DE1175804B - Fuel element for gas-cooled nuclear reactors - Google Patents
Fuel element for gas-cooled nuclear reactorsInfo
- Publication number
- DE1175804B DE1175804B DEU4969A DEU0004969A DE1175804B DE 1175804 B DE1175804 B DE 1175804B DE U4969 A DEU4969 A DE U4969A DE U0004969 A DEU0004969 A DE U0004969A DE 1175804 B DE1175804 B DE 1175804B
- Authority
- DE
- Germany
- Prior art keywords
- rod
- fuel
- fuel element
- gas
- moderator
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000000446 fuel Substances 0.000 title claims description 18
- 239000000463 material Substances 0.000 claims description 13
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 9
- 229910002804 graphite Inorganic materials 0.000 description 9
- 239000010439 graphite Substances 0.000 description 9
- 239000003758 nuclear fuel Substances 0.000 description 9
- 239000008358 core component Substances 0.000 description 3
- 230000001681 protective effect Effects 0.000 description 3
- 125000006850 spacer group Chemical group 0.000 description 3
- 239000000306 component Substances 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 238000009395 breeding Methods 0.000 description 1
- 230000001488 breeding effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000005553 drilling Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 239000011796 hollow space material Substances 0.000 description 1
- 239000011872 intimate mixture Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 210000000689 upper leg Anatomy 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
Classifications
-
- 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
- G21C3/16—Details of the construction within the casing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
- G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
-
- 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
-
- 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
- G21C3/041—Means for removal of gases from fuel elements
-
- 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
- G21C3/16—Details of the construction within the casing
- G21C3/18—Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/3213—Means for the storage or removal of fission gases
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
- G21C5/16—Shape of its constituent parts
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
DEUTSCHESGERMAN
PATENTAMTPATENT OFFICE
AUSLEGESCHRIFTEDITORIAL
Internat. Kl.: G 21 Boarding school Class: G 21
Deutsche KL: 21g-21/20 German KL: 21g-21/20
Nummer: 1175 804Number: 1175 804
Aktenzeichen: U 4969 VIII c / 21 gFile number: U 4969 VIII c / 21 g
Anmeldetag: 30. November 1957 Filing date: November 30, 1957
Auslegetag: 13. August 1964Opened on: August 13, 1964
Die Erfindung bezieht sich auf ein Brennstoffelement für gasgekühlte Kernreaktoren, dessen Brennstoff innerhalb eines praktisch gasundurchlässigen röhrenförmigen, aus Moderatormaterial bestehenden Behälters angeordnet ist.The invention relates to a fuel element for gas-cooled nuclear reactors, the Fuel within a practically gas-impermeable tubular made of moderator material Container is arranged.
Es ist bereits vorgeschlagen worden, Kernbrennstoff in Behältern unterzubringen, welche Moderiereigenschaften haben. So ist bekannt, einen Brennstoffstab in einem Behälter mit einer Innenauskleidung aus moderierendem Material anzuordnen und ein Kühlmittel über den Stab zu leiten. Weiterhin ist ein Graphitbehälter bekannt, in den Kernbrennstoff in Form von stranggepreßten Stäben, Pellets oder Pulver dicht eingeschlossen ist. Auch Brennstoffelemente mit hohlen Zylindern aus Kernbrennstoff, die in einer Zirkonhülle angeordnet sind, sind bekannt.It has already been proposed to accommodate nuclear fuel in containers which have moderating properties to have. It is known to have a fuel rod in a container with an inner liner of moderating material to be arranged and a coolant to be passed over the rod. Furthermore is a Graphite containers known to be in the nuclear fuel in the form of extruded rods, pellets or Powder is tightly enclosed. Also fuel elements with hollow cylinders made of nuclear fuel, which are arranged in a zirconium shell are known.
