zk2, etc.
(as in Figure 1) could be provided. In Figure 2 and also the fol-lowing Figures the parts with the same ~unction as those in Figure 1 are identified by the same reference numerals.
In addition to the illu3tration in Figure 1, reference numeral~ rela ing to the cold line 9.2 were added in Figures 2 and 3 for a pipe section 9.21 between the second heat exchanger 6 and the pump 5, for a pipe section 9.22 between the pump 5 and a branch point 16 and for a pipe section 9~23 between the branch point 16 and the first heat exchanger 4. It can already be seen from Figure 1 that there are no conventional valves for the change-over to emergency cooling operation. Figure 2 shows in greater detail that the respective flow rate regulating units for ~3~6717 - 14 20365-29g4 the after heat removal branch 10, 11, 12 are designed as a vortex chamber valve WV comprising a hydraulic connection sO for the supply current sl, a connection cO or the control current cl and a connection eO for the outlet current el. The internally con-trollable current path sO-eO is thereby connected at the branch point 17 to the hot line 9.1 of the intermediate circuit ZK via the associated pipe section 11.1 of th~ influx pipe 11 of the cooler 10 and the hydraulic connection cO for the control current cl is connected at the branch point 18 to the delivery side of the pump 5 of the intermediate circuit.
A single such vortex chamber valve WV is schematically illustrated in Figures ~ to 6 for better understanding. Its hy-draulic connections sO, cO and eO and the fluid currents, namely the supply current sl~ control current cl and outlet current el, are identified exactly the same as in Figure 2. The radial vor-tex chamber valve WV illustrated by way of example in Figure 4 (there are also axial and conical vortex valves) consists of a flat, hollow cylindrical vortex chamber housing 19 containing a vortex chamber 19', a connection piece for the supply current sl or suppl~ connection sO 10wing radially into the vortex chamber 19i, a connec~on piece for the control current cl or control con-connection cO flowing tangentially into the vortex chamber 19' and a connection piece for the outlet currentel or an outlet connection eO arranged axially with respect to the rotational axis of the housingl9 or the vortex chamber 19', As illustrated, the outlet connection eO can be designed like a nozzle or Venturi tube in order to keep the pressure drop as small as possible. The supply current sl, illustrated by dash lines, ~26717 which is fed through the radially arranged supply connectlon sO, leaves the vortex chamber 19' through the axial outlet connection eO, whereby it is first of all assumed that no control current cl is flowing yet. The throttle effect of this vortex chamber valve WV is then relatively low and sl = el. If a control current cl, whose control pressure is about 5 to 10% higher -than the pressure of the supply current sl, is sent through the tangential control connection cO, then an increasingly intensive twisting flow is produced in the vortex chamber 19' as the quantity of control cur-rent increases. Its centrifugal force causes the build-up of a counterpressure in the vortex chamber 19' which can reduce and thus control the influx of supply current sl (or increase it again with decreasing control current cl). A relatively low maximum control current throughput of approximately 10 to 20% of the maxi-mum throughput of the supply current sl is enough to bring the supply current sl to a standstill. The control current cl flows from the tangential control connection cO in spirals to the axial outlet connection eO and this spiral flow continues in its connec-tion piece. The outlet current el can contain both the control current cl as well as the supply current sl. If, however, the throughpu~ of the control current cl reaches the designated maxi-mum of approximate]y 10 to 20% of the supply current sl, then the latter comes to a standstill. The outlet current el then only contains the control current cl so that then approximately 20% of the throughput of the to a large extent blocked supply current sl flow3.
Figure 4 shows the general view, Figure 5 æhows a simp]ified flow diagram and Figure 6 shows the circuit symbol ~ 3L32~7~7 obtained therefrom of the vortex chamber valve WV which can also be simply identified as a vortex valve.
Coming back to Figure 2: It illustrates th0 "normal operation" in which the secondary coolant of the intermediate cir-cuit ZK is circulated by the pump 5 - see arrow f2. The control connection cO (tangential control current cl) of the associated vortex chamber valve WV is connected to the delivery side of the pump 5 via pipe 13 and with its supply connection sO is connected at the branch point to the hot line 9.1 of the intermediate cir-cuit ZK via the pipe 11.1. If the pump 5 is running, then the supply current sl is almost stopped by the control current cl, i.e. flow via the cooler 10 is prevented. The low control current cl flows via the outlet connection eO as outlet current el and via the pipe 11.2 to the cooler 10, is cooled in the cooler 10 and then flows back to the branch point 16 via the reflux pipe ~ F
where it mlxes with the secondary coolant in the cold line 9.2 of the intermediate circuit ZK. Since almost no supply current sl flows during the operating condition illustrated in Figure 2, ~he correQponding reference numeral i8 placed in brackets and the a~-sociated arrow is illustrated by dash lines. Furthermore, due to the low throughput the outlet current el i8 only illustrated by dash lines.
