US3179570A - Thermal exchange of the fuel elements in nuclear reactor - Google Patents

Thermal exchange of the fuel elements in nuclear reactor Download PDF

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US3179570A
US3179570A US46491A US4649160A US3179570A US 3179570 A US3179570 A US 3179570A US 46491 A US46491 A US 46491A US 4649160 A US4649160 A US 4649160A US 3179570 A US3179570 A US 3179570A
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fins
fluid
fuel element
elements
nuclear reactor
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US46491A
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Foll Jean Le
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/08—Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
    • 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/901—Fuel
    • Y10S376/903—Shapes

Definitions

  • the present invention relates to an apparatus for inducing transverse currents of cooling fluid along the fuel elements of atomic reactors.
  • Improvement of thermal exchange between the body (whether or not encased) of the fuel elements or cartridges for nuclear reactors and the fluid which surrounds it is generally obtained by means of fins extending from the body.
  • the fluid most usually a compressed gas, circulates inside a channel containing the fuel element and the general direction of fluid flow is longitudinal with respect to the element.
  • the fins increase the thermal exchange surface.
  • they should be sufficiently short for the fall in temperature from the base to the tip of the fin to be small; on the other hand, local convection currents should be set up which improve the thermal exchange.
  • a device referred to by its inventor as a polyzonal cartridge which allows a considerable increase of the exchange surface to be obtained.
  • the fins are helicoidal and are cut by longitudinal partitions or splitters; the fall of pressure of the principal fluid flow in the main channel between the ends of the elementary channels defined by the fins is then small compared with the dynamic pressure of this same flow; the movement of the fluid between the fins is essentially an ascending rotary movement; furthermore, exchanges constantly take place between the fluid circulating in the elementary channels located between the fins and the fluid circulating in the main channel, which is obtained by means of the splitters which set up a considerable flow in the subsidiary channels and cause the fluid circulating in these subsidiary channels to be renewed periodically.
  • Circumferential fins have been used which present their faces perpendicularly to the flow of the fluid in the annular part.
  • the arrangement usually adopted is that the fins are separated by a distance substantially equal to their height.
  • the present invention consists essentially in providing transverse fins on the body of a fuel element, the thickness of the fins and the interval between them being made as small as the present technique of manufacture allows, the height of the fins being about 3-10 times the separation between them, and also in producing, along the circular transverse channels defined by the fins, a pressure field having one or more maxima, the field being obtained from the dynamic pressure corresponding to the longitudinal movement of the principal fluid current, so that the cooling fluid is constrained to travel transversely and tangentially along the circular transverse channels.
  • This fiuid under pressure may be obatined by the following means.
  • wing members On the exterior contour formed by the assembly of transverse fins, wing members are provided having the form of flat arrowheads constituting triangular blades attached to a backbone fixed longitudinally to the casing of the fuel element following a generatrix; the plane of fixing of the blades forming an angle with the plane tangential to the casing along the generatrix, the sine of which is approximately the ratio of the thickness of the passages between the transverse fins to the sum of the thickness of these passages and the thickness of the fins.
