DE1514534A1 - Heterogeneous nuclear reactor - Google Patents

Heterogeneous nuclear reactor

Info

Publication number
DE1514534A1
DE1514534A1 DE19651514534 DE1514534A DE1514534A1 DE 1514534 A1 DE1514534 A1 DE 1514534A1 DE 19651514534 DE19651514534 DE 19651514534 DE 1514534 A DE1514534 A DE 1514534A DE 1514534 A1 DE1514534 A1 DE 1514534A1
Authority
DE
Germany
Prior art keywords
nuclear reactor
reactor
heat exchanger
temperature
heterogeneous nuclear
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.)
Pending
Application number
DE19651514534
Other languages
German (de)
Inventor
Wolfgang Braun
Franz Winkler
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Siemens AG
Original Assignee
Siemens AG
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Priority claimed from DES92534A external-priority patent/DE1281049B/en
Application filed by Siemens AG filed Critical Siemens AG
Priority claimed from DES99052A external-priority patent/DE1298651B/en
Publication of DE1514534A1 publication Critical patent/DE1514534A1/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • G21D5/06Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34Spacer grids
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/005Flux flattening
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/02Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/22Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/26Control of nuclear reaction by displacement of the moderator or parts thereof by changing the moderator concentration
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/32Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/02Arrangements of auxiliary equipment
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Description

Heterogener Kernreaktor Zusatz zum Patent . ... ... (Anmeldung S 92 534 VIIIc/21g .. . - PLA 64/1522) Gegeneta@nd d'ee Hauptpatentes ist ein heterogener Atomkernreaktoä vom Druckkeseeltyp, der mit Wasser moderiert und mit Wasser von überkritischem Druck und.überkritischer Temperatur gekühlt wirdi Dieser Kernreaktor k&= dabei im direkten oder auch im indirekter Kreislauf mit einer Turbine äusammenarbeiten. Zur Regelung ge- hört-dabei-neben Regelstäben atach eine Veränderung der Moderator- temperatur über eine entsprechende Justierung der durch= fließenden Moderatormenge.'Es wurde nun gefunden, daß sich der Betrist eines derartigen überkritischen Kernreaktors noch günstiger gestalten läßt, wenn eine Vorwärmung des Speisewassers'mit Hilfe des einen Teiles des im Reaktor selbst erzeugten Frischdampfes vorgenommen wird. Erfindungs- gemäß ist daher eine Vorwärmung des Speisewaasere mit Hilfe eines Wärmetauschers durch einen Teil des im Reaktor erzeug- ten Frischdampfes vorgesehen und wird dieser Teil nach der im rmetauscher vorgenommenen Temperaturabsenkung mit Hilfe einer Pumpe als Kondensat auf der Speisewassereintrittaaeite des Wärmetauschers wieder dem Kühlkreislauf zugeführt. Diese Schaltung ist aus der beiliegenden Figur näher darge- stellt, wobei die hier interessierenden Bauelemente wie folgt bezeichnet sind: Det Kernreaktor mit 1, die Moderatorzufüh- rungeleitung mit 43., das Moderatorregelventil mit 4, das Kühlmittelregelventil mit 42, der Wärmetauscher zur Vor- wärmung des Speisewassers mit 15, die,Kondeneatpumpe mit 14 und die Frischdampfleitung vom Ausgang des Reaktors zum Wärmetauscher 15 mit 11. Die übrigen Bauelemente dieser Schaltskizze können ohne Bezeichnung bleiben, da sie nicht zum Gegenstand dieser Erfindung gehören und an sich keiner näheren Erläuterung bedürfen. Zweck und Funktion dieser Einrichtt.,ng sind nun etwa folgende: Durch das Anhe",en der Eintrittstemperatur des Kühlmittels in den Reaktor wird die Eintritteenthalpiedeeselben ebenfalls erhöht. Bei gleichbleibender Auetrittetemperat@ur des Reaktors bcw. Auetritteenthalpie'dee Kühlmittels ist dadurch infolge der vorgegebenen Leistung ein größerer Kühlmitteldurcheatz durch den Reaktor bedingt. Dieser ist aber wiederum verbun-den mit einer höheren Strömungsgeschwindigkeit und damit einer höheren Wärmeübergangezahl 4 zwischen dem Kühlmittel und.den Brennelementen. Diese Erhöhung der Wärmeübergangezhhl be- wirkt bei konstantgehaltener Leistung eine Erniedrigung der Wandtemperatur der Hüllrohre tzw. t;ei konetantgehaltenen Oberflächentemperaturen eine entsprechende Erhöhung der apezifiechen Reaktorleistung. . Selbstverständlich könnte der für''die Aufhetzung den Speisewaseers.=rerwendete Frischdampf auch direkt in die Speieelei,. tung eingeführt werden. Dazu müßte jedoch zur Überwindung der Druckdifferenz ein Gebläse mit sehr hoher Leistung vorgesehen werden, da die erforderliche Gebläseleistung N etwa proportional ist dem Produkt aus gefördertem Volumen Y und der Druckdifferenz Lä p. Da das Fördervolumen Y dem Produkt von spezifischem Volumen v und der Masse G entspricht, die Masse G jedoch-konetant ist, wird durch die Abktlhlung im Wärmetauscher das spezifische Volumen v etwa auf q/10 herabgesetzt und dadurch die notwendige Pumpenleistung entsprechend verkleinert. Über diesen Kunstgriff ist es also möglich, die Pumpenleistung auf ein erträgliches Maß herabzusetzen. Durch diese Ausführungen wird auch ersichtlich, daß@es mit der beschriebenen Einrichtung möglich ist, entweder die'Leistung des Reaktors zu erhöhen oder aber auch die Oberflächentemperatur der Brennelemente herabzusetzen. Beide Möglichkei- ten sind aber gerade für einen überkritischen Kernreaktor von großer Bedeutung, da sie damit hinsichtlich der Grüße des Reaktors und der Beanspruchung seines Strukturmaterials wesent- liche Vereinfachungen und Erleichterungen mit sich bringen.Heterogeneous nuclear reactor Addition to the patent. ... ... (registration S 92 534 VIIIc / 21g .. . - PLA 64/1522) Gegeneta @ nd d'ee main patent is a heterogeneous atomic nuclear reactor of the pressure soul type moderating with water and with water from supercritical pressure and supercritical temperature is cooled i This nuclear reactor k & = thereby directly or indirectly Circulation äusammenarbeiten with a turbine. To regulate hears-besides the control staff atach a change in the moderator- temperature via a corresponding adjustment of the through = flowing moderator crowd. 'It has now been found that the operation of such a supercritical nuclear reactor Can be made even cheaper if a preheating of the Speisewassers'with the help of one part of the in the reactor self-generated live steam is made. Inventive Accordingly, it is necessary to preheat the food with help of a heat exchanger through part of the th live steam provided and this part is after the Reduce the temperature in the exchanger with the help a pump as condensate on the feedwater inlet side of the heat exchanger is fed back into the cooling circuit. This circuit is shown in more detail in the accompanying figure. represents, the components of interest here as follows are designated: Det nuclear reactor with 1, the moderator feed tion line with 43., the moderator control valve with 4, the Coolant control valve with 42, the heat exchanger for heating of the feed water with 15, the condensate pump with 14 and the main steam line from the outlet of the reactor to Heat exchanger 15 to 11. The other components of this Circuit diagrams can remain without a designation, as they are not belong to the subject matter of this invention and as such do not require further explanation. Purpose and function of this Furnishings are now about the following: By increasing the inlet temperature of the coolant in The inlet enthalpy is also increased in the reactor. If the exit temperature of the reactor remains the same. As a result of the given power, a greater coolant throughput through the reactor is required for outside enthalpy of coolant. However, this is in turn associated with a higher flow rate and thus a higher heat transfer coefficient 4 between the coolant and the fuel assemblies. This increase in Wärmeübergangezhhl loading effect at constant power lowering of the wall temperature of the cladding tubes tzw. If the surface temperatures are kept constant, a corresponding increase in the specific reactor output. . Of course, the live steam used for inciting the Speisewasers could also be fed directly into the Speieelei. to be introduced . However, this would require a blower are provided with a very high power to overcome the pressure difference because the required fan power N is approximately proportional to the product of p conveyed volume Y and the pressure difference Lä. Since the delivery volume Y corresponds to the product of the specific volume v and the mass G, but the mass G is constant , the cooling in the heat exchanger reduces the specific volume v to approximately q / 10 and thus the necessary pump output is reduced accordingly. With this trick it is possible to reduce the pump output to a tolerable level. From these explanations it is also evident that with the device described it is possible either to increase the performance of the reactor or to reduce the surface temperature of the fuel assemblies. Both possibilities , however, are of great importance especially for a supercritical nuclear reactor, since they bring with them considerable simplifications and simplifications with regard to the size of the reactor and the stress on its structural material.