Figure 3 shows the operatin~ condition "afterheat remov-al". Pump 5 is thereby switched off. The vortex chamber valve WV
has lost its blocking function since the control current cl (there is only natural circulation) is brought to a standstill on account of the pressure ratios. As is made clear by the arrow~ sl-el-f3, the ~econdary coolant of the intexmediate circuit ~K circulates 132~i7~l7 - 17 ~ 20365-2994 via the cooler 10. No or almost no control current cl is flowing any longerO Reference numeral cl is therefore placed in brackets and the associated arrow is illustrated by dash lines. However, the supply current sl, whose throughput is equal to that of the outlet current el, is flowing. Since the pump 5 is stopped, the flow stagnates at the primary side of the second heat exchanger 6 and in the pipe section 9.21 and the transfer pump (not illustrat-ed) provided for the heat supply network HN is also no longer working.
The heating reartor system according to Figure 7 corre-sponds in principle to that according to Figures 1 to 3. Added to this embodiment are two isolating valves 20a, 20b connected di-rectly in front of and after the pump 51 pressure vessels 21 re-spectively connected to the cold lines 9.2 of the intermediate circuit ZK, a non-return flap 107 in the branch 9.21, and in the six lines zkl to zk6 illustrated of the intermediate circuit ZK
motor-actuated control flaps or spool valves 105 provided in the hot line 9.1 and control flaps or spool valves 106 provided in the cold line 9.2. The non-return flap 107 allows a primary-side flow through the second heat exchanger 6 only in direction f2. The isol~ting valves 20a, 20b are used to separate the pump 5 from the remainins network during maintenance or repair work. The first heat exchangers 4 are modified ~omewhat in comparison to those in Figures 1 to 3. Their heat exchanger tubes 4.1 are divided into two partial tube bundles or pipe coils 4.11 and 4.12 connected parallel to one another. In addition, it can be seen that the pipes for the hot line 9.1 and the cold line 9.2 of the intermedi-ate circuit ZK leaving the first heat exchangers 4 are guided to ~32~7~7 - 18 - 20365-2~94 the outside through the casing wall 103 of the reactor pressure vessel 1 below its closure head flange connection 101, 102.
Flange 101 is part of the vessel base portion 1.1 and flange 102 is part of the closure 1.2.
The exemplary embodiments according to Figures 1 to 7 are based on a circuit arrangement wherein the afterheat removal branch 11, 10, 12 is connected to the hot or cold line 9.1, 9.2 on the secondary side of the first heat exchanger 4~ I~ the heat ex-changers 4 are arr~nged within the reactor pressure vessel 1 at a sufficiently large distance from the reactor core 2, then activa-tion of the secondary coolant is relatively low and having the secondary coolant act on the afterheat removal branch is justi-fied. In principle, it is also possible, however, to provide separate condensers in the steam plenum 14 of the reactor pressure vessel 1 for afterheat removalO
The heating reactor system illustrated in Figure 8 is preferably suitable for a thermal power output in the range of 5 to 50 MW. The reactor building is again identified by reference numeral 15 and it is illustrated somewhat more clearly that it consists of concrete walls. It is arranged underground in a cor-responding chamber 22 in the ground 23. The afterheat removal branch with its influx pipe 11, the cooler 10 and the reflux pipe 12 is connected to the hot line 25.1 of a condenser 24 via the vortex chamber valve WV, namely its controllable current path (sO-eO) between the supply connection sO and the outlet connection eO, and to the cold line 25.2 of the condenser 24 at the connec-tion point 26 of the reflux pipe 12. The condenser 24 is arranged in the steam plenum 14 of the reactor pressure vessel 1. The path of the steam rising in the volu~e of water 3 is schematically il-lustrated by the flow path F2 and the direction arrows f4. The steam flows through the primary side of the condenser 24~and, if the condenser 24 is cooled on the secondary side, releases its vaporization heat via the heat exchanger tubes 24.1 to the ter-tiary medium flowing therein, whereby the steam condenses and flows back into the volume o4 water 3 in accordance with flow arrows f5.
