DE1080236B - Metallic fuel element for an atomic nuclear reactor - Google Patents
Metallic fuel element for an atomic nuclear reactorInfo
- Publication number
- DE1080236B DE1080236B DES53842A DES0053842A DE1080236B DE 1080236 B DE1080236 B DE 1080236B DE S53842 A DES53842 A DE S53842A DE S0053842 A DES0053842 A DE S0053842A DE 1080236 B DE1080236 B DE 1080236B
- Authority
- DE
- Germany
- Prior art keywords
- fissile material
- fuel element
- embedded
- uncooled
- heat
- 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 10
- 239000000463 material Substances 0.000 claims description 30
- 238000001816 cooling Methods 0.000 claims description 23
- 230000035508 accumulation Effects 0.000 claims description 3
- 238000009825 accumulation Methods 0.000 claims description 3
- 238000010438 heat treatment Methods 0.000 claims description 3
- 238000000605 extraction Methods 0.000 claims description 2
- 230000004907 flux Effects 0.000 claims 1
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- 238000009924 canning Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000004744 fabric Substances 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
Classifications
-
- 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
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- 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
- G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in 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
-
- 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
-
- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Manufacture And Refinement Of Metals (AREA)
Description
DEUTSCHESGERMAN
Die Erfindung bezieht sich auf ein metallisches Brennstoffelement für einen Atomkernreaktor mit Wärmeentnahme mittels eines Wärmeträgers, welcher Kühlrohre durchfließt, die in den Spaltstoff des Brennstoffelementes eingebettet sind.The invention relates to a metallic fuel element for an atomic nuclear reactor with Heat extraction by means of a heat transfer medium, which flows through cooling pipes into the fissile material of the fuel element are embedded.
Die Erfindung ist dadurch gekennzeichnet, daß ungekühlte Oberflächen des Spaltstoffes und in den Spaltstoff eingebettete Oberflächen der Kühlrohre relativ zueinander derart ausgebildet sind, daß der Wärmefluß, welcher dem Innern des Spaltstoffes ent- *° quillt und den eingebetteten Kühlrohren zuströmt, an ungekühlten Spaltstoffoberflächen sowie in Spaltstoffanhäufungen örtliche Temperaturmaxima erzeugt, welche untereinander mindestens annähernd gleich sind, so daß eine unnötig hohe Erhitzung einzelner Spaltstoffteile vermieden wird.The invention is characterized in that uncooled surfaces of the fissile material and surfaces of the cooling pipes embedded in the fissile material are designed relative to one another in such a way that the heat flow, which swells out of the interior of the fissile material and flows towards the embedded cooling pipes, on uncooled fissile material surfaces and in Fissile material accumulations generate local temperature maxima which are at least approximately equal to one another, so that unnecessarily high heating of individual parts of the fissile material is avoided.
Hierzu kann mindestens ein Kühlrohr mit mindestens einer Außenrippe versehen sein, welche in den Spaltstoff hineinragt und die diesem entquellende Wärme dem Wärmeträger zuleitet. aoFor this purpose, at least one cooling tube can be provided with at least one outer rib which extends into the Fissile material protrudes and the heat from it passes through to the heat transfer medium. ao
Solche Rippen vorzusehen, ist insbesondere dann nützlich, wenn für die Kühlrohre ein Werkstoff von relativ hoher Wärmeleitfähigkeit gewählt ist, und ferner z. B. dann, wenn beim Einbetten des Kühlrohres der Spaltstoff an dasselbe angesintert wurde und derselbe dann unter Umständen eine nur geringe Wärmeleitfähigkeit aufweisen kann.Providing such ribs is particularly useful when a material of relatively high thermal conductivity is selected, and further z. B. when embedding the cooling tube the fissile material has been sintered to it and then under certain circumstances it has only a low thermal conductivity may have.
Es ist ein weiterer Vorteil solcher Rippen, daß durch sie die Haftung des Spaltstoffes an den in ihn eingebetteten Kühlrohren noch erhöht wird.Another advantage of such ribs is that they allow the fissile material to adhere to the ones in it embedded cooling tubes is increased.
Ob hierbei Längs- oder Querrippen zu wählen sind, ist vom Sonderfall abhängig zu machen.Whether longitudinal or transverse ribs are to be selected depends on the special case.
Längs- sowohl wie Querrippen können auch gelocht oder ausgezackt sein, wodurch die Haftung des Spaltstoffes an den in ihn eingebetteten Kühlrohren noch weiter verbessert wird.Longitudinal as well as transverse ribs can also be perforated or jagged, which reduces the adhesion of the Fissile material on the cooling pipes embedded in it is further improved.
Die Verwendung von Rippen ist schon anderweitig bekanntgeworden, wobei sie jedoch —■ im Gegensatz zur Erfindung — zur Wärmeübertragung zwischen einem Körper und einem flüssigen oder gasförmigen Wärmeträger dienen.The use of ribs has already become known elsewhere, but they - ■ in contrast to the invention - for heat transfer between a body and a liquid or gaseous Serve heat transfer medium.