Claims (1)

Patentanspruch Heterogener Kernreaktor, der mit Wasser moderiert und mit Wasser von überkritischem Druck und überkritischer Temperatur gekühlt wird nach Patent . ... ... (Anmeldung S 92 534 YIIIc/21g - fhA 64/1522), dadurch gekennzeichnet, daß für den Kernreaktor eine Vorwärmung des Speisewassers mit Hilfe eines Wärmetauschers durch einen Teil des im Reaktor erzeugten Frischdampfes vorge- sehen ist, der nach dieser Temperaturabsenkung als Kondensat mit Hilfe einer Pumpe auf der Speisewassereintrittseeite deec Wärmetauschers wieder dem Kühlkrei$lauf zugeführt wird.
Claim Heterogeneous nuclear reactor that moderates with water and with Water of supercritical pressure and temperature is cooled after patent. ... ... (registration S 92 534 YIIIc / 21g - fhA 64/1522), characterized in that for the nuclear reactor a preheating of the feed water with the help of a heat exchanger provided by part of the live steam generated in the reactor can be seen that after this temperature decrease as condensate with the help of a pump on the feed water inlet side deec Heat exchanger is fed back into the cooling circuit .
DE19651514534 1964-08-08 1965-08-13 Heterogeneous nuclear reactor Pending DE1514534A1 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DES92534A DE1281049B (en) 1964-08-08 1964-08-08 Heterogeneous pressure vessel reactor
DES0098818 1965-08-13
DES99052A DE1298651B (en) 1964-08-08 1965-08-26 Supercritical heterogeneous atomic nuclear reactor of the pressure vessel type

Publications (1)

Publication Number Publication Date
DE1514534A1 true DE1514534A1 (en) 1969-08-28

Family

ID=27212894

Family Applications (1)

Application Number Title Priority Date Filing Date
DE19651514534 Pending DE1514534A1 (en) 1964-08-08 1965-08-13 Heterogeneous nuclear reactor

Country Status (2)

Country Link
DE (1) DE1514534A1 (en)
FR (1) FR94054E (en)

Also Published As

Publication number Publication date
FR94054E (en) 1969-06-27

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