The second heat exchanger 6 - in this exemplary embodi-ment of a so called integral design - is also arranged in the steam plenum 14, i.e. also within the space enclosed by the reac-tor pressure vessel 1. For this reason the output pipe 7 and the return pipe 8 of the heat supply network HN penetrate the wall of the reactor pressure vessel 1, namely preferably the casing wall lU3, and are connected to the outlet end or the inlet end of the heat exchanger tubes 6.1 of the second heat exchanger 6. On their way to or from the second heat exchanger 6 the output and return pipe~ also penetrate the wall of the reactor containment shell 130 and the wall of the reactor building 15. The individual penetra-tion po1nts, seen from the outside in, are identified by reference numerals 7a, 7b and 7c for the output pipe 7 and by reference numerals 8a, 8b and 8c for the return pipe 8. The penetration point 7c, 8c of the output and return pipes 7, 8 are arranged below the pressure-sealed closure head flange connection 101, 102.
The secondary side of the first heat exchanger 4, i.e. the inlet and outlet endR of its heat exchanger tube~ 4.1, is connected to the primary side of the second ~integral) heat exchanger 6 via the hot and the cold secondary coolant line 9~1 or 9.2. For this ~ ~32~7~7 - 20 - ~0365-2994 reason the secondary coolant flows around the outside of the heat exchanger tubes 6.1 of the second heat exchanger 6, the tertiary medium of the heat supply network ~N flowing throu~h these tubes 6.1 during normal operation.
A motor-driven, remote-controllable valve 27 or 28 is inserted in each of the two pipes 7 and 8 (output and return pipe) within the reactor building 15 and preferably outside the contain-ment vessel 130. These valves 27, 28 can also be isolatin~ valves since they can completely separate the secondary side of the second heat exchanger 6 from the heat supply network if they are in the closed position. An adjustable throttle 29 connected in series to the valve 28 and preceding it is located in the return pipe 8, this throttle generating, on account of the pressure drop formed at it, a control pressure for the control current cl during normal heating operation. The control current comprises a partial current of the liquid heating medium branched o~f in front of the throttle 2g, this heating medium being fed to the control connec-tion cO of the vortex chamber valve WV via the control pipe 30 connected at the input side of the throttle 29.
The illustration in Yigure 8, just as the illustrations in Figures 1 to 7, is schematic, i.e. supports and holders ~or the containment ve~sel 130, the reactor pressure vessel 1, the first and second heat exchangers ~ and 6, the condenser 24, the valves 27l 28 and the throttle 29 as well as for the reactor core 2 are ~ot illustrated. The volume in the space 108 between the reactor pressure vessel 1 and the reactor containment vessel 130 on the one hand and the volume of water 3 on the other hand are determined in such i326717 a way that in the event of a leak in the wall of the reactor pres-sure vessel 1 the liquid level for the (now reduced) volume of water 3 will adjust to the volume of water in the space 108 such that the reactor core 2 at any rate remains covered with primary coolant.
The reflux pipe 12 ends via a pipe branch 12.1 at the connection point 31 between the valve 28 and the throttle 29.
During normal operation, i.e. when the heating medium in the heat supply network, not illustrated in greater detail, flows in accor-dance with the arrows f6 ~output) and f7 (return), the throttle 29 throttles down to such an extent that the dynamic pressure at its input side acts as control pre~gure on the control connection cO
of the vortex chamber valve WV, namely ~uch that the controllable current path sO-eO is to a large extent blocked so that no appre-ciable supply current sl can be built up via the hot line 25.1 of the conden~er 24. A first portion of the heating medium thus flows directly to the second heat exchanger 6 via the throttle 29 and the valve 28 and a second ~smaller, during normal operation) portion flows via the control pipe 30 and the control connection-outlet connection section cO-eO of the vortex chamber valve WV as well as via the influx pipe 11 into the cooler 10 where it is cooled down somewhat urther and then flows through the reflux pipe 12 back to the connection point 31 and from there tc the second heat exchanger 6. During this operating condition the con-denqer ~4 contributes almost nothing or nothing appreciable to the steam cooling since the supply current sl which can flow via the section sO-eO of the vortex chamber valve WV is very small. The arrows sOl in dash lines identify thi~ low power flow which is fed ~32~717 - 22 - 2~365-29 and maintained by the heating medium (tertiary medium).