Zweck der Erfindung ist die Schaffung einer gegenüber den bekannten Vorschlägen vorteilhafteren Anordnung des Kernbrennstoffes in einem Brennstoffelement, so daß bei höheren Betriebstemperaturen gearbeitet werden kann.The purpose of the invention is to create an arrangement that is more advantageous than the known proposals of the nuclear fuel in a fuel element, so that at higher operating temperatures can be worked.
Bei dem Brennstoffelement nach der Erfindung wird dies dadurch erreicht, daß ein aus Moderatormaterial bestehender Stab mittels mehrerer am Stab vorgesehener Flansche im rohrförmigen Behälter zentriert gelagert wird, so daß zwischen benachbarten Flanschen ein Ringraum verbleibt, und daß mehrere aus Spaltstoff-Moderatormaterial bestehende hohle Brennstoffhülsen auf dem Moderatorstab im besagten Ringraum lose aufgestapelt sind.In the fuel element according to the invention, this is achieved in that a rod made of moderator material is attached to the rod by means of several provided flanges is stored centered in the tubular container, so that between adjacent Flanges an annulus remains, and that several hollow material consisting of fissile material moderator material Fuel sleeves are loosely stacked on the moderator rod in said annulus.
Ein Vorteil des Brennstoffelements nach der Erfindung besteht darin, daß sehr hohe Wärmefreigabegeschwindigkeiten und Oberflächentemperaturen möglich sind. Die Wärme wird vom Kernbrennstoff nach seinem Behälter durch Strahlung übertragen und dann durch Wärmeleitung über den Behälter nach einem Kühlmittel weitergeleitet. Da die Wärme durch Strahlung vom Kernbrennstoff nach der Schutzhülle übertragen wird, besteht nicht die Notwendigkeit eines engen Wärmeleitungskontaktes zwischen diesen, und der Kernbrennstoff kann lose sitzend innerhalb der Schutzhülle oder des Behälters untergebracht werden, wodurch eine Beschädigung und eine Verformung des Kernbrennstoffs stattfinden kann, ohne daß der Reaktorbetrieb beeinflußt wird. Außerdem wirkt der Behälter sowohl als Schutzhülle als auch als Moderator.An advantage of the fuel element according to the invention is that very high heat release rates and surface temperatures are possible are. The heat is transferred from the nuclear fuel to its container by radiation and then passed on by conduction via the container to a coolant. Because the heat through Radiation from the nuclear fuel is transmitted after the protective envelope, there is no need a close thermal contact between these, and the nuclear fuel can be loosely seated within the protective cover or the container, causing damage and deformation of the nuclear fuel can take place without affecting the operation of the reactor. aside from that the container acts both as a protective cover and as a moderator.
Die Erfindung soll nunmehr an Hand eines Ausführungsbeispiels gemäß der Zeichnung näher erläutert werden, und zwar zeigtThe invention will now be explained in more detail using an exemplary embodiment according to the drawing be, namely shows
F i g. 1 eine aufgeschnittene Perspektivansicht eines Brennstoffelement für gasgekühlte KernreaktorenF i g. 1 is a cut-away perspective view of a fuel element for gas-cooled nuclear reactors
Anmelder:Applicant:
United Kingdom Atomic Energy Authority,United Kingdom Atomic Energy Authority,
LondonLondon
Vertreter:Representative:
Dipl.-Ing. E. Schubert,Dipl.-Ing. E. Schubert,
Patentanwalt, Siegen, Oranienstr. 14Patent attorney, Siegen, Oranienstr. 14th
Als Erfinder benannt:Named as inventor:
Peter Fortescue,Peter Fortescue,
George Edward Lockett, LondonGeorge Edward Lockett, London
Beanspruchte Priorität:Claimed priority:
Großbritannien vom 30. November 1956Great Britain 30 November 1956
(36775)(36775)
Kernbauteilabschnitts gemäß der Erfindung, während Core component section according to the invention, while
Fig. 2 einen lotrechten Schnitt durch die Mitte eines abgeänderten Kernbauteils in einem größeren Maßstab wiedergibt.Fig. 2 is a vertical section through the center of a modified core component in a larger one Scale.
