EP2481054A2 - Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire - Google Patents

Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire

Info

Publication number
EP2481054A2
EP2481054A2 EP10839921A EP10839921A EP2481054A2 EP 2481054 A2 EP2481054 A2 EP 2481054A2 EP 10839921 A EP10839921 A EP 10839921A EP 10839921 A EP10839921 A EP 10839921A EP 2481054 A2 EP2481054 A2 EP 2481054A2
Authority
EP
European Patent Office
Prior art keywords
heat exchanger
heat transfer
exchanger body
flow
pool
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Withdrawn
Application number
EP10839921A
Other languages
German (de)
English (en)
Inventor
Jon D. Mcwhirter
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.)
Searete LLC
Original Assignee
Searete LLC
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 US12/586,741 external-priority patent/US20110075786A1/en
Priority claimed from US12/653,653 external-priority patent/US20110075787A1/en
Priority claimed from US12/653,656 external-priority patent/US9275760B2/en
Application filed by Searete LLC filed Critical Searete LLC
Publication of EP2481054A2 publication Critical patent/EP2481054A2/fr
Withdrawn legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K3/00—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein
    • F01K3/18—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters
    • F01K3/181—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters using nuclear heat
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D1/00—Heat-exchange apparatus having stationary conduit assemblies for one heat-exchange medium only, the media being in contact with different sides of the conduit wall, in which the other heat-exchange medium is a large body of fluid, e.g. domestic or motor car radiators
    • F28D1/02—Heat-exchange apparatus having stationary conduit assemblies for one heat-exchange medium only, the media being in contact with different sides of the conduit wall, in which the other heat-exchange medium is a large body of fluid, e.g. domestic or motor car radiators with heat-exchange conduits immersed in the body of fluid
    • F28D1/0206—Heat exchangers immersed in a large body of liquid
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F1/00—Tubular elements; Assemblies of tubular elements
    • F28F1/02—Tubular elements of cross-section which is non-circular
    • F28F1/04—Tubular elements of cross-section which is non-circular polygonal, e.g. rectangular
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F13/00—Arrangements for modifying heat-transfer, e.g. increasing, decreasing
    • F28F13/06—Arrangements for modifying heat-transfer, e.g. increasing, decreasing by affecting the pattern of flow of the heat-exchange media
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F13/00—Arrangements for modifying heat-transfer, e.g. increasing, decreasing
    • F28F13/06—Arrangements for modifying heat-transfer, e.g. increasing, decreasing by affecting the pattern of flow of the heat-exchange media
    • F28F13/08—Arrangements for modifying heat-transfer, e.g. increasing, decreasing by affecting the pattern of flow of the heat-exchange media by varying the cross-section of the flow channels
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00—Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/02—Header boxes; End plates
    • F28F9/026—Header boxes; End plates with static flow control means, e.g. with means for uniformly distributing heat exchange media into conduits
    • F28F9/0282—Header boxes; End plates with static flow control means, e.g. with means for uniformly distributing heat exchange media into conduits by varying the geometry of conduit ends, e.g. by using inserts or attachments for modifying the pattern of flow at the conduit inlet or outlet
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
    • 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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/243—Promoting flow of the coolant for liquids
    • G21C15/247—Promoting flow of the coolant for liquids for liquid metals
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00—Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D2021/0019—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
    • F28D2021/0054—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for nuclear applications
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
    • G21C1/026—Reactors not needing refuelling, i.e. reactors of the type breed-and-burn, e.g. travelling or deflagration wave reactors or seed-blanket reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This application generally relates to induced nuclear reactions, including systems, processes and elements which implement such processes, such as a reactor core, primary heat exchanger, or pump, immersed in a liquid coolant in a vessel and more particularly relates to a heat exchanger, methods therefor and a nuclear fission reactor system .
  • the afore-mentioned fissile and/or fertile material is typically housed in a plurality of closely packed together fuel assemblies, which define a nuclear reactor core.
  • the fissile and/or fertile material may be a mixture of oxides of plutonium and uranium in the form of fuel pellets housed in fuel rods spaced apart by spacer or wire wound helically around each fuel rod
  • reactor primary coolant is pumped through the reactor fuel assemblies that define the reactor core and is heated by the fission process.
  • the heated primary coolant is carried to a steam generator where the heated primary coolant surrenders its heat to a secondary coolant (i.e., water) disposed in the steam generator.
  • the primary coolant then returns to the reactor core.
  • a portion of the water that receives the heat of the primary coolant vaporizes to steam, which travels to a turbine- generator set to generate electricity.
  • the steam that has passed through the turbine-generator set flows to a condenser that condenses the steam to water, which is then returned to the steam generator.
  • a type of nuclear fission reactor capable of safely generating electricity is a pool-type liquid sodium fast breeder reactor.
  • uranium-238 may be used as a fertile material.
  • the uranium-238 absorbs neutrons and transmutes to fissionable plutonium-239 by means of beta decay.
  • plutonium-239 absorbs a neutron, fission occurs to produce heat.
  • moderating materials such as water, may not be desired as coolant. Rather, in such a pool-type liquid sodium fast breeder nuclear reactor, sodium is the coolant of choice because sodium does not significantly thermalize neutrons.
  • the reactor core can operate at higher power densities so that size of the reactor may be reduced.
  • sodium melts at about 100°C (about 212°F) and boils at about 900°C (about 1650°F).
  • sodium can be used at high temperatures without boiling, thereby allowing high temperature and high pressure steam to be generated. This in turn provides increased power plant thermal efficiency.
  • the sodium coolant circulating through the reactor core becomes radioactive due to absorption of neutrons. Due to this radioactivity, reactor designers utilize intermediate heat exchange loops between the primary sodium coolant loop(s) and the steam generation loop. This lowers the of risk radioactive contamination of the turbine generator. In addition, steam generator pipe leaks may occur. If a leak were to occur in the piping carrying the sodium through the steam generator, the hot radioactive sodium passing through the steam generator will vigorously chemically react with the water and steam in the steam generator. This would radioactively contaminate the water and steam in the steam generator, thereby increasing risk of radioactive contamination of the surrounding biosphere. For all the reasons hereinabove, reactor designers incorporate use of an intermediate heat exchanger between the reactor core and the steam generator to avoid direct contact of the sodium in the core with the steam generator or turbine generator.
  • the intermediate heat exchanger forms a boundary between radioactive primary sodium in the reactor pool and nonradioactive secondary sodium in the steam generator.
  • the intermediate heat exchanger which is disposed in the pool of liquid sodium together with the reactor core, is typically used to remove heat from the fast breeder reactor core and transfer that heat to the external steam generator.
  • the shell of the heat exchanger is heated to a temperature substantially greater than the temperature of the tubes in the heat exchanger by thermal communication with the hot pool and tensioning said tubes during operation by said heating of the shell and thereby accommodating differential thermal expansion in the heat exchanger.
  • a heat exchanger capable of being disposed in a pool fluid residing in the pool-type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid, the heat exchanger comprising: a heat exchanger body; and means integrally formed with said heat exchanger body for removal of the heat.
  • a heat exchanger capable of being disposed in a pool fluid residing in the pool-type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid, the heat exchanger comprising a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a heat exchanger capable of being disposed in a pool fluid residing in the pool- type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid, the heat exchanger comprising: a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, said heat exchanger body having a surface formed thereon defining a portion of the plenum volume; and a heat transfer member coupled to said heat exchanger body, said heat transfer member defining a flow channel therethrough.
  • a heat exchanger capable of being disposed in a pool fluid residing in the pool-type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid, the heat exchanger comprising: a heat exchanger body having a surface formed thereon defining a portion of a plenum volume shaped for a predetermined flow of a heat transfer fluid into the portion of the plenum volume; and a plurality of adjacent heat transfer members connected to said heat exchanger body and spaced apart by a predetermined distance defining a plurality of flow passages between opposing ones of said plurality of adjacent heat transfer members for distributing flow of the heat transfer fluid through the plurality of flow passages.
  • a system for use in association with a pool-type nuclear fission reactor comprising: a nuclear fission reactor core capable of generating heat; a heat exchanger body associated with said nuclear fission reactor core, said heat exchanger body capable of being disposed in a pool fluid and in proximity to an interior periphery of a pool wall confining the pool fluid; and means in heat transfer communication with said nuclear fission reactor core and associated with said heat exchanger body for removal of the heat.