If the two isolating valves 27, 28 are closed in the course of inspection or repair work and/or if a fuel element i5 replaced and if the external pumps (not illustrated) conveying the heating medium are thereby accordingly also switched off, then the control pressure in the control pipe 30 drops to such an extent that the throttle effect of the control current cl stops. The section sO-eO of the vortex chamber valve WV is unblocked since its flow resistance is reduced considerably, resulting in a closed cooling circuit which i5 in addition induced by the forced heating of the medium in the heat exchanger tubes 24.1 of the con-denser 24, namely because the first and second heat exchangers 4 and 6 can no longer contribute to the removal of heat. The con-trol rods are inserted into the reactor core 2 during this after-heat removal op~ration and the condenser 24 is thus used to remove the decay heat. The tertiary medium flows via the hot line 2S.l, the ~ection sO-eO of the vortex chamber valve WV and the influx pipe 11 to ~he cooler 10, is cooled ~here (the cooler can be an air cooler or a water cooler) and, cooled of~, flows back to the heat exchanger tubes 24.1 of the conden~er 24 via the reflux pipe 12, the connection point 26 and the cold line 25.2. As can be seen, the removal of decay heat in the exemplary embodiment ac cording to Figure 8 can be induced without having to open addi~
tional valves in the afterheat removal branch 10, 11, 12. The vortex chambPr valve WV takes over the automatic change-over if the control pres~ure alls below a minimum value at its control connection cO and switche~ back to normal operation if the control pressure exceeds a miniumum value at the control connection cO.
~32~717 A variant of the heating reactor system according to Figure 8 is illustrated in Figure 9. The control pressure for the control connection cO of the vortex chamber valve WV is thereby generated not by throttling the flow in the return pipe 8 of the heat supply network, but by a control current pump 40 inserted in a control current path 41, 42, this control current pump being connected at connection point 26 to the reflux pipe 12 via a suc-tion pipe 41 and to the control connection cO of the vortex cham-ber valve ~ via a pressure pipe 42. During normal heating opera-tion of the illustrated heating reactor HR the control current pump 40 operates as a continuous running pump. The throughput pumped by it is relatively small so that a small control current pump is sufficient. During normal operation of the heating reac-tor HR a control pressure blocking or sharply throttling the in-ternally controllable current path sO-eO of the vortex chamber valve WV is generated by the control current pump 40. If the heating reactor HR is shut down - this occurs when the control rods, not illustrated, are fully inserted into the core of the heating reactor HR - then the control current pump 4n is al~o switched of. The means for stopping the control current pump 40 advantageou~ly depend for control on the command for insertion of the control rods (not illustrated). For example, an electrical command which, for example, cuts the power supply for the driYe motor of the control current pump 40 via a relay or an electronic switch can be derived from the electrical or hydraulic command for the complete insertion of ~he control rods and thus for the shutdown oE the heating reactor. On the other hand, when the heating reactor HR is restarted the relay or electronic switch is 3L~2671~
- 24 - 20365-29g4 controlled in such a way tha~ the motor is switched on again and the pump 40 begins to run. With the control current pump 40 switched o~f, the controllable current path sO-eO of the vortex chamber valve WV is opened for an unthrottled flow so that, as was already explained on the basis of Figure 8, natural circulation flow develops via the hot line 25.1 of the condenser 24, the open current path sO-eO, the influx pipe 11, the cooler lO, the reflux pipe 12 and the cold line 25.2 of the condenser 24 back to the heat exchanger tubes 24.1 of this condenser, the decay heat re-sulting in the heating reactor HR being removed by this natural circulation ~low. The heating reactor system according to Figure 9 corresponds otherwise to Figure 8. For this reason only one section is illustrated.
The afterheat removal circuit according to Figure 9 with its control current pump 40, the vortex chamber valve WV, the afterheat removal branch ll, 10, 12 and the connected condenser 24 can be advantageously used to remove the decay heat in a boiling water reactor or also in a pre~suri~ed water reactor, i.e. in those light-water reactors which serve to generate driving steam ~or a steam turbo-generator unit. Such a turbo-generator unit comprises a steam turbine on which the driving steam acts and a turbo-generator coupled to the steam turbine for generating elec-trical energy. In this case, one or a plurality of condensers are arranged within the stea~ plenum of the reactor, whereby the pipes for the hot and cold lines 25.1, 2S.2 connected to their heat ex-changer tubes 24.1 are guided to the outside through the wall o the reactor in corresponding pressure-3ealed penetrations.
