DE1254778B - Device for regulating the power of a nuclear reactor - Google Patents
Device for regulating the power of a nuclear reactorInfo
- Publication number
- DE1254778B DE1254778B DEC36980A DEC0036980A DE1254778B DE 1254778 B DE1254778 B DE 1254778B DE C36980 A DEC36980 A DE C36980A DE C0036980 A DEC0036980 A DE C0036980A DE 1254778 B DE1254778 B DE 1254778B
- Authority
- DE
- Germany
- Prior art keywords
- chains
- chain
- channel
- reactor
- control
- 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
- 230000001105 regulatory effect Effects 0.000 title description 2
- 230000002745 absorbent Effects 0.000 claims description 19
- 239000002250 absorbent Substances 0.000 claims description 19
- 239000000463 material Substances 0.000 claims description 17
- 239000011358 absorbing material Substances 0.000 claims description 5
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 3
- 229910000831 Steel Inorganic materials 0.000 claims description 3
- 229910052796 boron Inorganic materials 0.000 claims description 3
- 239000010959 steel Substances 0.000 claims description 3
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims 2
- 229910045601 alloy Inorganic materials 0.000 claims 2
- 239000000956 alloy Substances 0.000 claims 2
- 229910052782 aluminium Inorganic materials 0.000 claims 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims 2
- 239000002826 coolant Substances 0.000 claims 2
- 229910052726 zirconium Inorganic materials 0.000 claims 2
- 229910000712 Boron steel Inorganic materials 0.000 claims 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims 1
- 230000004308 accommodation Effects 0.000 claims 1
- 238000001816 cooling Methods 0.000 claims 1
- 230000000694 effects Effects 0.000 claims 1
- 238000001595 flow curve Methods 0.000 claims 1
- 239000000446 fuel Substances 0.000 claims 1
- 229910002804 graphite Inorganic materials 0.000 claims 1
- 239000010439 graphite Substances 0.000 claims 1
- 230000005484 gravity Effects 0.000 claims 1
- 229910052751 metal Inorganic materials 0.000 claims 1
- 239000002184 metal Substances 0.000 claims 1
- 230000001681 protective effect Effects 0.000 claims 1
- 230000009257 reactivity Effects 0.000 claims 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
- G21C7/14—Mechanical drive arrangements
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Particle Accelerators (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
Description
DEUTSCHES GERMAN 4M94M9 W> PATENTAMT W> PATENT OFFICE
AUSLEGESCHRIFT G21dEDITORIAL G21d
DeutscheKl.: 21g-21/31German class: 21g-21/31
Nummer: 1254 778Number: 1254 778
Aktenzeichen: C 36980 VIII c/21 gFile number: C 36980 VIII c / 21 g
j[ 254 T78 Anmeldetag: 27.September 1965j [254 T78 filing date: September 27, 1965
Auslegetag: 23. November 1967Opening day: November 23, 1967
Das Hauptpatent 1 237 234 betrifft eine Vorrichtung zur Leistungsregelung eines Kernreaktors mit einem als Rundgliederkette ausgebildeten Regelelement veränderlicher Länge aus Neutronen absorbierendem Material, das sich durch eine Antriebseinrichtung längs eines den Reaktorkern durchquerenden vertikalen Kanals zwischen einer »zusammengelegten« Lage, in der es sich vollständig außerhalb des Reaktorkerns befindet, und einer »gestreckten« Lage, in der es sich im wesentlichen über die gesamte Höhe des Reaktorkernes erstreckt, verschieben und in einen am unteren Ende des Kanals angeordneten transportablen Behälter einbringen läßt. Dieses Neutronen absorbierende Regelelement wird durch wenigstens eine Rundgliederkette gebildet, die mit einem ihrer beiden Enden lösbar an einem Kabel befestigt ist, wobei zur Bewegung der Kette oberhalb des Kanals eine Winde vorgesehen ist, auf die sich das Kabel aufwickeln läßt.The main patent 1 237 234 relates to a device for regulating the output of a nuclear reactor a control element of variable length made of neutron absorbing material, designed as a round link chain Material which is traversed by a drive device along a reactor core vertical channel between a "collapsed" position in which it is completely outside the reactor core, and an "extended" position in which it is essentially Extends over the entire height of the reactor core, move it and move it into one at the lower end of the Can introduce channel arranged transportable container. This neutron absorbing control element is formed by at least one round link chain that is detachable with one of its two ends a cable is attached, a winch being provided for moving the chain above the channel on which the cable can be wound.