  • a system for use in association with a pool-type nuclear fission reactor comprising: a vessel defining a pool wall having an interior periphery, the pool wall being configured to confine a pool fluid therein; a nuclear fission reactor core capable of being disposed in said vessel and capable of generating heat; a heat exchanger body capable of being in heat transfer communication with said nuclear fission reactor core, said heat exchanger body capable of being disposed in the pool fluid in proximity to the interior periphery of the pool wall, said heat exchanger body having a surface formed thereon defining a portion of a plenum volume shaped for achieving a predetermined flow of a heat transfer fluid into the plenum volume; and means in heat transfer communication with said nuclear fission reactor core and associated with said heat exchanger body for removal of the heat.
  • a system for use in association with a pool-type nuclear fission reactor comprising: a pressure vessel defining a pool wall having an interior periphery, the pool wall being configured to confine a pool fluid therein; a nuclear fission reactor core disposed in said pressure vessel and capable of generating heat; a heat exchanger body capable of being in heat transfer communication with said nuclear fission reactor core, said heat exchanger body capable of being disposed in the pool fluid in proximity to the interior periphery of the pool wall, said heat exchanger body having a surface formed thereon defining a portion of a plenum volume therein shaped for predetermined flow of a heat transfer fluid into the plenum volume; and a plurality of adjacent heat transfer members coupled to said heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of said plurality of adjacent heat transfer members for distributing flow of a heat transfer fluid through the plurality of flow passages
  • a method of assembling a heat exchanger capable of being disposed in a pool fluid residing in the pool-type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid comprising: receiving a heat exchanger body; and coupling means to the heat exchanger body for removal of the heat.
  • a method of assembling a heat exchanger capable of being disposed in a pool fluid residing in the pool-type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid comprising receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a method of assembling a heat exchanger capable of being disposed in a pool fluid residing in the pool-type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid comprising: receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume; and coupling a heat transfer member to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a method of assembling a heat exchanger capable of being disposed in a pool fluid residing in the pool-type nuclear fission reactor, the heat exchanger capable of being disposed in proximity to an interior periphery of a pool wall confining the pool fluid comprising: receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume shaped for a predetermined flow of a heat transfer fluid into the plenum volume; and connecting a plurality of adjacent heat transfer members to the heat exchanger body, the plurality of adjacent heat transfer members being spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members for distributing flow of the heat transfer fluid through the plurality of flow passages.
  • a feature of the present disclosure is the provision of a heat exchanger body defining a chamber therein shaped for uniform flow of a heat transfer fluid through the chamber.
  • Another feature of the present disclosure is the provision of a plurality of adjacent heat transfer members connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between respective ones of the plurality of adjacent heat transfer members in order to evenly distribute flow of a heat transfer fluid through the plurality of flow passages!
  • FIG. 1 is a schematic representation of a nuclear fission reactor system
  • FIG. 2 is a view in horizontal section of an hexagonally-shaped nuclear fission reactor core containing a plurality of nuclear fission reactor modules and breeder fuel modules;
  • FIG. 3 is view in horizontal section of one of the plurality of nuclear fission reactor modules and a plurality of control rods therein;
  • FIG. 4 is an isometric view of a nuclear fuel rod, with parts removed for clarity;
  • FIG. 5 is a view in horizontal section of a parallelepiped-shaped nuclear fission reactor core containing a plurality of the nuclear fission reactor modules and breeder fuel modules;
  • FIG. 6 is a view in vertical section of three exemplary nuclear reactor fission modules with parts removed for clarity;
  • FIG. 7 is an isometric view of a heat exchanger
  • FIG. 8 is an isometric view of a heat exchanger in section and with parts shown in phantom;
  • FIG. 8 A is an isometric view of a heat exchanger in section and showing a guide structure
  • FIG. 9 is a view in vertical section of the heat exchanger, this view showing cross-flow of a primary heat transfer fluid and a secondary heat transfer fluid;
  • FIG. 9A is a view in vertical section of the heat exchanger, this view showing counter-flow of a primary heat transfer fluid and a secondary heat transfer fluid;
  • FIG. 9B is an exploded isometric illustration of the heat exchanger shown in Fig. 9A with parts removed for clarity, this view showing the counter- flow of a primary heat transfer fluid and a secondary heat transfer fluid;
  • FIG. 9C is a view in vertical section of the heat exchanger, this view showing parallel-flow of a primary heat transfer fluid and a secondary heat transfer fluid;
  • FIG. 9D is an exploded isometric illustration of the heat exchanger shown in Fig. 9C with parts removed for clarity, this view showing the parallel- flow of a primary heat transfer fluid and a secondary heat transfer fluid;
  • FIG. 10 is an isometric view of a heat transfer member having a plurality of fins on an exterior surface thereof;
  • FIG. 11 is an isometric view of a heat transfer member having a plurality of nodules on an exterior surface thereof;
  • FIG. 12 is an isometric view of a heat transfer member having a plurality of fins on an interior surface thereof;
  • FIG. 13 is a view in an isometric view of a heat transfer member defining a flow channel therethrough and a plurality of conduits disposed along the flow channel;
  • Fig. 13 A is an isometric view of a heat transfer member having wedge- shaped fins on an exterior surface thereof;
  • Fig. 13B is an isometric view of a heat transfer member having nodules of increasing density on an exterior surface thereof;
  • FIG. 14 is a schematic illustration of a plurality of heat exchangers disposed in a pressure vessel;
  • FIG. 15 is a view taken along section line 15-15 of Figure 14;
  • FIG. 16 is a view in horizontal section of a pressure vessel belonging to the nuclear fission reactor system, this view showing a plurality of contiguous heat exchangers disposed in the pressure vessel;
  • FIGS. 17 - 47 are flowcharts of illustrative methods, for use in association with a nuclear fission reactor, of assembling a heat exchanger.
  • the present application uses formal outline headings for clarity of presentation.
  • the outline headings are for presentation purposes, and that different types of subject matter may be discussed throughout the application (e.g., device(s)/structure(s) may be described under process(es)/operations heading(s) and/or process(es)/operations may be discussed under structure(s)/process(es) headings; and/or descriptions of single topics may span two or more topic headings).
  • the use of the formal outline headings is not intended to be in any way limiting.
  • any two components so associated can also be viewed as being “operably connected”, or “operably coupled,” to each other to achieve the desired functionality, and any two components capable of being so associated can also be viewed as being “operably couplable,” to each other to achieve the desired functionality.
  • operably couplable include but are not limited to physically mateable and/or physically interacting components, and/or wirelessly interactable, and/or wirelessly interacting components, and/or logically interacting, and/or logically interactable components.
  • one or more components may be referred to herein as “configured to,” “configurable to,” “operable/operative to,” “adapted/adaptable,” “able to,” “conformable/conformed to,” etc.
  • “configured to” can generally encompass active-state components and/or inactive-state components and/or standby-state components, unless context requires otherwise.
  • nuclear fission reactor system 10 may be a "traveling wave" nuclear fission reactor system.
  • Nuclear fission reactor system 10 generates electricity that is transmitted over a plurality of transmission lines (not shown) to users of the electricity.
  • Nuclear fission reactor system 10 alternatively may be used to conduct tests, such as tests to determine effects of temperature on reactor materials.
  • nuclear fission reactor system 10 comprises a nuclear fission reactor core, generally referred to as 20, that includes a plurality of nuclear fission fuel assemblies or, as also referred to herein, nuclear fission modules 30.
  • Nuclear fission reactor core 20 is sealingly housed within a reactor core enclosure 40.
  • each nuclear fission module 30 may form a hexagonally-shaped structure in transverse cross-section, as shown, so that more nuclear fission modules 30 may be closely packed together within reactor core 20, as compared to other shapes for nuclear fission module 30, such as cylindrical or spherical shapes.
  • Each nuclear fission module 30 comprises a plurality of fuel rods 50 for generating heat due to the aforementioned nuclear fission chain reaction process.
  • the plurality of fuel rods 50 may be surrounded by a fuel rod canister 60, if desired, for adding structural rigidity to nuclear fission modules 30 and for segregating nuclear fission modules 30 one from another when nuclear fission modules 30 are disposed in nuclear fission reactor core 20. Segregating nuclear fission modules 30 one from another avoids transverse coolant cross flow between fuel rods 50. Avoiding transverse coolant cross flow prevents transverse vibration of fuel rods 50. Such transverse vibration might otherwise increase risk of damage to fuel rods 50.
  • segregating nuclear fission modules 30 one from another can allow control of coolant flow on an individual module-by-module basis.
  • Controlling coolant flow to individual nuclear fission modules 30 efficiently manages coolant flow within reactor core 20, such as by directing coolant flow substantially according to the nonuniform temperature distribution in reactor core 20. In other words, more coolant may be directed to those nuclear fission modules 30 having higher temperature in order to provide a substantially uniform temperature distribution across reactor core 20.
  • the coolant may have an average nominal volumetric flow rate of approximately 5.5 m 3 /sec (i.e., approximately 194 cubic f Vsec) and an average nominal velocity of approximately 2.3 m/sec (i.e., approximately 7.55 ft/sec) in the case of an exemplary sodium cooled reactor during normal operation.