It will be explained herebelow on the basis of Figure l that the afterheat removal circuit illustrated in Figures 1 to 7 is also suitable for removing the decay heat in a boiling water reactor or a pressurized water reactor. For the explanation, ref-erence is made herebelow only to the two lines zkl of the inter-mediate circuit ZK. It is understood, however, that more than one pair of lines zkl can be used for afterheat removal~
According to the exemplary embodiment, the second heat exchanger 6 on the secondary side of the first heat exchanger 4 is replaced by a pipe section 50, illustrated by dash lines, connect-ing the two secondary coolant lines 9.1, 9.2. As a result the secondary coolant is circulated by the pump 5 during normal opera-tion of the reactor (not illustrated) to generate the control pressure for the control connection cO of the vortex chamber valve WV. This pump 5, just as the control current pump 40, then oper-ates as a continuous running pump to genexate the control pres-sure. Since an external heat supply network HN is not connected in this case, the pipes for the hot and cold line 9.1~ 9.2 can be hortened. Ths controllable current pa~h sO-eO of the vortex valve WV is blocked or sharply throttled, as was already e~plained several times. A control command for ~witching off the drive motor of the pump S is only given when the control rods in the boiling water or pressurized water reastor are moved into the com~
pletely shutdown position and the controllable current path of the vortex chamber valve WV is thus opened; afterheat removal opera-tion in the natural circulation flow begins immediately. The secondary coolant heated in the heat exchanger tubes 4.1 of the ~irst heat exchanger 4 flows via the hot line, the pipe section 11.1, the current path sO-eO of the vortex chamber valve WV, the ~326717 - 26 - 20365-~,9g4 influx pipe 11, the cooler lOa and the reflux pipe 12 back to the cold line 9.2 and rom there to the heat exchanger 4, whereby the secondary coolant is continuously cooled in the cooler lOa and the decay heat is thus removed. In this exemplary embodiment the first,heat exchanger 4, disposed in the volume of water 3 of the boiling water or pressurized water reactor, is utilized a~ a heat sink for the removal of decay heat. The two pipes 9.1 and 9.2 for its hot and cold line ~ust again be guided pressure-sealed to the outside through the wall of the reactor pressure vessel. These pipe penetrations can be provided in the cover or the casins wall of the reactor pressure vessel, not illustrated.
In acordance with the second embodiment for using the afterheat removal circuit with a vortex chamber valve for boiling water or pressurized water reactors, the pump 5 i~ dispensed with in accordance with the exemplary embodiment according to Figure 9.
It is sufficient if the intermediate circuit lines zkl under con-sideration extend only up to the points 61, 62 indicated by the da~h lines. Instead of the pump 5 in the cold line 9.2, a control current pump 60 is disposed in this embodiment in the control cur-rent path 13. Thi~ pump 60 is lik~wise only illustrated by dash lines ~ince it is a variant within the framework of the use. The control current pump 60 is connected to ~he reflux pipe 12 via a suction pipe section 13.1 of the control current path 13 (or to the pipe section of the hot line 9.2 connected to it) and to the control connection cO of the vortex chamber valve WV via a pres-sure pipe section 13.2 of the control current path 13. As was already explained on the basis of ~'igure 9, a control pre~sure blocking or sharply throttling the internally controllable current ~326717 , ,~
- 27 - 20365-29g4 path sO-eO of the vortex chamber valve WV is generated by the con-trol current pump 60 during normal operation of the reactor (not illustrated). As well, means (not illustrated) which were already explained in greater detail on the basis of Figure 9 are again provided for stopping the control current pump 60 during shutdown of the reactor. The advantage of this embodiment lies therein that the throughput of the control current pump 60 amounts to ap-proximately only 10 to 20% of the throughput which the pump 5 must circulate. The control current pump can therefore be a relatively small pump.
Claims (26)
1. A heating reactor system, particulary for light-water reactors, comprising a nuclear reactor having a reactor pressure vessel, said reactor pressure vessel containing a volume of water as primary coolant, a core of said nuclear reactor being located within said volume of water and, comprising a first heat exchanger and a second heat exchanger connected to one another via an intermediate circuit for a secondary coolant, and an afterheat removal circuit, which contains an afterheat removal cooler, connected to the intermediate circuit via cooler connection pipes in the form of an influx pipe and a reflux pipe and with at least one flow rate regulating unit inserted in the cooler connection pipes, characterized in that a vortex chamber valve is provided as the flow rate regulating unit.
2. A heating reactor system according to claim 1 having a pump in and a hot line as well as a cold line belonging to the intermediate circuit, characterized in that the vortex chamber valve is provided with a supply connection, a control connection and an outlet connection, and that the supply connection is connected to the hot line, the outlet connection is connected to the cold line via the afterheat removal cooler and the control connection on the delivery side of the pump is likewise connected to the cold line of the intermediate circuit.