  • This structure superimposed on the transverse fins allow a difference in propulsive pressure to be set up between the inlets and outlets of the elementary transverse channels defined by these fins.
  • FIGURES 1 to 4 of the accompanying drawings an embodiment of devices for the production of transverse currents of fluid along the fuel elements of nuclear reactors, according to the invention, is described below, by Way of example.
  • FIGURE 1 is a partial axial view of a casing of a fuel element comprising triangular wing members attached to a backbone fixed longitudinally to the casing, the plane of the section passing through a midrib;
  • FIGURE 2 is a side elevation of FIGURE 1;
  • FIGURE 3 is an end view of the casing of FIGURE 1;
  • FIGURE 4 is a free perspective representation of a broken piece of this same casing.
  • defiective elements have a plane triangular or delta form and are designated by the reference 27.
  • a backbone 28 which is long compared with its breadth, is secured to the transverse cooling fins 2 of the casing 1 of the rod 1a.
  • the backbone 28 is fixed to the casing along a generatrix of the right cylinder enclosing the fins themselves. According to FIG. 3 and the embodiment chosen, the number of such backbones is equal to four. They are arranged symmetrically on the circumference of the casing and from them are derived in turn the planes of symmetry for the delta vanes 27.
  • the vanes 27 are then situated on both sides of each of the backbones 28.
  • the inclination of the plane of these vanes 27 with respect to the plane tangential to the cylinder along the generatrix connected with a backbone 28 is determined so that these planes make an angle between them the since of which is preferably approximately the same or slightly greater than the ratio of the width of the spaces between the transverse fins 2 to the sum of the thickness of these spaces and the thickness of the fins.
  • the thickness of the spaces being equal to that of the fins, the angle at which the vanes 27 are mounted is about 30.
  • the inductive assembly (delta vanes and backbone) can be made from graphite, which has the advantage of acting as a moderator and absorbing few neutrons.
  • the backbones 28 can be prolonged as far as the channel of the pile and then are supported by lugs 29 on the Walls 10 of the channel and thus ensure the centering of the fuel element cartridge in the reactor channel.
  • Another modification according to the invention consists in cutting down the triangular vanes on a part of their length so as to avoid marginal turbulence of the fluid on these vanes and to suppress useless frothing of liquid under the sides of the triangular vanes.
  • the principal flow of cooling fluid is shown by the arrow 30 (FIGS. 1 and 4).
  • the arrow 31 represents the path of a portion of this same fluid subjected to deflection by the vanes 27; it is seen that this path is transverse as far as the point 32 and then passes down the space between the fins 2.
  • a nuclear reactor fuel channel the combination of a nuclear reactor fuel element and a device for removing heat from the nuclear fuel element having a sheath provided with transverse cooling fins by means of a cooling fluid so as to make the fluid circulate transversely throughout the unitary circular channels formed by the fins, a plurality of spaced deflecting elements uniformly distributed over the fins for deflecting the fluid into the circular channels, each of said elements being triangular with one side tangent to the edges of the fins and lying in a single plane oblique to the longitudinal axis of the fuel element and forming arrow-shaped flat vanes, said triangular elements down toward the fins, and longitudinal backbones parallel to the longitudinal axis of the fuel element secured to and in contact with the outer edges of the fins supporting said deflecting elements, the longitudinal spacing of said deflecting elements being such that a cross section transverse to the longitudinal axis of the fuel elements includes two of said deflecting elements supported by the same backbone.
  • said backbones including lugs extending adjacent to the inner wall of the channel containing the fuel element and bearing on the wall for centering the fuel element.