  • Fuel rods 50 are adjacent one to another and define a fuel rod coolant flow channel 80 (see Fig. 6) therebetween for allowing flow of coolant along the exterior of fuel rods 50.
  • Canister 60 may include means (not shown) for supporting and for tying fuel rods 50 together. Thus, fuel rods 50 are bundled together within canister 60 so as to form the previously mentioned hexagonal nuclear fission module 30.
  • fuel rods 50 are adjacent to each other, fuel rods 50 are nonetheless maintained in a spaced-apart relationship by a wire wrapper 90 (see Fig. 6) that surrounds and extends spirally along the length of each fuel rod 50 in a serpentine fashion, as well known by persons of ordinary skill in the art of nuclear power reactor design.
  • control rods 95 are each disposed within a control rod guide tube or cladding (not shown).
  • Control rods 95 are symmetrically disposed within selected nuclear fission modules 30 and extend the length of a predetermined number of nuclear fission modules 30.
  • Control rods 95 which are shown disposed in a predetermined number of the hexagonally-shaped nuclear fission modules 30, control the neutron fission reaction occurring in nuclear fission modules 30.
  • control rods 95 comprise a suitable neutron absorber material having an acceptably high neutron absorption cross-section.
  • the absorber material may be a metal or metalloid selected from the group consisting essentially of lithium, silver, indium, cadmium, boron, cobalt, hafnium, dysprosium, gadolinium, samarium, erbium, europium and mixtures thereof.
  • the absorber material may be a compound or alloy selected from the group consisting essentially of silver- indium-cadmium, boron carbide, zirconium diboride, titanium diboride, hafnium diboride, gadolinium titanate, dysprosium titanate and mixtures thereof.
  • Control rods 95 will controllably supply negative reactivity to reactor core 20.
  • control rods 95 provide a reactivity management capability to reactor core 20.
  • control rods 95 are capable of controlling the neutron flux profile across nuclear fission reactor core 20 and thus influence the temperature within nuclear fission reactor core 20.
  • each fuel rod 50 has a plurality of nuclear fuel pellets 100 stacked end-to-end therein, which nuclear fuel pellets 100 are sealingly surrounded by a fuel rod cladding material 1 10.
  • Nuclear fuel pellets 100 comprise the afore-mentioned fissile nuclide, such as uranium- 235, uranium-233 or plutonium-239.
  • nuclear fuel pellets 100 may comprise a fertile nuclide, such as thorium-232 and/or uranium-238 which may be transmuted via neutron capture during the fission process into the fissile nuclides mentioned immediately hereinabove.
  • Such fertile nuclide material may be housed in breeder rods disposed in specially designated breeder fuel modules 1 15.
  • breeder fuel modules 1 15 may be arranged as a "breeding blanket" around the interior periphery of nuclear fission reactor core 20 for breeding nuclear fuel, as well known in the art of fast neutron breeder reactor design.
  • nuclear fuel pellets 100 may comprise a predetermined mixture of fissile and fertile nuclides.
  • nuclear fuel pellets 100 may be made from an oxide selected from the group consisting essentially of uranium monoxide (UO), uranium dioxide (U0 2 ), thorium dioxide (Th0 2 ) (also referred to as thorium oxide), uranium trioxide (U0 3 ), uranium oxide-plutonium oxide (UO-PuO), triuranium octoxide (U 3 0 8 ) and mixtures thereof.
  • nuclear fuel pellets 100 may substantially comprise uranium either alloyed or unalloyed with other metals, such as, but not limited to, zirconium or thorium metal.
  • nuclear fuel pellets 100 may substantially comprise a carbide of uranium (UC X ) or a carbide of thorium (ThC x ).
  • nuclear fuel pellets 100 may be made from a carbide selected from the group consisting essentially of uranium monocarbide (UC), uranium dicarbide (UC 2 ), uranium sesquicarbide (U 2 C 3 ), thorium dicarbide (ThC 2 ), thorium carbide (ThC) and mixtures thereof.
  • nuclear fuel pellets 100 may be made from a nitride selected from the group consisting essentially of uranium nitride (U 3 N 2 ), uranium nitride-zirconium nitride (U 3 N 2 Zr 3 N 4 ), uranium-plutonium nitride ((U-Pu)N), thorium nitride (ThN) and mixtures thereof.
  • Fuel rod cladding material 1 10, which sealingly surrounds the stack of nuclear fuel pellets 100 may be a suitable zirconium alloy, such as ZIRCOLOYTM (trademark of the Westinghouse Electric Corporation), which has known resistance to corrosion and cracking.
  • Cladding material 1 10 may be made from other materials, as well, such as ferritic martensitic steels.
  • nuclear fission reactor core 20 is disposed within a vault or reactor pressure vessel 120 for preventing leakage of radioactive materials, gasses or liquids from reactor core 20 to the surrounding biosphere.
  • pressure vessel 120 which has an interior wall surface 122, is substantially filled with a pool of fluid or coolant 125, such as liquid sodium, to the extent nuclear fission reactor core 20 is submerged in the pool of coolant.
  • Pressure vessel 120 may be steel, concrete or other material of suitable size and thickness to reduce risk of such radiation leakage and to support required pressure loads.
  • a primary loop coolant pipe 130 is coupled to nuclear fission reactor core 20 for allowing a suitable coolant to flow through reactor core 20 along directional arrow 135 in order to cool nuclear fission reactor core 20.
  • Primary loop coolant pipe 130 may be made from any suitable material, such as stainless steel. It may be appreciated that, if desired, primary loop coolant pipe 130 may be made not only from ferrous alloys, but also from non-ferrous alloys, zirconium-based alloys or other suitable structural materials or composites.
  • the coolant carried by primary loop coolant pipe 130 may be a liquid metal selected from the group consisting essentially of sodium, potassium, lithium, lead and mixtures thereof.
  • the coolant may be a metal alloy, such as lead-bismuth (Pb-Bi).
  • the coolant is a liquid sodium (Na) metal or sodium metal mixture, such as sodium-potassium (Na-K).
  • Na sodium-potassium
  • normal operating temperature of a sodium-cooled reactor core may be relatively high.
  • the reactor core outlet temperature during normal operation may range from approximately 510° Celsius (i.e., 950° Fahrenheit) to approximately 550° Celsius (i.e., 1 ,020° Fahrenheit).
  • peak fuel cladding temperatures may reach about 600° Celsius (i.e. 1,1 10° Fahrenheit) or more, depending on reactor core design and operating history.
  • decay heat build-up during post-LOCA or post- LOFTA scenarios and also during suspension of reactor operations may produce unacceptable heat accumulation. In some cases, therefore, it is appropriate to remove heat produced by nuclear fission reactor core 20 during both normal operation and post accident scenarios.
  • the heat-bearing coolant generated by nuclear fission reactor core 20 flows along a coolant flow stream or flow path 140 to an intermediate heat exchanger 150 that is also submerged in coolant pool 125.
  • Intermediate heat exchanger 150 may be made from any convenient material resistant to the heat and corrosive effects of the sodium coolant in coolant pool 125, such as a suitable stainless steel.
  • the coolant flowing along coolant flow path 140 flows through intermediate heat exchanger 150, as described more fully hereinbelow, and continues through primary loop coolant pipe 130. It may be appreciated that the coolant leaving intermediate heat exchanger 150 has been cooled due to the heat transfer occurring in intermediate heat exchanger 150, as disclosed more fully hereinbelow.
  • a first pump 170 which may be an electromechanical pump, is coupled to primary loop pipe 130, and is in fluid communication with the reactor coolant carried by primary loop coolant pipe 130, for pumping the reactor coolant through primary loop pipe 130, through reactor core 20, along coolant flow path 140 and into intermediate heat exchanger 150.
  • Secondary loop pipe 180 is provided for removing heat from intermediate heat exchanger 150.
  • Secondary loop pipe 180 comprises a secondary "hot" leg pipe segment 190 and a secondary "cold” leg pipe segment 200.
  • Secondary hot leg pipe segment 190 and secondary cold leg pipe segment 200 are integrally connected to intermediate heat exchanger 150.
  • Secondary loop pipe 180 which includes hot leg pipe segment 190 and cold leg pipe segment 200, contains a fluid, such as a liquid metal selected from the group consisting essentially of sodium, potassium, lithium, lead and mixtures thereof.
  • the fluid may be a metal alloy, such as lead-bismuth (Pb-Bi).
  • the fluid may suitably be a liquid sodium (Na) metal or sodium metal mixture, such as sodium- potassium (Na-K).
  • Secondary hot leg pipe segment 190 extends from intermediate heat exchanger 150 to a steam generator and superheater combination 210 (hereinafter referred to as "steam generator 210"), for reasons described momentarily.
  • steam generator 210 a steam generator and superheater combination 210
  • the coolant flowing through secondary loop pipe 180 and exiting steam generator 210 is at a lower temperature and enthalpy than before entering steam generator 210 due to the heat transfer occurring within steam generator 210.
  • steam generator 210 After passing through steam generator 210, the coolant is pumped, such as by means of a second pump 220, which may be an electro-mechanical pump, along "cold" leg pipe segment 200, which extends into intermediate heat exchanger 150 for providing the previously mentioned heat transfer.
  • a second pump 220 which may be an electro-mechanical pump
  • leg pipe segment 200 which extends into intermediate heat exchanger 150 for providing the previously mentioned heat transfer.
  • disposed in steam generator 210 is a body of water 230 having a predetermined temperature and pressure.
  • the fluid flowing through secondary hot leg pipe segment 190 will transfer its heat by means of conduction to body of water 230, which is at a lower temperature than the fluid flowing through secondary hot leg pipe segment 190.
  • Steam 240 will then travel through a steam line 250 which has one end thereof in vapor communication with steam 240 and another end thereof in liquid communication with body of water 230.
  • a rotatable turbine 260 is coupled to steam line 250, such that turbine 260 rotates as steam 240 passes therethrough.
  • An electrical generator 270 which is coupled to turbine 260, such as by a rotatable turbine shaft 280, generates electricity as turbine 260 rotates.
  • a condenser 290 is coupled to steam line 250 and receives the steam passing through turbine 260. Condenser 290 condenses the steam to liquid water and passes any waste heat to a heat sink, such as a cooling tower 300, which is associated with condenser 290.