3. A heating reactor system according to claim 1, characterized in that a vortex chamber valve is inserted in the influx pipe of the afterheat removal cooler.
4. A heating reactor system according to any one of claims 1 to 3, wherein said core has an upper edge having a primary and a secondary side as well as heat exchanger tubes characterized in that the first heat exchanger is arranged in the volume of water at a distance above the upper edge of the core and can be heated on the primary side by the primary coolant, and that the pipes of the intermediate circuit connected on the secondary side to the heat exchanger tubes of the first heat exchanger are guided to the outside through the wall of the reactor pressure vessel.
5. A heating reactor system according to claim 1, wherein the reactor pressure vessel has a steam plenum above the volume of water characterized in that the first and the second heat exchangers are arranged integrally within the space enclosed by the reactor pressure vessel, the second heat exchanger being disposed within the steam plenum.
6. A heating reactor system according to claim 4, characterized in that an output pipe and a return pipe, which are connected to the heat exchanger tubes of the second heat exchanger, are guided to the outside through the wall of the reactor pressure vessel and are connected to an external heat supply network.
7. A heating reactor system according to any one of claims 1 to 3, 5 or 6, having a hot line and a cold line belonging to the intermediate circuit and the reactor pressure vessel having a casing wall and a closure head flange connection characterized in the pipes for the hot line and the cold line of the intermediate circuit leaving the first heat exchanger or the output pipe and return pipe leaving the second heat exchanger disposed in the reactor pressure vessel penetrate the casing wall of the reactor pressure vessel below the closure head flange connection.
8. A heating reactor system according to claim 4, having a hot line and a cold line belonging to the intermediate circuit and the reactor pressure vessel having a casing wall and a closure head flange connection characterized in the pipes for the hot line and the cold line of the intermediate circuit leaving the first heat exchanger or the output pipe and return pipe leaving the second heat exchanger disposed in the reactor pressure vessel penetrate the casing wall of the reactor pressure vessel below the closure head flange connection.
9. A heating reactor system, particularly for light-water reactors, comprising a nuclear reactor having a reactor pressure vessel, said reactor pressure vessel containing a volume of water as primary coolant, a core of said nuclear reactor being located within said volume of water and a steam plenum above said volume of water and comprising a first heat exchanger and a second heat exchanger connected to one another via an intermediate circuit for a secondary coolant, with the additional features of an afterheat removal circuit which contains an afterheat removal cooler and which is connected to the secondary side of a further heat exchanger arranged in the reactor pressure vessel via cooler connection pipes in the form of an influx pipe and a reflux pipe, whereby a vortex chamber valve is inserted in the cooler connection pipes, as a flow rate regulating unit and whereby the further heat exchanger is a condenser arranged in the steam plenum of the reactor pressure vessel.
10. A heating reactor system according to claim 9, wherein the vortex chamber valve has a supply-connection, an outlet-connection and a control-connection characterized in that the internally controllable current path of the vortex chamber valve formed between the supply connection and the outlet connection is inserted in the influx pipe of the afterheat removal cooler.
11. A heating reactor system according to claim 9 or 10, wherein the vortex chamber valve has a supply-connection, an outlet-connection, and a control-connection, characterized in that an adjustable throttle having a delivery side is inserted in the return pipe of an external heat supply network, the delivery side of this throttle being connected to a control pipe leading to the control connection of the vortex chamber valve, and that the reflux pipe of the afterheat removal cooler is connected to a pipe branch on the side of the throttle facing away from the delivery side.
12. A heating reactor system according to claim 9 or 10, wherein the vortex chamber valve has a supply-connection, an outlet-connection, a control-connection, and an internally controllable current path between the supply- and the outlet-connection characterized in that a control current pump lying in a control current path is connected to the reflux pipe via a suction pipe and to the control connection of the vortex chamber valve via a pressure pipe, whereby a control pressure blocking or sharply throttling the internally controllable current path of the vortex chamber valve can be generated by the control current pump during normal operation of the heating reactor and whereby means are provided for stopping the pump during shutdown of the heating reactor.
13. Use of the afterheat removal circuit with a vortex chamber valve according to any one of claims 1 to 3, 5 or 6 for removing the afterheat in a boiling water reactor or a pressurized water reactor which serve to generate driving steam for a steam turbo-generator unit.