Gemäß der Zeichnung besteht der Behälter des Kernbauteilabschnitts aus einem Graphitrohr 3 von sechseckigem Querschnitt, das eine kreisförmige Bohrung von beispielsweise 38 mm Durchmesser besitzt. Jedes Rohr 3, welches etwa 1,8 m lang ist, wird durch Graphitstöpsel verschlossen.According to the drawing, the container of the core component section consists of a graphite tube 3 from hexagonal cross-section, which has a circular bore of, for example, 38 mm in diameter. Each tube 3, which is about 1.8 m long, is closed by graphite plugs.
In jedem Rohr 3 befindet sich ein Brennstoffhaltestab 14 aus Graphit, welcher in Abständen mit ringförmigen Nuten ausgebildet ist, in die Graphitsprengringe 15 eingeführt sind. Zwischen je zwei Sprengringen befindet sich eine lose sitzende Hülse 16, welche Spaltmaterial enthält und den Kernbrennstoff bildet. Ein Abstandsbauteil 17 ist an jedem Ende zwischen dem Stab 14 und einem oberen Endstopfen 4 und einem unteren Endstopfen vorgesehen. Es wird darauf hingewiesen, daß diese Abstandshalter 17 und die Ösen und Schenkelkreuze, welche sich über diesen befinden, neutronenreflektierende Bauteile bilden.In each tube 3 there is a fuel holding rod 14 made of graphite, which at intervals with annular Grooves is formed into which graphite snap rings 15 are inserted. Between two snap rings there is a loosely fitting sleeve 16 which contains fissile material and the nuclear fuel forms. A spacer member 17 is at each end between the rod 14 and an upper end plug 4 and a lower end plug provided. It should be noted that these spacers 17 and the eyelets and thigh crosses that are above these are neutron-reflecting Form components.
In F i g. 2 ist eine vorzugsweise verwendete Konstruktion für den Brennstoffhaltestab veranschaulicht. Der Stab besteht aus einer Mehrzahl von Abschnitten 40 aus Graphit, von denen jeder einenIn Fig. Figure 2 illustrates a preferably used construction for the fuel support rod. The rod consists of a plurality of sections 40 of graphite, each of which is one
·■.· ' 409 540/294· ■. · '409 540/294
Flansch 41 aufweist, aus einem Sockel 42 an seinem unteren Ende und aus einem Zapfen 43 an seinem oberen Ende. Der Durchmesser des Flansches 41 ist so gewählt, daß der Flansch mit losem Sitz innerhalb der kreisförmigen Bohrung des Graphitrohres 3 a sitzt. Zum Beispiel ist, um Herstellungstoleranzen zu gestatten, ein Spielraum von 0,05 bis 0,18 mm vorgesehen bei einem Durchmesser von 38 mm für die Bohrung.Has flange 41, from a base 42 at its lower end and from a pin 43 at his upper end. The diameter of the flange 41 is chosen so that the flange with a loose fit within the circular bore of the graphite tube 3 a sits. For example, there is to be manufacturing tolerances allow a margin of 0.05 to 0.18 mm provided with a diameter of 38 mm for the Drilling.
Eine Mehrzahl von Graphithülsen 16 a, welche etwa 1 Atom Spaltmaterial in 1000 Atomen Moderatormaterial enthalten, wird auf jeden Abschnitt 40 aufgebracht, und zwar ehe die Abschnitte Ende am Ende zusammengebaut und in das Rohr 3 a eingesetzt werden. Die Hülsen 16 α sitzen lose über den Stababschnitten; sie sitzen jedoch noch loser innerhalb der Bohrung des Rohres 3 a, wobei ein Mindestspielraum von etwa 1,02 mm verbleibt. Somit besteht, wenn die höchstmögliche addierte Außermittigkeit sowohl der Hülsen als auch des Stabes angenommen wird, immer noch ein wesentlicher Spielraum zwischen den Hülsen und der Bohrung des Rohres.A plurality of graphite sleeves 16 a, which contain about 1 atom of fissile material in 1000 atoms of moderator material is applied to each section 40 before the sections end Assembled end and inserted into the tube 3 a. The sleeves 16 α sit loosely over the rod sections; However, they sit even more loosely within the bore of the tube 3 a, with a minimum margin of about 1.02 mm remains. Thus, if there is the highest possible added eccentricity Both the sleeves and the rod are adopted, there is still a substantial margin between the sleeves and the bore of the pipe.