  • the liquid water condensed by condenser 290 is pumped along steam line 250 from condenser 290 to steam generator 210 by means of a third pump 310, which may be an electro-mechanical pump, interposed between condenser 290 and steam generator 210.
  • a third pump 310 which may be an electro-mechanical pump, interposed between condenser 290 and steam generator 210.
  • nuclear fission modules 30 may be arranged to define a parallelepiped-shaped nuclear fission reactor core configuration, generally referred to as 222 rather than the previously mentioned hexagonally- shaped configuration.
  • reactor core enclosure 40 of nuclear fission reactor core 222 defines a first end 330 and a second end 340, for reasons provided hereinbelow.
  • the nuclear fission reactor core 20 or 222 may be configured as a traveling wave nuclear fission reactor core.
  • a comparatively small and removable nuclear fission igniter 350 which may include isotopic enrichment of nuclear fissionable material, such as, without limitation, U-233, U-235 or Pu-239, is suitably located in reactor core 222.
  • igniter 350 may be located near first end 330 that is opposite second end 340 of reactor core 340. Neutrons are released by igniter 350.
  • igniter 350 initiates a three-dimensional, traveling deflagration wave or "burn wave” 360.
  • burn wave 360 travels outwardly from igniter 350 that is near first end 330 and toward second end 340 of reactor core 222, so as to form the traveling or propagating burn wave 360.
  • each nuclear fission module 30 is capable of accepting at least a portion of traveling burn wave 360 as burn wave 360 propagates through reactor core 222.
  • Speed of the traveling burn wave 360 may be constant or non-constant.
  • the speed at which burn wave 360 propagates can be controlled.
  • longitudinal movement of the previously mentioned control rods 95 (see Fig. 3) in a predetermined or programmed manner can drive down or lower neutronic reactivity of fuel rods 50 that are disposed in nuclear fission modules 30.
  • neutronic reactivity of fuel rods 50 that are presently being burned at the location of burn wave 360 is driven down or lowered relative to neutronic reactivity of "unburned" fuel rods 50 ahead of burn wave 360.
  • FIG. 6 there are shown upright, adjacent hexagonally-shaped nuclear fission modules 30. Only three adjacent nuclear fission modules 30 are shown, it being understood that a greater number of nuclear fission modules 30 are present in reactor core 20.
  • Each nuclear fission module 30 is mounted on a horizontally extending reactor core lower support plate 370.
  • Reactor core lower support plate 370 suitably extends across a bottom end portion of all nuclear fission modules 30.
  • Reactor core lower support plate 370 has a counter bore 380 therethrough for reasons provided hereinbelow.
  • Counter bore 380 has an open end 390 for allowing flow of coolant thereinto.
  • reactor core upper support plate 400 Horizontally extending across a top end portion or exit portion of all nuclear fission modules 30 and removably connected to nuclear fission modules 30 is a reactor core upper support plate 400 that caps all nuclear fission modules 30.
  • Reactor core upper support plate 400 also defines a plurality of flow slots 410 for allowing flow of coolant therethrough.
  • Primary loop pipe 130 and first pump 170 (see Fig. 1) deliver reactor coolant to nuclear fission modules 30 along a coolant flow path or fluid stream indicated by directional arrows 140. The primary coolant then continues along coolant flow path 140 and through open end 390 that is formed in lower support plate 370.
  • nuclear fission reactor core 20 it is important to remove the heat produced by nuclear fission reactor core 20 and the nuclear fission modules 30 therein, regardless of the configuration selected for nuclear fission reactor core 20.
  • Proper heat removal is important for several reasons. For example, heat damage may occur to reactor core structural materials if the peak temperature exceeds material limits. Such peak temperatures may undesirably reduce the operational life of structures subjected to peak temperatures by altering the mechanical properties of the structures, particularly those properties relating to thermal creep. Also, reactor power density is limited by the ability of core structural materials to withstand high peak temperatures without damage.
  • nuclear fission reactor system 10 alternatively may be used to conduct tests, such as tests to determine effects of temperature on reactor materials. Controlling reactor core temperature by properly removing the heat from the reactor core is important for successfully conducting such tests.
  • intermediate heat exchanger 150 it may be desirable to achieve uniform flow rate of the heat transfer fluid through intermediate heat exchanger 150. Such uniform flow rate may otherwise avoid uneven coolant flow to the nuclear reactor core and resulting core reactivity perturbations. Further, it may be desirable to provide uniform distribution of coolant flow through the heat exchanger in order to avoid preferential flow of the coolant through the heat exchanger. Avoidance of preferential flow of the coolant can mitigate development of localized temperature "hot spots" in the heat exchanger. Such localized temperature "hot spots” might otherwise decrease the operational life of the heat exchanger. Uniform flow also acts to enhance heat exchange evenly across the heat transfer surfaces of the heat exchanger, enhancing heat exchange for a given heat exchange area. The structure and operation of intermediate heat exchanger 150 addresses these concerns.
  • intermediate heat exchanger 150 comprises a heat exchanger body 420 affixed to interior wall surface 122 of pressure vessel 120, so that intermediate heat exchanger 150 is supported within pressure vessel 120.
  • interior wall surface 122 with confines pool 125, may form a rear wall of intermediate heat exchanger 150.
  • Heat exchanger body 420 comprises an upright generally L-shaped (in transverse cross section) rear portion 425 that defines a primary fluid exit plenum volume or exit plenum chamber 430 therein.
  • primary fluid exit plenum chamber 430 is a part of heat exchanger body 420.
  • Primary fluid exit plenum chamber 430 is shaped to provide uniform flow of a first heat transfer fluid (i.e., the primary heat transfer fluid) through primary fluid exit plenum chamber 430, as described in more detail hereinbelow.
  • a first heat transfer fluid i.e., the primary heat transfer fluid
  • a bottom portion 440 of heat exchanger body 420 Connected to rear portion 425 is a bottom portion 440 of heat exchanger body 420 defining a bottom plenum 450 for hot secondary sodium.
  • Bottom plenum 450 which has a bottom plenum exit side or port 455, forms a box-like structure having a top surface 460 thereon to which a plurality of upright plate-type heat transfer members 470 are integrally attached, such as by welding.
  • Each heat transfer member 470 defines a flow channel 480 therethrough that has an inlet 490 and an outlet 500 at respective ends of flow channel 460.
  • Inlet 490 is in fluid communication with heat transfer fluid flowing through cold leg pipe segment 200.
  • Outlet 500 is in fluid communication with heat transfer fluid in bottom plenum 450.
  • the primary fluid is supplied to heat exchanger body 420 without use of a conduit or manifold.
  • the primary fluid is supplied to heat exchanger body 420 conduit- free or manifold-free. It may be appreciated that pool 125 is also manifold-free. In addition, it may be appreciated that the inlet side of intermediate exchanger 150 may be manifold-free and the outlet side of intermediate exchanger 150 may be manifold-free, as well. This may decrease capital cost of constructing reactor 10 and/or fabrication cost of heat exchanger 150 because such a conduit or manifold is not required.
  • intermediate heat exchanger 150 comprises a plurality of adjacent heat transfer members 470.
  • the plurality of adjacent heat transfer members 470 are spaced-apart by a relatively small predetermined distance "d" for defining a plurality of flow passages 510 between the adjacent heat transfer members 470.
  • the distance "d" is that distance necessary for achieving even flow distribution among flow passages 510.
  • heat transfer members 470 are spaced-apart by distance "d” in order to evenly distribute flow of the primary heat transfer fluid through a plurality of flow passages 510.
  • heat exchanger body 420 may comprise a guide structure 515 for guiding flow of the heat transfer fluid into heat exchanger 150.
  • Guide structure 515 suitably spans heat transfer members 470 and is associated with flow passages 510 such that the heat transfer fluid is guided into flow passages 510.
  • Heat exchanger body 420 further comprises a top portion 520 sealingly mounted on or connected to an upper portion of rear portion 425 and an upper portion of the plurality of heat transfer members 470.
  • Top portion 520 defines a top plenum 530 therein for receiving cooled secondary sodium flowing along flow path 532 from steam generator 210.
  • the cooled secondary sodium flowing along flow path 532 and the primary heat transfer fluid flowing along flow path 140 define a cross-flow configuration.
  • flow path 532 is substantially perpendicular (i.e., plus or minus 45°) to flow path 140 in intermediate heat exchanger 150.
  • Top plenum 530 is in communication with inlet 490 for allowing the cooled secondary sodium to flow through inlet 490, into flow channel 470, through outlet 500 and into bottom plenum 450.
  • an alternative embodiment intermediate heat exchanger 150 comprises cold leg pipe segment 200 through which the cooled secondary heat transfer fluid flows along flow path 532.
  • cooled secondary heat transfer fluid enters a plate member 534 through an opening 536a and exits an opening 536b that are formed in plate member 534.
  • the secondary heat transfer fluid continues along flow path 532 and enters return pipe segment 538 for returning the secondary heat transfer fluid to steam generator 210.
  • the cooled secondary sodium flowing along flow path 532 and the primary heat transfer fluid flowing along flow path 140 define a counter-flow configuration. In this counter-flow configuration, flow path 532 is parallel, but opposite, to flow path 140 in intermediate heat exchanger 150.
  • an alternative embodiment intermediate heat exchanger 150 comprises cold leg pipe segment 200 through which the cooled secondary heat transfer fluid flows along flow path 532.
  • cooled secondary heat transfer fluid enters plate member 534 through an opening 536a and exits an opening 536b that are formed in plate member 534.
  • the secondary heat transfer fluid continues along flow path 532 and enters a return pipe segment 538 for returning the secondary heat transfer fluid to steam generator 210.