14. Use of the afterheat removal circuit with a vortex chamber valve according to claim 4, for removing the afterheat in a boiling water reactor or a pressurized water reactor which serve to generate driving steam for a steam turbo-generator unit.
15. Use of the afterheat removal circuit with a vortex chamber valve according to claim 7, for removing the afterheat in a boiling water reactor or a pressurized water reactor which serve to generate driving steam for a steam turbo-generator unit.
16. Use of the afterheat removal circuit with a vortex chamber valve according to claim 8, for removing the afterheat in a boiling water reactor or a pressurized water reactor which serve to generate driving steam for a steam turbo-generator unit.
17. Use according to claim 13, wherein a first heat exchanger and a second heat exchanger are connected by secondary coolant lines, namely a hot line and a cold line of an intermediate circuit characterized in that the second heat exchanger on the secondary side of the first heat exchanger is replaced by a pipe section connecting the two secondary coolant lines so that the secondary coolant can be circulated by the pump during normal operation of the reactor to generate a control pressure, said control pressure being supplied to a control connection of the vortex chamber valve, whereby means are provided for stopping the pump during shutdown of the reactor.
18. Use according to claim 14, wherein a first heat exchanger and a second heat exchanger are connected by secondary coolant lines, namely a hot fine and a cold line of an intermediate circuit characterized in that the second heat exchanger on the secondary side of the first heat exchanger is replaced by a pipe section connecting the two secondary coolant lines so that the secondary coolant can be circulated by the pump during normal operation of the reactor to generate a control pressure, said control pressure being supplied to a control connection of the vortex chamber valve, whereby means are provided for stopping the pump during shutdown of the reactor.
19. Use according to claim 15, wherein a first heat exchanger and a second heat exchanger are connected by secondary coolant lines, namely a hot line and a cold line of an intermediate circuit characterized in that the second heat exchanger on the secondary side of the first heat exchanger is replaced by a pipe section connecting the two secondary coolant lines so that the secondary coolant can be circulated by the pump during normal operation of the reactor to generate a control pressure, said control pressure being supplied to a control connection of the vortex chamber valve, whereby means are provided for stopping the pump during shutdown of the reactor.
20. Use according to claim 16, wherein a first heat exchanger and a second heat exchanger are connected by secondary coolant lines, namely a hot line and a cold line of an intermediate circuit characterized in that the second heat exchanger on the secondary side of the first heat exchanger is replaced by a pipe section connecting the two secondary coolant lines so that the secondary coolant can be circulated by the pump during normal operation of the reactor to generate a control pressure, said control pressure being supplied to a control connection of the vortex chamber valve, whereby means are provided for stopping the pump during shutdown of the reactor.
21. Use according to claim 13, characterized in that a control current pump lying in a control current path is connected to the reflux pipe via a suction pipe section and to a control connection of the vortex chamber valve via a pressure pipe section, whereby a control pressure blocking or sharply throttling the internally controllable current path of the vortex chamber valve can be generated by a control current pump during normal operation of the reactor and whereby means are provided for stopping the control current pump during shutdown of the reactor.
22. Use according to claim 14, characterized in that a control current pump lying in a control current path is connected to the reflux pipe via a suction pipe section and to a control connection of the vortex chamber valve via a pressure pipe section, whereby a control pressure blocking or sharply throttling the internally controllable current path of the vortex chamber valve can be generated by a control current pump during normal operation of the reactor and whereby means are provided for stopping the control current pump during shutdown of the reactor.
23. Use according to claim 15, characterized in that a control current pump lying in a control current path is connected to the reflux pipe via a suction pipe section and to a control connection of the vortex chamber valve via a pressure pipe section, whereby a control pressure blocking or sharply throttling the internally controllable current path of the vortex chamber valve can be generated by a control current pump during normal operation of the reactor and whereby means are provided for stopping the control current pump during shutdown of the reactor.
24. Use according to claim 16, characterized in that a control current pump lying in a control current path is connected to the reflux pipe via a suction pipe section and to a control connection of the vortex chamber valve via a pressure pipe section, whereby a control pressure blocking or sharply throttling the internally controllable current path of the vortex chamber valve can be generated by a control current pump during normal operation of the reactor and whereby means are provided for stopping the control current pump during shutdown of the reactor.
25. Use of the afterheat removal circuit with a vortex chamber valve according to claim 9 for removing afterheat in a boiling water reactor or a pressurized water reactor which serve to generate driving steam for a steam turbo-generator unit.