Bei einer Rohrbohrung von etwa 38 mm Durchmesser, wobei jeder Stababschnitt 40 eine Länge von etwa 152 mm haben kann, können etwa 12 Brennstoffhülsen 16 a über jeden Abschnitt gestapelt werden. So können beispielsweise bei einer Rohrlänge von 1,8 m zehn Stababschnitte 40 und ein Abstandsbauteil 17 (F i g. 1) an jedem Ende vorgesehen sein. Ein wesentlicher Spielraum (welcher etwa der Hälfte einer Hülsenlänge 16 a entspricht) wird dabei zwischen dem oberen Ende eines jeden Stapels und dem Flansch 41 des Stababschnitts, welcher darüberliegt, gestattet.With a pipe bore of about 38 mm in diameter, each rod section 40 having a length of may have about 152 mm, about 12 fuel sleeves 16 a can be stacked over each section. For example, with a pipe length of 1.8 m, ten rod sections 40 and a spacer component 17 (Fig. 1) may be provided at each end. A substantial margin (which is about half corresponds to a sleeve length 16 a) is between the top of each stack and the Flange 41 of the rod portion overlying it.
Die Hülsen 16 a können dadurch hergestellt werden, daß eine innige Mischung aus einem einen hohen Reinheitsgrad aufweisenden synthetischen Gra-The sleeves 16 a can be produced in that an intimate mixture of one high purity synthetic grade
phit- (»Kernreaktor-Graphit«-) Staub und einem staubförmigen Spalt- und/oder Brutmaterial kaltgepreßt wird. phit ("nuclear reactor graphite") dust and a dusty fissure and / or breeding material is cold-pressed.
Claims (3)
Schweizerische Patentschrift Nr. 286 658;
britische Patentschrift Nr. 754 183;
»Reactor Handbook Engineering«, 1955, S. 451; »Nucleonics«, Vol. 14, Nr. 3, März 1956,
S. 34 bis 41;Considered publications:
Swiss Patent No. 286 658;
British Patent No. 754 183;
"Reactor Handbook Engineering", 1955, p. 451; "Nucleonics", Vol. 14, No. 3, March 1956,
Pp. 34 to 41;
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB36775/56A GB850015A (en) | 1956-11-30 | 1956-11-30 | Improvements in or relating to fuel elements for nuclear reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1175804B true DE1175804B (en) | 1964-08-13 |
Family
ID=10391090
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEU10271A Pending DE1223466B (en) | 1956-11-30 | 1957-11-30 | Fuel element bundle for gas-cooled nuclear reactors operated at high temperature |
| DEU4969A Pending DE1175804B (en) | 1956-11-30 | 1957-11-30 | Fuel element for gas-cooled nuclear reactors |
Family Applications Before (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEU10271A Pending DE1223466B (en) | 1956-11-30 | 1957-11-30 | Fuel element bundle for gas-cooled nuclear reactors operated at high temperature |
Country Status (6)
| Country | Link |
|---|---|
| BE (1) | BE562864A (en) |
| CH (1) | CH360137A (en) |
| DE (2) | DE1223466B (en) |
| FR (2) | FR1187405A (en) |
| GB (1) | GB850015A (en) |
| NL (3) | NL6503923A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE4218023A1 (en) * | 1992-06-01 | 1993-12-02 | Siemens Ag | Gas tight fuel rod for a water cooled nuclear reactor - includes metal stoppers between the fuel pellet column and top and bottom mounting arrangements |