  • the cooled secondary heat transfer fluid flowing along flow path 532 and the primary heat transfer fluid flowing along flow path 140 define a parallel-flow configuration. In this parallel-flow configuration, flow path 532 is parallel and in the same direction to flow path 140 in intermediate heat exchanger 150.
  • At least one of plurality of heat transfer members 470 comprises a wall 540 defining an enhanced heat transfer surface 550 that accommodates flow of the primary heat transfer fluid along enhanced heat transfer surface 550.
  • wall 540 separates hot primary sodium (i.e., a first heat transfer fluid) from cool secondary sodium (i.e., a second heat transfer fluid).
  • At least one of plurality of heat transfer members 470 comprises at least one integrally connected external fin or external flange 560 outwardly extending from wall 540 for forming enhanced heat transfer surface 550. External flange 560 enhances heat transfer by increasing the surface area for increased heat transfer.
  • At least one of plurality of heat transfer members 470 comprises at least one nodule 570 outwardly projecting from wall 540 for forming enhanced heat transfer surface 550.
  • Nodule 570 enhances heat transfer by increasing the surface area for increased heat transfer.
  • at least one of plurality of heat transfer members 470 comprises at least one integrally connected internal fin or internal flange 580 inwardly extending from wall 540 for purposes of enhanced heat transfer. Internal flange 580 enhances heat transfer by increasing the surface area for increased heat transfer.
  • at least one of plurality of heat transfer members 470 comprises at least one conduit 590 extending along flow channel 490 for accommodating flow of cooled heat transfer fluid through conduit 590.
  • Figs. 13A and 13B present further embodiments that include enhanced heat transfer surface 550.
  • external flange 560 may have increasing heat transfer surface area as flange 560 extends from a forward portion 592 of wall 540 to a rearward portion 594 of wall 540.
  • a greater portion of heat transfer will occur nearer forward portion 592 of wall 540 than nearer rearward portion 594 of wall 540 because the primary heat transfer fluid flows from forward portion 592 of wall 540 to rearward portion 594 of wall 540.
  • more heat transfer will occur nearer forward portion 592 of wall 540 and a reduced amount of heat transfer will occur nearer rearward portion 594 of wall 540.
  • the heat transfer surface area of flange 560 increases as flange 560 extends from forward portion 592 of flange 560 to rearward portion 594 of flange 560.
  • flange 560 may be wedge-shaped with a smaller end portion thereof near forward portion 592 and a wider end portion thereof near rearward portion 594.
  • density of nodules 570 i.e., number of nodules 570 per unit area
  • density of nodules 570 that outwardly project from wall 540 may increase from forward portion 592 to rearward portion 594 for increasing heat transfer surface area from forward portion 592 of wall 540 to rearward portion 594 of wall 540. This configuration of nodules 570 compensates for the reduced heat transfer occurring near rearward portion 594 of wall 540.
  • FIGs. 14 and 15 there is shown an alternative embodiment of nuclear fission reactor system 10, wherein there are a plurality of heat exchangers, such as a first heat exchanger 600 and a second heat exchanger 610.
  • first heat exchanger 600 and second heat exchanger 610 is coupled to steam generator 210 by a first cold leg pipe segment 620a and a second cold leg pipe segment 620b, respectively, that supply cooled heat transfer fluid to heat exchangers 600/610.
  • each of first heat exchanger 600 and second heat exchanger 610 is coupled to steam generator 210 by a first hot leg pipe segment 630a and a second hot leg pipe segment 630b, respectively, that allow extraction of heated heat transfer fluid from heat exchangers 600/610.
  • shut-off valve 640a installed in first cold leg pipe segment 620a and a second shut-off valve 640b installed in second cold leg pipe segment 620b for reasons described presently.
  • first shut-off valve 640a installed in first cold leg pipe segment 620a and a second shut-off valve 640b installed in second cold leg pipe segment 620b for reasons described presently.
  • third shut-off valve 650a installed in first hot leg pipe segment 630a and a fourth shut-off valve 650b installed in hot leg pipe segment 630b for reasons described presently.
  • shut-off valves 640a/650a can be closed to cease coolant flow to and from first heat exchanger 600 and thereby isolate first heat exchanger 600.
  • shut-off valves 640b/650b can be closed to cease coolant flow to and from second heat exchanger 610 and thereby isolate second heat exchanger 610. It may be desirable to isolate either first heat exchanger 600 or second heat exchanger 610 if a leak occurs in wall 540 of any of heat transfer members 470.
  • a plurality of pumps such as pumps 660a and 660b, are coupled to respective ones of plurality of heat exchangers 600 and 610 for pumping cooled heat transfer fluid from heat exchangers 600 and 610 to nuclear fission reactor core 20.
  • FIG. 16 there is show an embodiment, wherein a plurality of heat exchangers 670a, 670b, 670c, 670d, 670e, 670f and 670g are arranged side- by-side or contiguously around interior wall surface 122 of pressure vessel 120.
  • This embodiment provides another configuration for using intermediate heat exchanger 150.
  • first pump 170 is operated to suction or draw the first heat transfer fluid from heat exchanger 150 and then pump the first heat transfer fluid past fuel rods 50, through flow slots 410 in upper core support plate 400 and into coolant pool 125. Continued operation of first pump 170 will then draw the first heat transfer fluid through flow passages 510 and into primary fluid exit plenum chamber 430.
  • the first heat transfer fluid As the first heat transfer fluid flows through flow passages 510, the first heat transfer fluid will come into intimate contact with enhanced heat transfer surface 550. As the first heat transfer fluid flows in intimate contact with enhanced heat transfer surface 550, cooler secondary heat transfer fluid flows from steam generator 210, along cold pipe segment 200, into top plenum 530, through inlet 490, through flow channel 480, through outlet 500 and into bottom plenum 450. Thereafter, the second heat transfer fluid exits bottom plenum 450 through exit port 455 to be received by hot leg pipe segment 190 that passes through steam generator 210. The second heat transfer fluid that travels along the portion of hot leg pipe segment 190 and that passes through steam generator 210 transfers its heat to body of water 230 for generating steam 240. Second pump 220 is operated to bring the cooler secondary fluid from steam generator 210 to top plenum 520.
  • the plurality of adjacent heat transfer members 470 are spaced-apart by the previously mentioned predetermined distance "d” in order to evenly distribute flow of the primary heat transfer fluid through plurality of flow passages 510.
  • primary fluid exit plenum chamber 430 is shaped to provide uniform flow of a first heat transfer fluid (i.e., the primary heat transfer fluid) through primary fluid exit plenum chamber 430.
  • a first heat transfer fluid i.e., the primary heat transfer fluid
  • an upper portion of primary fluid exit plenum chamber 430 is disposed closer to interior wall surface 122, so that primary fluid exit plenum chamber 430 has a smaller volume than a lower portion of primary fluid exit plenum chamber 430.
  • volume of primary fluid exit plenum chamber 430 becomes greater nearer exit port 435 than inlet 490.
  • This shape for primary fluid exit plenum 430 provides uniform flow of the first heat transfer fluid (i.e., the primary heat transfer fluid) through primary fluid exit plenum chamber 430.
  • FIG. 17 - 47 illustrative methods, for use in association with a nuclear fission reactor capable of generating heat, are provided for assembling a heat exchanger.
  • an illustrative method 680 of assembling a heat exchanger starts at a block 690.
  • the method comprises receiving a heat exchanger body.
  • means is coupled to the heat exchanger body for removal of the heat.
  • the method stops at block 720.
  • an illustrative method 730 of assembling a heat exchanger starts at block 740.
  • the method comprises receiving a heat exchanger body.
  • the method comprises coupling means to the heat exchanger body for removal of the heat.
  • the method comprises coupling a heat removal means configured to achieve a predetermined flow of a heat transfer fluid into the heat exchanger body. The method stops at block 780.
  • an illustrative method 790 of assembling a heat exchanger starts at a block 800.
  • the method comprises receiving a heat exchanger body.
  • means is coupled to the heat exchanger body for removal of the heat.
  • a heat removal means is coupled that is configured to achieve a predetermined flow of a heat transfer fluid into the heat exchanger body.
  • a heat removal means is coupled that is configured to achieve a substantially uniform flow of a heat transfer fluid into the heat exchanger body. The method stops at a block 850.
  • an illustrative method 860 of assembling a heat exchanger starts at a block 870.
  • the method comprises receiving a heat exchanger body.
  • means is coupled to the heat exchanger body for removal of the heat.
  • a heat removal means having an enhanced heat transfer surface is coupled. The method stops at a block 910.
  • an illustrative method 920 of assembling a heat exchanger starts at a block 930.
  • means is coupled to the heat exchanger body for removal of the heat.
  • a heat exchanger body defining a plenum volume therein of predetermined shape is received for achieving a substantially uniform flow of the heat transfer fluid through the heat exchanger body. The method stops at a block 970.
  • an illustrative method 971 for use in association with a pool-type nuclear fission reactor capable of generating heat, an illustrative method 971 , of assembling a heat exchanger starts at a block 973.
  • the method comprises receiving a heat exchanger body.
  • means are coupled to the heat exchanger body for removal of the heat.
  • a manifold-free heat exchanger body is received. The method stops at a block 979.
  • an illustrative method 980 of assembling a heat exchanger starts at a block 990.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • the method stops at a block 1010.
  • an illustrative method 1011a for use in association with a pool-type nuclear fission reactor capable of generating heat, an illustrative method 1011a, of assembling a heat exchanger starts at a block 1013a.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a guide structure for guiding flow of the pool fluid is received. The method stops at a block 1019a.
  • an illustrative method 101 1b of assembling a heat exchanger starts at a block 1013b.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a guide structure for guiding flow of the pool fluid is received.