Durch eine derartige Anordnung kann man den Raumbedarf und die Länge des Regelelementes, wenn es sich außerhalb des Reaktorkernes befindet, in erheblichem Maße verkleinern, ohne seine Wirksamkeit zu beeinträchtigen, wenn es sich im Innern des Reaktorkernes befindet. Die in dem Hauptpatent vorgeschlagene Verwendung führt jedoch stets dazu, daß das absorbierende Element von unten nach oben in den Reaktorinnenraum durch Befestigung an einem Greifer eingeführt wird, der am unteren Ende des Kabels befestigt ist und mit einem Halterungskopf in Eingriff kommt, an dem die Ketten aus absorbierendem Material befestigt sind.Such an arrangement allows the space requirement and the length of the control element, if it is located outside the reactor core, it can be reduced in size to a considerable extent, without its effectiveness to affect if it is inside the reactor core. The one in the main patent however, the proposed use always results in the absorbent element from bottom to top is introduced into the interior of the reactor by attachment to a gripper, which is at the lower end of the cable and comes into engagement with a mounting head on which the chains of absorbent Material are attached.
Bei einer in dem Hauptptatent beschriebenen Variante ist zur Aufnahme des absorbierenden Elementes eine andere Anordnung vorgesehen, die es ermöglicht, dieses Element nicht von unten nach oben, sondern von oben nach unten in den Reaktorkern einzuführen, wobei im übrigen auch der Materialaustausch erleichtert wird. Zu diesem Zweck ist einerseits der das absorbierende Element enthaltende ausbaubare Behälter am oberen Teil seines Kanals angebracht; andererseits wird dieses Element durch eine einzige Kette gebildet, deren Kettenglieder mit einem Mitnehmerrad zusammenwirken, das oberhalb des Behälters angeordnet ist und das Einführen der Kette von oben nach unten in den Reaktorkern bestimmt. In a variant described in the main patent, the absorbent element is to be received another arrangement is provided, which makes it possible, this element not from the bottom down to be introduced into the reactor core from above, but from top to bottom, with the rest of the material exchange is facilitated. For this purpose, on the one hand, is the one containing the absorbent element removable container attached to the upper part of its channel; on the other hand, this element is through formed a single chain, the chain links cooperate with a driver wheel above of the container and determines the introduction of the chain from top to bottom into the reactor core.
Unter diesen Verhältnissen sowie im Hinblick auf den Ersatz der Kettengruppen durch eine einzige Kette aus stark absorbierendem Material, beispielsweise aus borhaltigem Stahl, kann man den Durchmesser des Kanals, in dem sich die Kette bewegt, aufUnder these circumstances and with a view to replacing the chain groups with a single one Chain made of highly absorbent material, for example made of boron-containing steel, can be adjusted in diameter of the channel in which the chain moves
Vorrichtung zur Leistungsregelung eines
KernreaktorsDevice for power control of a
Nuclear reactor
Zusatz zum Patent: 1237 234Addendum to the patent: 1237 234
Anmelder:Applicant:
Commissariat ä FEnergie Atomique, Paris
Vertreter:Commissariat ä FEnergie Atomique, Paris
Representative:
Dipl.-Ing. R. Beetz und Dipl.-Ing. K. Lamprecht,
Patentanwälte, München 22, Steinsdorfstr. 10Dipl.-Ing. R. Beetz and Dipl.-Ing. K. Lamprecht,
Patent Attorneys, Munich 22, Steinsdorfstr. 10
Als Erfinder benannt:Named as inventor:
Didier Costes, Paris;Didier Costes, Paris;
Jacques Lebey, Viroflay, Seine-et-Oise;Jacques Lebey, Viroflay, Seine-et-Oise;
Roger Martin, Paris (Frankreich)Roger Martin, Paris (France)
Beanspruchte Priorität:Claimed priority:
Frankreich vom 13. Oktober 1964 (991 268) -France of October 13, 1964 (991 268) -
ein Minimum verkleinern. Dieser Kanal braucht lediglich eine Gleitbewegung der einzigen, verhältnismäßig dünnen Kette zu ermöglichen und hierfür eine Führung zu bilden, wobei diese Kette jedenfalls einen wesentlich kleineren Raumbedarf aufweist als die in dem Hauptpatent beschriebene Greifereinrichtung zur Erfassung des Halterungskopfes, an dem bei der älteren Ausführung die Ketten aus absorbierendem Material befestigt sind.reduce it to a minimum. This channel only needs a sliding movement of the only, relatively To enable thin chain and to form a guide for this purpose, this chain at least one has a much smaller space requirement than the gripper device described in the main patent to detect the mounting head on which the chains made of absorbent material in the older version are attached Material are attached.