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

Description

J- LE FOLL April 20, 1965 THERMAL EXCHANGE OF THE FUEL ELEMENTS IN NUCLEAR REACTOR Filed Aug. 1. 1960 United States Patent 3,179,570 THERMAL EXCHANGE OF THE FUEL ELEMENTS IN NUCLEAR REACTOR Jean Le Foll, Sevres, France, assignor to Commissariat a lEnergie Atomique, Paris, France Filed Aug. 1, 1966, Ser. No. 46,491 Claims priority, application France, Aug. 13, 1%9, 802,766; Apr. 6, 1960, 823,516 3 Claims. (Cl. 176-59) The present invention relates to an apparatus for inducing transverse currents of cooling fluid along the fuel elements of atomic reactors.
Improvement of thermal exchange between the body (whether or not encased) of the fuel elements or cartridges for nuclear reactors and the fluid which surrounds it is generally obtained by means of fins extending from the body. The fluid, most usually a compressed gas, circulates inside a channel containing the fuel element and the general direction of fluid flow is longitudinal with respect to the element.
In this way, the fins increase the thermal exchange surface. However, in order to be eflicient, they should be sufficiently short for the fall in temperature from the base to the tip of the fin to be small; on the other hand, local convection currents should be set up which improve the thermal exchange. In order to increase the exchange surface without lengthening the fins too much, it has been the practice to place the fins close to one another, but then a new difficulty appears.
In fact, by the use of very particular aerodynamic arrangements, high rates of flow only arise in the annular region situated between the tips of the fins and the channel. In contrast, although the elementary channels delimited by the fins are open to the aforesaid annular region, the rates there remain moderate and the local coefficients of exchange remain very limited immediately away from the tips of the fins.
To avoid this disadvantage, which becomes particularly serious in the case of very close-packed longitudinal fins, a device referred to by its inventor as a polyzonal cartridge has been used which allows a considerable increase of the exchange surface to be obtained. The fins are helicoidal and are cut by longitudinal partitions or splitters; the fall of pressure of the principal fluid flow in the main channel between the ends of the elementary channels defined by the fins is then small compared with the dynamic pressure of this same flow; the movement of the fluid between the fins is essentially an ascending rotary movement; furthermore, exchanges constantly take place between the fluid circulating in the elementary channels located between the fins and the fluid circulating in the main channel, which is obtained by means of the splitters which set up a considerable flow in the subsidiary channels and cause the fluid circulating in these subsidiary channels to be renewed periodically.
In contrast to what takes place in the case of a casing provided with longitudinal fins or helicoidal fins without splitters, the thermal etficiency of polyzonal casings increases according to the fineness and closeness of packing of the vanes and the only limit appears to be of a technological nature.
Circumferential fins have been used which present their faces perpendicularly to the flow of the fluid in the annular part. The arrangement usually adopted is that the fins are separated by a distance substantially equal to their height.
It is hence seen that a powerful dynamic and turbulent flow is set up between these fins, considerably increasing not only the heat exchange, but also the losses of the charge. The improvement obtained by means of this device is limited by the fact that the ting cannot be placed too closely together without causing the disappearance of the phenomenon described above which favours thermal exchange. Indeed, if the fins are placed transversely very closely together, sufliciently rapid local currents cannot be induced between the fins, that is to say, transversely of the body of the fuel element; eddy currents are only found at the tips of the fins and there is furthermore the disadvantage of an increased loss of charge along the channel.
The present invention consists essentially in providing transverse fins on the body of a fuel element, the thickness of the fins and the interval between them being made as small as the present technique of manufacture allows, the height of the fins being about 3-10 times the separation between them, and also in producing, along the circular transverse channels defined by the fins, a pressure field having one or more maxima, the field being obtained from the dynamic pressure corresponding to the longitudinal movement of the principal fluid current, so that the cooling fluid is constrained to travel transversely and tangentially along the circular transverse channels.
This fiuid under pressure may be obatined by the following means.
On the exterior contour formed by the assembly of transverse fins, wing members are provided having the form of flat arrowheads constituting triangular blades attached to a backbone fixed longitudinally to the casing of the fuel element following a generatrix; the plane of fixing of the blades forming an angle with the plane tangential to the casing along the generatrix, the sine of which is approximately the ratio of the thickness of the passages between the transverse fins to the sum of the thickness of these passages and the thickness of the fins.
This structure superimposed on the transverse fins allow a difference in propulsive pressure to be set up between the inlets and outlets of the elementary transverse channels defined by these fins.
Referring to FIGURES 1 to 4 of the accompanying drawings, an embodiment of devices for the production of transverse currents of fluid along the fuel elements of nuclear reactors, according to the invention, is described below, by Way of example.