  • a guide structure configured for achieving substantially uniform flow of the pool fluid within at least a portion of the heat exchanger body is received. The method stops at a block 1019b.
  • an illustrative method 1011c for use in association with a pool-type nuclear fission reactor capable of generating heat, an illustrative method 1011c, of assembling a heat exchanger starts at a block 1013c.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a heat exchanger body having an inlet guide structure for guiding inlet flow of the pool fluid is received. The method stops at a block 1019c.
  • an illustrative method 101 Id of assembling a heat exchanger starts at a block 1013d.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a heat exchanger body having an outlet guide structure for guiding outlet flow of the pool fluid is received. The method stops at a block 1019d.
  • an illustrative method 101 le of assembling a heat exchanger starts at a block 1013e.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a guide structure for preventing contact of the pool fluid with the pool wall is received, the pool fluid being disposed within at least a portion of the heat exchanger body. The method stops at a block 1019e.
  • an illustrative method 1020 of assembling a heat exchanger starts at a block 1030.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a reactor vessel defining a portion of an outlet plenum volume of non-uniform shape is received. The method stops at a block 1060.
  • an illustrative method 1070 of assembling a heat exchanger starts at block 1080.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • a heat exchanger body is received that is capable of being in heat transfer communication with a nuclear fission reactor core. The method stops at a block 1 1 10.
  • an illustrative method 1120 of assembling a heat exchanger starts at a block 1 130.
  • the method comprises receiving a heat exchanger body having a surface formed thereon defining a portion of a plenum volume.
  • the method comprises receiving a manifold-free heat exchanger body. The method stops at a block 1 160.
  • an illustrative method 1 170 of assembling a heat exchanger starts at a block 1 180.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough. The method stops at a block 1210.
  • an illustrative method 1220 of assembling a heat exchanger starts at a block 1230.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a heat transfer member is coupled that is configured to achieve a predetermined flow of a heat transfer fluid into the heat exchanger body. The method stops at a block 1270.
  • an illustrative method 1280 of assembling a heat exchanger starts at a block 1290.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a heat transfer member is coupled that is configured to achieve a predetermined flow of a heat transfer fluid into the heat exchanger body.
  • a heat transfer member is coupled that is configured to achieve a substantially uniform flow of a heat transfer fluid into the heat exchanger body. The method stops at a block 1340.
  • an illustrative method 1350 of assembling a heat exchanger starts at a block 1360.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a heat transfer member is coupled having a conduit extending along the flow channel. The method stops at a block 1400.
  • an illustrative method 1410 of assembling a heat exchanger starts at a block 1420.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a heat exchanger body is received that is capable of being in heat transfer communication with a nuclear fission reactor core. The method stops at a block 1460.
  • an illustrative method 1470 of assembling a heat exchanger starts at a block 1480.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a heat exchanger body is received that is capable of being in heat transfer communication with a traveling wave nuclear fission reactor core.
  • a heat exchanger body capable of being in heat transfer communication with a traveling wave nuclear fission reactor core is received. The method stops at a block 1520.
  • an illustrative method 1521 of assembling a heat exchanger starts at a block 1523.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a manifold-free heat exchanger body is received. The method stops at a block 1529.
  • an illustrative method 1530 of assembling a heat exchanger starts at a block 1540.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a heat transfer member is coupled to the heat exchanger body, the heat transfer member defining a flow channel therethrough.
  • a heat transfer member is coupled having a wall defining an enhanced heat transfer surface thereon. The method stops at a block 1580.
  • an illustrative method 1650 of assembling a heat exchanger starts at a block 1660.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • the method stops at a block 1690.
  • an illustrative method 1700 of assembling a heat exchanger starts at a block 1710.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a plurality of adjacent heat transfer members configured to achieve a uniform flow of the heat transfer fluid into the heat exchanger body are connected. The method stops at a block 1750.
  • an illustrative method 1760 of assembling a heat exchanger starts at a block 1770.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a reactor vessel is received defining a portion of an outlet plenum volume of non-uniform shape. The method stops at a block 1810.
  • an illustrative method 1820 of assembling a heat exchanger starts at a block 1830.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a heat exchanger body is received that is capable of being in heat transfer communication with a nuclear fission reactor core. The method stops at a block 1870.
  • an illustrative method 1880 of assembling a heat exchanger starts at a block 1890.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a heat exchanger body capable of being in heat transfer communication with a nuclear fission reactor core is received.
  • a heat exchanger body is received that is capable of being in heat transfer communication with a traveling wave nuclear fission reactor core. The method stops at a block 1930.
  • an illustrative method 1940 of assembling a heat exchanger starts at a block 1950.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a block 1980 at least two heat transfer fluids having a cross-flow orientation are accommodated. The method stops at a block 1990.
  • an illustrative method 2000 of assembling a heat exchanger starts at a block 2010.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a block 2040 at least two heat transfer fluids having a counter-flow orientation are accommodated. The method stops at a block 2050.
  • an illustrative method 2060 of assembling a heat exchanger starts at a block 2070.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a block 2100 at least two heat transfer fluids having a parallel-flow orientation are accommodated. The method stops at a block 21 10.
  • an illustrative method 2120 of assembling a heat exchanger starts at a block 2130.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • at least one of the plurality of adjacent heat transfer members is coupled having a wall defining an enhanced heat transfer surface thereon for increased heat transfer through the wall. The method stops at a block 2170.
  • an illustrative method 2180 of assembling a heat exchanger starts at a block 2190.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • at least one of the plurality of adjacent heat transfer members is coupled having a wall defining an enhanced heat transfer surface thereon for increased heat transfer through the wall.
  • at least one of the plurality of adjacent heat transfer members is coupled having a flange outwardly extending from the wall for forming the enhanced heat transfer surface. The method stops at a block 2240.
  • an illustrative method 2250 of assembling a heat exchanger starts at a block 2260.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • at least one of the plurality of adjacent heat transfer members is coupled having a wall defining an enhanced heat transfer surface thereon for increased heat transfer through the wall.
  • at least one of the plurality of adjacent heat transfer members is coupled having a flange inwardly extending from the wall for forming the enhanced heat transfer surface. The method stops at a block 2310.
  • an illustrative method 2320 of assembling a heat exchanger starts at a block 2330.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • at least one of the plurality of adjacent heat transfer members is coupled having a wall defining an enhanced heat transfer surface thereon for increased heat transfer through the wall.
  • at least one of the plurality of adjacent heat transfer members is coupled having a nodule outwardly projecting from the wall for forming the enhanced heat transfer surface. The method stops at a block 2380.
  • an illustrative method 2390 of assembling a heat exchanger starts at a block 2400.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a heat transfer member is coupled having a conduit extending along a flow channel for flow of the second heat transfer fluid through the conduit. The method stops at a block 2440.
  • an illustrative method 2450 of assembling a heat exchanger starts at a block 2460.
  • the method comprises receiving a heat exchanger body defining a plenum volume therein shaped for a predetermined flow of a heat transfer fluid into the plenum volume, the heat exchanger body having a surface formed thereon defining a portion of the plenum volume.
  • a plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between opposing ones of the plurality of adjacent heat transfer members to distribute flow of the heat transfer fluid through the plurality of flow passages.
  • a manifold-free heat exchanger body is received. The method stops at a block 2500.
  • shut-off valves 640a/640b/650a/650b may each be coupled to respective ones of a plurality of thermocouples (not shown) disposed in pipes 620a/620b/630a/630b.
  • a controller could selectively and progressively open and close the shut-off valves depending on the temperature of the heat transfer fluid entering and leaving heat exchangers 600/610. That is, the amount heat transfer that is desired within the heat exchangers as a function of temperature sensed by the thermocouples could be preprogrammed into and stored in the controller.
  • thermocouples The temperatures within the heat exchangers could be detected by the controller via the thermocouples and the controller could then operate the shut-off valves by progressively opening and closing the shut-off valves to bring the heat transfer occurring within the heat exchangers into substantial agreement with the preprogrammed value stored within the controller.
  • heat exchangers 600/610 could be selectively operated to provide precise amounts of heat transfer within the heat exchangers by allowing the controller to automatically adjust the valves.