26. Use of the afterheat removal circuit with a vortex chamber valve according to claim 12 for removing afterheat in a boiling water reactor or a pressurized water reactor which serve to generate driving steam for a steam turbo-generator unit.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE3833327 | 1988-09-30 | ||
| DEP3833327.9 | 1988-09-30 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1326717C true CA1326717C (en) | 1994-02-01 |
Family
ID=6364117
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA000614208A Expired - Fee Related CA1326717C (en) | 1988-09-30 | 1989-09-28 | Heating reactor system with an afterheat removal circuit and use of the latter for boiling water reactors and pressurized water reactors |
Country Status (4)
| Country | Link |
|---|---|
| EP (1) | EP0362596B1 (en) |
| CN (1) | CN1027201C (en) |
| CA (1) | CA1326717C (en) |
| DE (1) | DE58906300D1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5428652A (en) * | 1991-08-12 | 1995-06-27 | Siemens Aktiengesellschaft | Secondary-side residual-heat removal system for pressurized-water nuclear reactors |
Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE4126630A1 (en) * | 1991-08-12 | 1993-02-18 | Siemens Ag | SECOND-SIDED HEAT EXHAUST SYSTEM FOR PRESSURE WATER CORE REACTORS |
| US7757715B2 (en) | 2006-11-28 | 2010-07-20 | Mitsubishi Heavy Industries, Ltd. | Accumulator and method of manufacturing flow damper |
| US7881421B2 (en) | 2006-11-28 | 2011-02-01 | Mitsubishi Heavy Industries, Ltd. | Accumulator |
| FR2975215B1 (en) * | 2011-05-11 | 2013-05-10 | Areva | NUCLEAR REACTOR WITH INJECTION DEVICE OF NANO PARTICLES IN CASE OF ACCIDENT |
| CN102601085B (en) * | 2012-03-16 | 2014-06-18 | 中广核工程有限公司 | System and method for washing nuclear loop of nuclear island |
| CN103456375B (en) * | 2013-07-31 | 2016-05-25 | 中广核研究院有限公司 | With the secondary side residual heat removal system of non-active volume control device |
| DE102016206906A1 (en) * | 2016-04-22 | 2017-10-26 | Areva Gmbh | Passive level control system |
| CN111951985B (en) * | 2020-07-15 | 2022-10-18 | 四川大学 | Modularized space nuclear reactor power generation unit |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2112228A1 (en) * | 1971-03-13 | 1972-09-14 | Edwin Wanka | Nuclear reactor primary circuit - for subsidiary heating additional to main primary cooling circuit |
| CH539927A (en) * | 1972-04-25 | 1973-07-31 | Siemens Ag | Coolant isolation system - for insertion between high and low pressure pipework in nuclear reactors |
| DE2459150C3 (en) * | 1974-12-14 | 1988-07-07 | BBC Brown Boveri AG, 6800 Mannheim | Method and circuit arrangement for removing the decay heat of a pressurized water reactor in the event of a malfunction |
| DE2621258A1 (en) * | 1976-05-13 | 1977-11-24 | Interatom | NUCLEAR ENERGY PLANT WITH IMPROVED FACILITIES FOR SUBSTITUTE AND EMERGENCY HEAT DISCHARGE |
| DE3021965A1 (en) * | 1980-06-12 | 1981-12-17 | Evt Energie- Und Verfahrenstechnik Gmbh, 7000 Stuttgart | Light water reactor for power and process steam generation - has superheater heated by fossil fuel and tertiary process steam circuit |
-
1989
- 1989-09-15 EP EP89117137A patent/EP0362596B1/en not_active Expired - Lifetime
- 1989-09-15 DE DE89117137T patent/DE58906300D1/en not_active Expired - Fee Related
- 1989-09-28 CA CA000614208A patent/CA1326717C/en not_active Expired - Fee Related
- 1989-09-30 CN CN89108173A patent/CN1027201C/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5428652A (en) * | 1991-08-12 | 1995-06-27 | Siemens Aktiengesellschaft | Secondary-side residual-heat removal system for pressurized-water nuclear reactors |
Also Published As
| Publication number | Publication date |
|---|---|
| EP0362596A1 (en) | 1990-04-11 |
| CN1027201C (en) | 1994-12-28 |
| EP0362596B1 (en) | 1993-12-01 |
| CN1041665A (en) | 1990-04-25 |
| DE58906300D1 (en) | 1994-01-13 |
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| Date | Code | Title | Description |
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| MKLA | Lapsed |