The arrangement to be described in connection with this embodiment is to be considered as forming part of the invention, it being understood that all equivalent arrangements may be utilised without exceeding the scope thereof.
FIGURE 1 is a partial axial view of a casing of a fuel element comprising triangular wing members attached to a backbone fixed longitudinally to the casing, the plane of the section passing through a midrib;
FIGURE 2 is a side elevation of FIGURE 1;
FIGURE 3 is an end view of the casing of FIGURE 1;
FIGURE 4 is a free perspective representation of a broken piece of this same casing.
In these figures, only those elements necessary for the understanding of the invention have been depicted; corresponding elements in different figures carry the same references.
In the modification shown in FIGURES l to 4, defiective elements have a plane triangular or delta form and are designated by the reference 27. A backbone 28 which is long compared with its breadth, is secured to the transverse cooling fins 2 of the casing 1 of the rod 1a. The backbone 28 is fixed to the casing along a generatrix of the right cylinder enclosing the fins themselves. According to FIG. 3 and the embodiment chosen, the number of such backbones is equal to four. They are arranged symmetrically on the circumference of the casing and from them are derived in turn the planes of symmetry for the delta vanes 27.
The vanes 27 are then situated on both sides of each of the backbones 28. The inclination of the plane of these vanes 27 with respect to the plane tangential to the cylinder along the generatrix connected with a backbone 28 is determined so that these planes make an angle between them the since of which is preferably approximately the same or slightly greater than the ratio of the width of the spaces between the transverse fins 2 to the sum of the thickness of these spaces and the thickness of the fins. As an example of this embodiment, the thickness of the spaces being equal to that of the fins, the angle at which the vanes 27 are mounted is about 30.
These vanes and the backbone which supports them have in practice a purely aerodynamic role and only participate in heat exchanges with a very low coefiicient. Consequently, this assembly can be constructed in a material different from that of the casing, so far as the choice of such a material is advantageous as regards absorption of neutrons or techniques of construction. For example, the inductive assembly (delta vanes and backbone) can be made from graphite, which has the advantage of acting as a moderator and absorbing few neutrons. In this case and according to FIGURE 1, the backbones 28 can be prolonged as far as the channel of the pile and then are supported by lugs 29 on the Walls 10 of the channel and thus ensure the centering of the fuel element cartridge in the reactor channel.
Another modification according to the invention consists in cutting down the triangular vanes on a part of their length so as to avoid marginal turbulence of the fluid on these vanes and to suppress useless frothing of liquid under the sides of the triangular vanes.
The principal flow of cooling fluid is shown by the arrow 30 (FIGS. 1 and 4). The arrow 31 represents the path of a portion of this same fluid subjected to deflection by the vanes 27; it is seen that this path is transverse as far as the point 32 and then passes down the space between the fins 2.
I claim:
1. In a nuclear reactor fuel channel, the combination of a nuclear reactor fuel element and a device for removing heat from the nuclear fuel element having a sheath provided with transverse cooling fins by means of a cooling fluid so as to make the fluid circulate transversely throughout the unitary circular channels formed by the fins, a plurality of spaced deflecting elements uniformly distributed over the fins for deflecting the fluid into the circular channels, each of said elements being triangular with one side tangent to the edges of the fins and lying in a single plane oblique to the longitudinal axis of the fuel element and forming arrow-shaped flat vanes, said triangular elements down toward the fins, and longitudinal backbones parallel to the longitudinal axis of the fuel element secured to and in contact with the outer edges of the fins supporting said deflecting elements, the longitudinal spacing of said deflecting elements being such that a cross section transverse to the longitudinal axis of the fuel elements includes two of said deflecting elements supported by the same backbone.
2. Device as described in claim 1 in which the angle between a plane tangent to the fins along one of said backbones and the plane of said vanes has its sine approaching the ratio of the distance between adjacent transverse fins and the sum of said distance and the thickness of a fin.
3. Device as described in claim 1, said backbones including lugs extending adjacent to the inner wall of the channel containing the fuel element and bearing on the wall for centering the fuel element.
References Cited by the Examiner UNITED STATES PATENTS OTHER REFERENCES Printed application No. 1,066,291, Germany.
October 1959,
45 CARL D. QUARFORTH, Primary Examiner.
OSCAR R. VERTIZ, ROGER L. CAMPBELL,
Examiners.
UNITE-D STATES-PATENT OFFICE CERTIFICATE OF CORRECTION Patent No. 3,179,570 April 20, 1965- Jean Le Foll It is hereby certified that error appears in-the above numbered bat- I ent reqliring correction and that the said Letters Patent should read as correctedbelow.
Column 3, line 6, for "since" read sine Signed and sealed this 17th day of August 1965 (sum Attest:
EDWARD J. BRENNER Commissioner of Patents' ERNEST w. SWIDER -All.csting Officer UNITED STATES PATENT OFFICE CERTIFICATE OF CORRECTION Patent No. 3,179,570 I April 20, 1965 Jean Le F011 It is hereby certified that error appears in the above numbered batj ent reqliring correction and that the said Letters Patent should read as corrected below Column 3 line 6 for "since" read sine Signed and sealed this 17th 'dayof August 1965 SEA L) Attest:
EDWARD J. BRENNER Commissioner of Patents ERNEST w. SWIDER Al testing Officer