Es kann sich empfehlen, mindestens eine ungekühlte Oberfläche des Spaltstoffes zu kannelieren, wobei die Kannelüren zwischen einander benachbarten Kühlrohren angeordnet sind. Hierdurch lassen sich die 4S Temperaturunterschiede, die an einer ungekühlten Spaltstoffoberfläche entstehen können, niedrig halten, so daß dort eine unnötig hohe Erhitzung einzelner Spaltstoffteile vermieden wird.It may be advisable to flute at least one uncooled surface of the fissile material, the flutes being arranged between adjacent cooling tubes. In this way, let the 4 S temperature differences that may arise on an uncooled gap cloth, kept low so that there is an unnecessarily high heating single fissile material parts is avoided.
Die Verwendung- von Kannelüren ist schon anderweitig bekanntgeworden, wobei sich jedoch — im Gegensatz zur Erfindung — zur Wärmeübertragung dienen. The use of flutes has already become known elsewhere, but - in contrast to the invention - are used for heat transfer.
Weitere Merkmale der Erfindung sollen an Hand Metallisches Brennstoffelement
für einen AtomkernreaktorFurther features of the invention are intended to be based on metallic fuel elements
for an atomic nuclear reactor
Anmelder:Applicant:
Gebrüder Sulzer Aktiengesellschaft,
Winterthur (Schweiz)Sulzer Brothers Aktiengesellschaft,
Winterthur (Switzerland)
Vertreter: Dipl.-Ing. H. Marsch, Patentanwalt,
Schwelm, Drosselstr. 31Representative: Dipl.-Ing. H. Marsch, patent attorney,
Schwelm, Drosselstr. 31
Beanspruchte Priorität:
Schweiz vom 28. Mai 1957Claimed priority:
Switzerland from May 28, 1957
der in der Zeichnung dargestellten Ausführungsbeispiele erläutert werden.the embodiments shown in the drawing are explained.
Die Fig. 1 und 2 zeigen in schematischer Darstellung einen Querschnitt durch ein Brennstoffelement von im wesentlichen zylindrischer Form, wobei 1 ein zentrales Kühlrohr, 2 einen Kranz von acht Kühlrohren und 3 den Spaltstoffkörper bedeutet, in den die Kühlrohre 1 und 2 eingebettet sind.1 and 2 show a schematic representation of a cross section through a fuel element of substantially cylindrical shape, with 1 a central cooling tube, 2 a ring of eight cooling tubes and 3 denotes the fissile material body in which the cooling pipes 1 and 2 are embedded.
In Fig. 1 sind die Kühlrohre 2 und 1 mit Längsrippen 7 und 9 versehen, die in die Spaltstoff-Massenanhäufungen 10 und 8 hineinragen und dort dazu beitragen, die zwischen den einander benachbarten Kühlrohren 2 und 1 und 2 bzw. zwischen den Kühlrohren 2 und 2 und der Außenfläche 11 des Spaltstoffkörpers 3 vorhandenen, für die Wärmeabfuhr maßgebenden Abstände innerhalb der Grenze des Zulässigen zu halten. Der Spaltstoffkörper 3 ist durch eine als sogenanntes »Canning« bekannte Umhüllung 4 gegen Korrosion geschützt, und das gesamte Brennstoffelement ist in ein Aluminiumrohr 5 gesteckt, außerhalb welchem sich der Moderator befindet.In Fig. 1, the cooling tubes 2 and 1 are with longitudinal ribs 7 and 9, which protrude into the fissile material mass accumulations 10 and 8 and there contribute to those between the adjacent cooling tubes 2 and 1 and 2 or between the cooling tubes 2 and 2 and the outer surface 11 of the fissile material body 3 existing, for the heat dissipation decisive distances to be kept within the limit of what is permitted. The fissile material body 3 is by a so-called "Canning" known casing 4 protected against corrosion, and the entire fuel element is in an aluminum tube 5 is inserted, outside which the moderator is located.
In Fig. 2 sind sowohl für das zentrale Kühlrohr 1, als auch für den Kranz von acht Kühlrohren 2 glatte Rohre verwendet. Der Spaltstoffkörper 3 ist kanneliert, wobei die Kannelüren 12 auf seiner Außenfläche zwischen einander benachbarten Kühlrohren 2 angeordnet sind. Die den Spaltstoffkörper 3 mit Zwischenraum umschließende Hülle 6 schützt ihn gegen Korrosion und der durch die Kannelüren 12 noch vergrößerte Zwischenraum dient zur Wärmeisolation für den außerhalb liegenden Moderator.In Fig. 2 are both for the central cooling pipe 1, as well as 2 smooth tubes for the ring of eight cooling tubes. The fissile material body 3 is fluted, wherein the flutes 12 are arranged on its outer surface between adjacent cooling tubes 2 are. The shell 6 enclosing the fissile material body 3 with a gap protects it against corrosion and the space, which is still enlarged by the fluting 12, is used for thermal insulation for the moderator lying outside.