Der Erfindung liegt nun die Aufgabe zugrunde, die Vorrichtung gemäß dem Hauptpatent dahin weiterzuentwickeln, daß die Handhabung und Einführung eines Steuerelementes, das durch eine oder mehrere Ketten aus absorbierendem Material gebildet wird, von unten nach oben in einem Reaktorkanal von geringem Querschnitt möglich ist, wobei die Verwendung eines Greifers und eines die Ketten tragenden Halterungskopfes vermieden werden soll.The invention is now based on the object of further developing the device according to the main patent in such a way that that the handling and introduction of a control that is controlled by one or more Chains of absorbent material are formed from bottom to top in a reactor duct of low value Cross-section is possible, with the use of a gripper and one carrying the chains Bracket head should be avoided.
Diese Aufgabe wird erfindungsgemäß dadurch gelöst, daß das obere Ende jeder Kette mit einer zweiten Kette aus nicht absorbierendem Material verbunden ist, deren Kettenglieder mit einem am oberen Ende des Kanals vorgesehenen Kettenrad zusammenwirken, und daß das Kettenrad, seine Steuereinrich-This object is achieved in that the upper end of each chain with a second Chain made of non-absorbent material is connected, the chain links with one at the top End of the channel provided sprocket cooperate, and that the sprocket, its control device
709 689/366709 689/366
Claims (2)
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR939251A FR1368891A (en) | 1963-06-25 | 1963-06-25 | Device for regulating the power of a nuclear reactor |
| FR952351A FR84641E (en) | 1963-06-25 | 1963-10-30 | Device for regulating the power of a nuclear reactor |
| FR991268A FR86619E (en) | 1963-06-25 | 1964-10-13 | Device for regulating the power of a nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1254778B true DE1254778B (en) | 1967-11-23 |
Family
ID=27247303
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEC33125A Pending DE1237234B (en) | 1963-06-25 | 1964-06-12 | Device for regulating the power of a nuclear reactor |
| DEC36980A Pending DE1254778B (en) | 1963-06-25 | 1965-09-27 | Device for regulating the power of a nuclear reactor |
Family Applications Before (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEC33125A Pending DE1237234B (en) | 1963-06-25 | 1964-06-12 | Device for regulating the power of a nuclear reactor |
Country Status (8)
| Country | Link |
|---|---|
| BE (2) | BE649518A (en) |
| CH (1) | CH419362A (en) |
| DE (2) | DE1237234B (en) |
| FR (3) | FR1368891A (en) |
| GB (2) | GB1064382A (en) |
| LU (1) | LU46323A1 (en) |
| NL (2) | NL6407176A (en) |
| NO (2) | NO116095B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2058619A1 (en) * | 1970-11-28 | 1972-05-31 | Interatom | Vertical control rod for the quick and safe shutdown of nuclear reactors |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3438856A (en) * | 1967-12-29 | 1969-04-15 | Atomic Energy Commission | Nuclear reactor hydraulic control drive system |
| US4019954A (en) * | 1974-11-07 | 1977-04-26 | Commissariat A L'energie Atomique | Safety device for a nuclear reactor and especially a fast reactor |
| RU2166214C1 (en) * | 2000-02-21 | 2001-04-27 | Государственный научный центр Российской Федерации Всероссийский научно-исследовательский институт неорганических материалов им. акад. А.А. Бочвара | Composite fuel assembly for power control system of nuclear reactor core |
| RU2190886C1 (en) * | 2001-10-31 | 2002-10-10 | Государственное предприятие "Московский завод полиметаллов" | Method for operating pressurized-tube uranium- graphite reactor and control element of pressurized-tube uranium-graphite reactor |
| RU2188470C1 (en) * | 2001-10-31 | 2002-08-27 | Государственное предприятие "Московский завод полиметаллов" | Control element of pressurized-tube uranium- graphite reactor |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE567089A (en) * | 1957-05-08 | 1900-01-01 | ||