Claims (1)

1. IN A NUCLEAR REACTOR FUEL CHANNEL, THE COMBINATION OF A NUCLEAR REACTOR FUEL ELEMENT AND A DEVICE FOR REMOVING HEAT FROM THE NUCLEAR FUEL ELEMENT HAVING A SHEATH PROVIDED WITH TRANSVERSE COOLING FINS BY MEANS OF A COOLING FLUID SO AS TO MAKE THE FLUID CIRCULATE TRANSVERSELY THROUGHOUT THE UNITARY CIRCULAR CHANNELS FORMED BY THE FINS, A PLURALTIY OF SPACED DEFLECTING ELEMENTS UNIFORMLY DISTRIBUTED OVER THE FINS FOR DEFLECTING THE FLUID INTO THE CIRCULAR CHANNELS, EACH OF SAID ELEMENTS BEING TRIANGULAR WITH ONE SIDE TANGENT TO THE EDGES OF THE FINS AND LYING IN A SINGLE PLANE OBLIQUE TO THE LONGTUDINAL AXIS OF THE FUEL ELEMENT AND FORMING ARROW-SHAPED FLAT VANES, SAID TRIANGULAR ELEMENTS DOWN TOWARD THE FINS, LONGITUDINAL BACKBONES PARALLEL TO THE LONGITUDINAL AXIS
US46491A 1959-08-13 1960-08-01 Thermal exchange of the fuel elements in nuclear reactor Expired - Lifetime US3179570A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR802766A FR1241855A (en) 1959-08-13 1959-08-13 New process and devices for extracting heat from nuclear reactor fuel elements using transverse fins
FR823516A FR77447E (en) 1959-08-13 1960-04-06 New process and devices for extracting heat from nuclear reactor fuel elements using transverse fins

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BE (1) BE593730A (en)
CH (1) CH367575A (en)
FR (2) FR1241855A (en)
GB (1) GB955425A (en)
LU (1) LU39049A1 (en)
NL (1) NL254720A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3368946A (en) * 1964-03-04 1968-02-13 Alfa Laval Ab Fuel assembly
US3402766A (en) * 1967-05-23 1968-09-24 Varian Associates Method and means for vapor cooling an electron tube
US3435891A (en) * 1967-03-23 1969-04-01 Int Rectifier Corp Air flow baffle for rectifier heat exchanger
US3787286A (en) * 1971-12-17 1974-01-22 Combustion Eng Fuel assembly flow redistribution
US4054487A (en) * 1974-06-04 1977-10-18 Tokyo Shibaura Denki Kabushiki Kaisha Nuclear fuel rods

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL262351A (en) * 1958-12-05 1900-01-01
DE2255699A1 (en) * 1972-11-14 1974-05-16 Kernforschung Gmbh Ges Fuer FUEL ELEMENT FOR A REACTOR
GB8431042D0 (en) * 1984-12-07 1985-02-13 Atomic Energy Authority Uk Gas cooled nuclear reactors
GB2168192B (en) * 1984-12-07 1989-08-31 Atomic Energy Authority Uk Gas cooled nuclear reactors
GB2208749B (en) * 1985-10-07 1989-09-13 Atomic Energy Authority Uk Gas cooled nuclear reactors

Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB258388A (en) *
US1925720A (en) * 1930-12-20 1933-09-05 Gen Fire Extinguisher Co Fin for heat exchanger
FR795938A (en) * 1934-10-19 1936-03-25 Ig Farbenindustrie Ag Process for heating heating tubes by means of gas containing dust
US2406551A (en) * 1943-08-28 1946-08-27 United Aircraft Corp Cylinder cooling structure for aircraft engines
US2434519A (en) * 1942-04-18 1948-01-13 Raskin Walter Heat exchange conduit with a spiral fin having a capillary groove
US2874940A (en) * 1951-05-16 1959-02-24 Svenska Rotor Maskiner Ab Heat exchanger
GB816124A (en) * 1956-11-23 1959-07-08 Atomic Energy Authority Uk Improvements in or relating to fuel elements
GB817963A (en) * 1956-06-22 1959-08-06 Atomic Energy Authority Uk Improvements in or relating to heat transfer systems
GB821263A (en) * 1956-11-24 1959-10-07 Atomic Energy Authority Uk Improvements in or relating to fuel elements for nuclear reactors
GB821861A (en) * 1956-09-28 1959-10-14 Atomic Energy Authority Uk Improvements in or relating to heat transfer systems in nuclear reactor fuel elements
US2998228A (en) * 1956-11-23 1961-08-29 Huet Andre Surface heat exchangers

Patent Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB258388A (en) *
US1925720A (en) * 1930-12-20 1933-09-05 Gen Fire Extinguisher Co Fin for heat exchanger
FR795938A (en) * 1934-10-19 1936-03-25 Ig Farbenindustrie Ag Process for heating heating tubes by means of gas containing dust
US2434519A (en) * 1942-04-18 1948-01-13 Raskin Walter Heat exchange conduit with a spiral fin having a capillary groove
US2406551A (en) * 1943-08-28 1946-08-27 United Aircraft Corp Cylinder cooling structure for aircraft engines
US2874940A (en) * 1951-05-16 1959-02-24 Svenska Rotor Maskiner Ab Heat exchanger
GB817963A (en) * 1956-06-22 1959-08-06 Atomic Energy Authority Uk Improvements in or relating to heat transfer systems
GB821861A (en) * 1956-09-28 1959-10-14 Atomic Energy Authority Uk Improvements in or relating to heat transfer systems in nuclear reactor fuel elements
GB816124A (en) * 1956-11-23 1959-07-08 Atomic Energy Authority Uk Improvements in or relating to fuel elements
US2998228A (en) * 1956-11-23 1961-08-29 Huet Andre Surface heat exchangers
GB821263A (en) * 1956-11-24 1959-10-07 Atomic Energy Authority Uk Improvements in or relating to fuel elements for nuclear reactors

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3368946A (en) * 1964-03-04 1968-02-13 Alfa Laval Ab Fuel assembly
US3435891A (en) * 1967-03-23 1969-04-01 Int Rectifier Corp Air flow baffle for rectifier heat exchanger
US3402766A (en) * 1967-05-23 1968-09-24 Varian Associates Method and means for vapor cooling an electron tube
US3787286A (en) * 1971-12-17 1974-01-22 Combustion Eng Fuel assembly flow redistribution
US4054487A (en) * 1974-06-04 1977-10-18 Tokyo Shibaura Denki Kabushiki Kaisha Nuclear fuel rods

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NL254720A (en)
FR77447E (en) 1962-03-02
FR1241855A (en) 1960-09-23
GB955425A (en) 1964-04-15
BE593730A (en) 1960-12-01
CH367575A (en) 1963-02-28
LU39049A1 (en) 1960-10-04

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