Landscapes

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

Abstract

L'invention concerne un échangeur thermique, des procédés apparentés et un système de réacteur à fission nucléaire. L'échangeur thermique comprend un corps formant un plenum de sortie configuré pour un écoulement uniforme d'un fluide de transfert thermique primaire chaud dans la chambre. Une pluralité d'éléments de transfert thermique adjacents sont reliés au corps de l'échangeur thermique et sont espacés sur une distance prédéterminée pour définir une pluralité de voies d'écoulement entre les éléments de transfert thermique. Les voies d'écoulement donnent sur le plenum de sortie. L'espacement des éléments de transfert thermique sur une distance prédéterminée répartit uniformément l'écoulement de fluide de transfert thermique primaire dans les voies d'écoulement, à travers les surfaces des éléments de transfert thermique et à l'intérieur du plenum de sortie. Chaque élément de transfert thermique forme un canal d'écoulement pour l'écoulement d'un flux de transfert thermique secondaire plus froid. Le transfert thermique s'effectue du fluide de transfert thermique primaire chaud au fluide de transfert thermique secondaire plus froid lorsque le fluide de transfert thermique primaire s'écoule dans la chambre et que le fluide de transfert thermique secondaire s'écoule simultanément dans le canal d'écoulement.
EP10839921A 2009-09-25 2010-09-22 Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire Withdrawn EP2481054A2 (fr)

Applications Claiming Priority (4)