Families Citing this family (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3172820A (en) * | 1958-07-25 | 1965-03-09 | Neutronic reactor | |
| BE591447A (en) * | 1959-06-03 | |||
| US3182001A (en) * | 1959-07-23 | 1965-05-04 | Siemens Ag | Heterogeneous nuclear reactor |
| NL255838A (en) * | 1960-03-07 | |||
| US3146173A (en) * | 1960-03-07 | 1964-08-25 | Fortescue Peter | Fuel element |
| US3141829A (en) * | 1960-04-19 | 1964-07-21 | Fortescue Peter | Fuel element |
| US3128234A (en) * | 1960-08-26 | 1964-04-07 | Jr Joseph F Cage | Modular core units for a neutronic reactor |
| NL272289A (en) * | 1960-12-09 | |||
| US3114693A (en) * | 1961-07-12 | 1963-12-17 | William T Furgerson | Vented fuel element for gas-cooled neutronic reactors |
| NL281237A (en) * | 1961-07-31 | |||
| BE620998A (en) * | 1961-08-02 | 1900-01-01 | ||
| BE624769A (en) * | 1961-11-15 | 1900-01-01 | ||
| BE630217A (en) * | 1962-03-28 | 1900-01-01 | ||
| DE1237231B (en) * | 1963-02-08 | 1967-03-23 | Kernforschung Mit Beschraenkte | Clamping device for the fission and breeding zone of an atomic nuclear reactor |
| FR1544171A (en) * | 1967-09-20 | 1968-10-31 | Creusot Forges Ateliers | Nuclear reactor operating at high temperature |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH286658A (en) * | 1950-11-09 | 1952-10-31 | Sulzer Ag | Process for harnessing atomic energy and nuclear reactor for carrying out the process. |
| GB754183A (en) * | 1954-05-14 | 1956-08-01 | Asea Ab | Improvements in nuclear-chain reactors |
-
0
- BE BE562864D patent/BE562864A/xx unknown
- NL NL222873D patent/NL222873A/xx unknown
- NL NL128573D patent/NL128573C/xx active
-
1956
- 1956-11-30 GB GB36775/56A patent/GB850015A/en not_active Expired
-
1957
- 1957-11-30 DE DEU10271A patent/DE1223466B/en active Pending
- 1957-11-30 CH CH360137D patent/CH360137A/en unknown
- 1957-11-30 DE DEU4969A patent/DE1175804B/en active Pending
- 1957-11-30 FR FR1187405D patent/FR1187405A/en not_active Expired
- 1957-11-30 FR FR1187404D patent/FR1187404A/en not_active Expired
-
1965
- 1965-03-26 NL NL6503923A patent/NL6503923A/xx unknown
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH286658A (en) * | 1950-11-09 | 1952-10-31 | Sulzer Ag | Process for harnessing atomic energy and nuclear reactor for carrying out the process. |
| GB754183A (en) * | 1954-05-14 | 1956-08-01 | Asea Ab | Improvements in nuclear-chain reactors |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE4218023A1 (en) * | 1992-06-01 | 1993-12-02 | Siemens Ag | Gas tight fuel rod for a water cooled nuclear reactor - includes metal stoppers between the fuel pellet column and top and bottom mounting arrangements |
Also Published As
| Publication number | Publication date |
|---|---|
| BE562864A (en) | |
| CH360137A (en) | 1962-02-15 |
| DE1223466B (en) | 1966-08-25 |
| FR1187404A (en) | 1959-09-10 |
| NL222873A (en) | |
| GB850015A (en) | 1960-09-28 |
| FR1187405A (en) | 1959-09-10 |
| NL128573C (en) | |
| NL6503923A (en) | 1965-05-25 |
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