909· 787/535909 787/535
Die Erfindung beschränkt sich nicht auf diese Ausführungsbeispiele. Es können insbesondere auch andere Anordnungen der Kühlrohre sowie andere Bauarten der Spaltstoffelemente verwendet werden.The invention is not restricted to these exemplary embodiments. In particular, other arrangements of the cooling tubes and other types of construction of the fission material elements can also be used.
Claims (5)
Französische Patentschrift Nr. 1 126 414;
»Nucleonics«, 14, 1956, Considered publications:
French Patent No. 1,126,414;
"Nucleonics", 14, 1956,
»Proceedings of the International Conference on4, p. 14;
"Proceedings of the International Conference on
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CH348212T | 1957-04-17 | ||
| CH350724T | 1957-05-28 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1080236B true DE1080236B (en) | 1960-04-21 |
Family
ID=4539817
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DES53842A Pending DE1080236B (en) | 1957-04-17 | 1957-06-08 | Metallic fuel element for an atomic nuclear reactor |
Country Status (5)
| Country | Link |
|---|---|
| BE (1) | BE566754A (en) |
| CH (2) | CH348212A (en) |
| DE (1) | DE1080236B (en) |
| FR (1) | FR1203515A (en) |
| GB (1) | GB824829A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1614932B2 (en) * | 1966-08-08 | 1976-12-16 | United Kingdom Atomic Energy Authority, London | FUEL ELEMENT FOR FAST NUCLEAR REACTORS |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE632489A (en) * | 1962-06-13 | 1900-01-01 | ||
| BE637885A (en) * | 1962-10-22 | |||
| US3156625A (en) * | 1962-10-22 | 1964-11-10 | Harty Harold | Core for a supercritical pressure power reactor |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1126414A (en) * | 1955-02-16 | 1956-11-22 | Thomson Houston Comp Francaise | Further training in nuclear reactors |
-
1957
- 1957-04-17 CH CH348212D patent/CH348212A/en unknown
- 1957-05-28 CH CH350724D patent/CH350724A/en unknown
- 1957-06-08 DE DES53842A patent/DE1080236B/en active Pending
-
1958
- 1958-01-24 FR FR1203515D patent/FR1203515A/en not_active Expired
- 1958-02-10 GB GB4330/58A patent/GB824829A/en not_active Expired
- 1958-04-14 BE BE566754A patent/BE566754A/en unknown
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1126414A (en) * | 1955-02-16 | 1956-11-22 | Thomson Houston Comp Francaise | Further training in nuclear reactors |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1614932B2 (en) * | 1966-08-08 | 1976-12-16 | United Kingdom Atomic Energy Authority, London | FUEL ELEMENT FOR FAST NUCLEAR REACTORS |
Also Published As
| Publication number | Publication date |
|---|---|
| CH348212A (en) | 1960-08-15 |
| CH350724A (en) | 1960-12-15 |
| GB824829A (en) | 1959-12-02 |
| FR1203515A (en) | 1960-01-19 |
| BE566754A (en) | 1958-10-14 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| DE3301965C2 (en) | Shielding element for a reactor core made up of nuclear fuel elements and the shielding elements | |
| DE3783428T2 (en) | CORE FUEL ELEMENT RESISTANT TO INTERACTIONS BETWEEN TABLETS AND PIPES. | |
| DE1187744B (en) | A fuel element designed for a boiler reactor with a neutron moderating coolant | |
| DE1041180B (en) | Fuel element for nuclear reactors | |
| DE1464123A1 (en) | Nuclear reactor | |
| DE1068821B (en) | ||
| DE1201928B (en) | Nuclear reactor fuel element | |
| DE1204345B (en) | Nuclear reactor fuel element | |
| DE1080236B (en) | Metallic fuel element for an atomic nuclear reactor | |
| CH370491A (en) | Thermal insulation for the moderator boiler and the components of liquid-moderated nuclear reactors passed through it | |
| DE1204755B (en) | Fuel assembly for a nuclear reactor | |
| DE3226403C2 (en) | ||
| AT211441B (en) | Metallic fissile material element for an atomic nuclear reactor | |
| DE1200449B (en) | Tubular container for nuclear fuel | |
| DE2825142A1 (en) | CORE FUEL ELEMENT | |
| DE1514558A1 (en) | Spacer for nuclear reactor fuel elements | |
| DE1093495B (en) | Carrying and supporting device for nuclear reactor fuel elements | |
| DE1041174B (en) | Fissile material element for nuclear reactors | |
| DE2816264C2 (en) | Nuclear reactor plant | |
| AT206076B (en) | Atomic nuclear reactor with fissile elements | |
| DE68910879T2 (en) | Fission zone component of a nuclear reactor and operating method for a nuclear reactor. | |
| DE19842486C2 (en) | Fuel element with a qualified distribution of fissile material in the fuel rod | |
| DE102010003809A1 (en) | Reactor core in sodium-cooled fast reactors | |
| DE1489636C (en) | Fuel element for a nuclear reactor | |
| DE1614404C (en) | Fast breeder reactor |