Application Number Priority Date Filing Date Title
US12/586,741 US20110075786A1 (en) 2009-09-25 2009-09-25 Heat exchanger, methods therefor and a nuclear fission reactor system
US12/653,653 US20110075787A1 (en) 2009-09-25 2009-12-15 Heat exchanger, methods therefor and a nuclear fission reactor system
US12/653,656 US9275760B2 (en) 2009-09-25 2009-12-15 Heat exchanger, methods therefor and a nuclear fission reactor system
PCT/US2010/002603 WO2011078871A2 (fr) 2009-09-25 2010-09-22 Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire

Publications (1)

Publication Number Publication Date
EP2481054A2 true EP2481054A2 (fr) 2012-08-01

Family

ID=44196378

Family Applications (3)

Application Number Title Priority Date Filing Date
EP10839920A Withdrawn EP2481053A4 (fr) 2009-09-25 2010-09-22 Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire
EP10839922A Withdrawn EP2481055A2 (fr) 2009-09-25 2010-09-22 Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire
EP10839921A Withdrawn EP2481054A2 (fr) 2009-09-25 2010-09-22 Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire

Family Applications Before (2)

Application Number Title Priority Date Filing Date
EP10839920A Withdrawn EP2481053A4 (fr) 2009-09-25 2010-09-22 Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire
EP10839922A Withdrawn EP2481055A2 (fr) 2009-09-25 2010-09-22 Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire

Country Status (7)

Country Link
EP (3) EP2481053A4 (fr)
JP (3) JP2013506130A (fr)
KR (3) KR20120083432A (fr)
CN (3) CN102667954A (fr)
GB (3) GB2485754A (fr)
RU (3) RU2012113142A (fr)
WO (3) WO2011078870A2 (fr)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103426486B (zh) * 2013-08-06 2015-12-30 华北电力大学 自然循环多功能气体抬升器装置
CN103839600B (zh) * 2014-03-18 2016-03-02 中国科学院合肥物质科学研究院 一种用于池式自然循环反应堆的流量测量装置及测量方法
US11034796B1 (en) 2015-08-06 2021-06-15 Cornell University Poly(arylamine)s and uses thereof
US10446284B2 (en) * 2016-06-01 2019-10-15 Terrapower, Llc Instrumentation conduit housing
CN107145175B (zh) * 2017-05-26 2020-11-06 中国核动力研究设计院 一种蒸汽发生器给水温度控制模拟系统

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1322221A (en) * 1970-02-06 1973-07-04 Atomic Energy Authority Uk Valves self closable in the event of reverse flow particularly for fast-fission liquid metal cooled fast reactors
FR2350566A1 (fr) * 1976-05-04 1977-12-02 Commissariat Energie Atomique Echangeur de chaleur
FR2524687B1 (fr) * 1982-04-01 1988-03-18 Commissariat Energie Atomique Reacteur nucleaire a neutrons rapides
JPS5935782A (ja) * 1982-08-20 1984-02-27 Toshiba Corp 高速炉用熱交換器
US4560533A (en) * 1984-08-30 1985-12-24 The United States Of America As Represented By The United States Department Of Energy Fast reactor power plant design having heat pipe heat exchanger
US4737337A (en) * 1985-05-09 1988-04-12 Stone & Webster Engineering Corporation Nuclear reactor having double tube helical coil heat exchanger
US4983353A (en) * 1989-03-13 1991-01-08 General Electric Company Novel passive approach to protecting the primary containment barrier formed by the intermediate heat exchanger from the effects of an uncontrolled sodium water reaction
EP0667623A1 (fr) * 1994-02-14 1995-08-16 FINMECCANICA S.p.A. AZIENDA ANSALDO Un système pour l'évacuation passive de la chaleur de l'intérieur de la structure de confinement d'un réacteur nucléaire
US5499277A (en) * 1994-08-19 1996-03-12 General Electric Company Method and apparatus for enhancing reactor air-cooling system performance
US6916430B1 (en) * 1996-10-25 2005-07-12 New Qu Energy Ltd. Superconducting heat transfer medium
CN1141213C (zh) * 1996-10-25 2004-03-10 渠玉芝 超导传热介质及其制备方法与超导传热装置
GB9926466D0 (en) * 1999-11-10 2000-01-12 Chart Marston Limited Heat exchanger
JP2003028975A (ja) * 2001-07-10 2003-01-29 Central Res Inst Of Electric Power Ind 原子炉
US7278474B2 (en) * 2001-10-09 2007-10-09 Mikros Manufacturing, Inc. Heat exchanger
US9734922B2 (en) * 2006-11-28 2017-08-15 Terrapower, Llc System and method for operating a modular nuclear fission deflagration wave reactor
CN100578683C (zh) * 2007-11-09 2010-01-06 中国核动力研究设计院 非能动的固有安全的管池式反应堆

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
See references of WO2011078871A2 *

Also Published As

Publication number Publication date
CN102667955A (zh) 2012-09-12
JP2013506132A (ja) 2013-02-21
RU2012113145A (ru) 2013-10-27
EP2481053A4 (fr) 2013-02-27
GB201205572D0 (en) 2012-05-16
EP2481055A2 (fr) 2012-08-01
EP2481053A2 (fr) 2012-08-01
GB2485754A (en) 2012-05-23
WO2011078870A2 (fr) 2011-06-30
KR20120083432A (ko) 2012-07-25
JP2013506130A (ja) 2013-02-21
WO2011078872A2 (fr) 2011-06-30
WO2011078870A3 (fr) 2011-08-18
CN102667954A (zh) 2012-09-12
KR20120083433A (ko) 2012-07-25
GB201205569D0 (en) 2012-05-16
CN102667953A (zh) 2012-09-12
RU2012113143A (ru) 2013-10-27
WO2011078872A3 (fr) 2011-08-18
KR20120083434A (ko) 2012-07-25
WO2011078871A3 (fr) 2011-08-18
WO2011078871A2 (fr) 2011-06-30
GB2485752A (en) 2012-05-23
GB2485753A (en) 2012-05-23
RU2012113142A (ru) 2013-10-27
JP2013506131A (ja) 2013-02-21
GB201205571D0 (en) 2012-05-16

Similar Documents

Publication Publication Date Title
US11145424B2 (en) Direct heat exchanger for molten chloride fast reactor
US11367536B2 (en) Molten fuel reactor thermal management configurations
US11488731B2 (en) Direct reactor auxiliary cooling system for a molten salt nuclear reactor
US20110075786A1 (en) Heat exchanger, methods therefor and a nuclear fission reactor system
US9275760B2 (en) Heat exchanger, methods therefor and a nuclear fission reactor system
US9221093B2 (en) Heat exchanger, methods therefor and a nuclear fission reactor system
EP2481054A2 (fr) Échangeur thermique, procédés apparentés et système de réacteur à fission nucléaire
WO2011071512A1 (fr) Réacteur à fission nucléaire, module de combustible de fission nucléaire dégazé, procédés pour ceux-ci et système de module de combustible de fission nucléaire dégazé
CN102460594B (zh) 核裂变反应堆、流量控制组件、其方法和流量控制组件系统
EP0152206A2 (fr) Réflecteur radial de neutrons
JP2009085650A (ja) 高速炉の炉心構成要素，炉心燃料集合体、及び炉心並びに原子炉構造
EP2610875A1 (fr) Tube d'emballage pour sous-assemblage de carburant d'un coeur de réacteur nucléaire et procédé de protection du combustible contre les surchauffes en cas d'ébullition du fluide de refroidissement
Smith et al. Fast reactor operation in the United States
CHETAL et al. IMPROVED PRIMARY PIPE COOLANT DESIGN CONCEPTS FOR FUTURE FBRs

Legal Events

Date Code Title Description
PUAI Public reference made under article 153(3) epc to a published international application that has entered the european phase

Free format text: ORIGINAL CODE: 0009012

17P Request for examination filed

Effective date: 20120329

AK Designated contracting states

Kind code of ref document: A2

Designated state(s): AL AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HR HU IE IS IT LI LT LU LV MC MK MT NL NO PL PT RO SE SI SK SM TR

RIN1 Information on inventor provided before grant (corrected)

Inventor name: MCWHIRTER, JON, D.

DAX Request for extension of the european patent (deleted)
STAA Information on the status of an ep patent application or granted ep patent

Free format text: STATUS: THE APPLICATION HAS BEEN WITHDRAWN

18W Application withdrawn

Effective date: 20140528