| FR1188583A (en) * | 1957-11-12 | 1959-09-23 | Cie D Applic Et De Rech S Atom | Improvements to anti-reactivity control means for nuclear fission reactors and new products resulting from these improvements |
-
1963
- 1963-06-25 FR FR939251A patent/FR1368891A/en not_active Expired
- 1963-10-30 FR FR952351A patent/FR84641E/en not_active Expired
-
1964
- 1964-06-12 DE DEC33125A patent/DE1237234B/en active Pending
- 1964-06-15 LU LU46323D patent/LU46323A1/xx unknown
- 1964-06-15 GB GB24697/64A patent/GB1064382A/en not_active Expired
- 1964-06-16 CH CH781564A patent/CH419362A/en unknown
- 1964-06-19 BE BE649518A patent/BE649518A/xx unknown
- 1964-06-22 NO NO153760A patent/NO116095B/no unknown
- 1964-06-24 NL NL6407176A patent/NL6407176A/xx unknown
- 1964-10-13 FR FR991268A patent/FR86619E/en not_active Expired
-
1965
- 1965-09-27 GB GB41008/65A patent/GB1076708A/en not_active Expired
- 1965-09-27 BE BE670163D patent/BE670163A/xx unknown
- 1965-09-27 DE DEC36980A patent/DE1254778B/en active Pending
- 1965-09-30 NO NO159913A patent/NO116096B/no unknown
- 1965-10-13 NL NL6513241A patent/NL6513241A/xx unknown
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2058619A1 (en) * | 1970-11-28 | 1972-05-31 | Interatom | Vertical control rod for the quick and safe shutdown of nuclear reactors |
Also Published As
| Publication number | Publication date |
|---|---|
| NO116096B (en) | 1969-01-27 |
| NL6407176A (en) | 1964-12-28 |
| FR86619E (en) | 1966-03-11 |
| NO116095B (en) | 1969-01-27 |
| LU46323A1 (en) | 1972-01-01 |
| NL6513241A (en) | 1966-04-14 |
| GB1064382A (en) | 1967-04-05 |
| FR84641E (en) | 1965-03-19 |
| FR1368891A (en) | 1964-08-07 |
| BE670163A (en) | 1966-01-17 |
| CH419362A (en) | 1966-08-31 |
| DE1237234B (en) | 1967-03-23 |
| BE649518A (en) | 1964-10-16 |
| GB1076708A (en) | 1967-07-19 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| DE1539821C3 (en) | Bundled fuel assembly for a nuclear reactor | |
| DE2130598A1 (en) | Device for quickly changing the core of a nuclear reactor | |
| DE1589851A1 (en) | Device for operating the core elements of a reactor core and method for operating this device | |
| DE1254778B (en) | Device for regulating the power of a nuclear reactor | |
| DE1274251B (en) | Feeding system for a nuclear reactor | |
| DE1184865B (en) | Device for generating linear controlled movements | |
| DE1227575B (en) | Control rod device for a nuclear reactor | |
| DE2659430B2 (en) | Transport container for irradiated fuel elements | |
| DE1514964A1 (en) | Nuclear reactor | |
| DE2746391A1 (en) | LOADING / UNLOADING DEVICE FOR FUEL ELEMENT BUNDLES FOR NUCLEAR REACTORS | |
| DE2718305C2 (en) | Fuel storage | |
| DE1122442B (en) | Device connected to a container for remotely controlling objects to be brought into or out of the container | |
| DE2515885A1 (en) | PROTECTIVE DEVICE FOR THE DOME OF THE PRESSURE VESSEL OF A NUCLEAR REACTOR | |
| DE2302831A1 (en) | DEVICE MOVABLE IN THE ROTATING LID FOR HANDLING ROD-SHAPED ELEMENTS IN NUCLEAR REACTORS | |
| DE1489821B1 (en) | Loading and unloading machine for loading fuel channels of heterogeneous nuclear reactors | |
| DE1864390U (en) | LOADING AND REMOVING DEVICE FOR NUCLEAR REACTORS. | |
| DE1539789A1 (en) | Safety device for a nuclear reactor | |
| DE1195876B (en) | Loading machine for nuclear reactor ducts | |
| DE1079229B (en) | System for dismantling and handling cells containing radioactive rods | |
| DE3631018A1 (en) | Method and device for shutting down and moderating nuclear reactors with a side reflector | |
| DE1227159B (en) | Control device for magazines of loading and unloading devices for nuclear reactors | |
| DE1684594A1 (en) | Prestressed concrete container | |
| AT257755B (en) | Device for regulating the power of a nuclear reactor | |
| DE2017912C3 (en) | Grapple | |
| AT263958B (en) | Device for regulating the power of a nuclear reactor |