DE2642352A1 - Nuclear vessel assembled from forged rings by welding - has support flange forged integrally with ring or tube-plate - Google Patents
Nuclear vessel assembled from forged rings by welding - has support flange forged integrally with ring or tube-plateInfo
- Publication number
- DE2642352A1 DE2642352A1 DE19762642352 DE2642352A DE2642352A1 DE 2642352 A1 DE2642352 A1 DE 2642352A1 DE 19762642352 DE19762642352 DE 19762642352 DE 2642352 A DE2642352 A DE 2642352A DE 2642352 A1 DE2642352 A1 DE 2642352A1
- Authority
- DE
- Germany
- Prior art keywords
- forged
- ring
- rings
- tube
- support brackets
- 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
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/24—Supporting, suspending, or setting arrangements, e.g. heat shielding
- F22B37/246—Supporting, suspending, or setting arrangements, e.g. heat shielding for steam generators of the reservoir type, e.g. nuclear steam generators
- F22B37/248—Supporting, suspending, or setting arrangements, e.g. heat shielding for steam generators of the reservoir type, e.g. nuclear steam generators with a vertical cylindrical wall
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Pressure Vessels And Lids Thereof (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
Tragkonsole fii'r BehälterCarrying bracket for containers
Die Erfindung betrifft Tragkonsolen für Behälter die insbesondere in Kernkraftwerken zum Einsatz kommen, wobei die Behälter aus geschmiedeten Ringen (Schüssen), Böden und Rohrplatten zusammengeschweißt sind.The invention relates to support brackets for containers in particular are used in nuclear power plants, the containers made of forged rings (Shots), floors and tube plates are welded together.
Derartige Behälter finden beispielsweise als Reaktordruckbehälter, Dampferzeuger oder Druckhalter Verwendung.Such containers are used, for example, as reactor pressure vessels, Steam generator or pressurizer use.
Bisher werden die als Schweißkonstruktionen ausgebildeten Tragkonsolen an dem Behälter angeschweißt (DT-PS 21 01 965). Die Verbindungsnähte mit dem Behälter als auch die Schweißnähte der Tragkonsolen selbst werden aufgrund des großen Gewichtes der Behälter sehr stark beansprucht. Diese Schweißnähte werden daher im Rahmen der in regelmäßigen Zeitabständen durchzuführenden Behälterinspektionen ebenfalls einer Wiederholungsprüfung mittels Ultraschall unterzogen. Bei der Durchführung der Wiederholungsprüfungen hat es sich als nachteilig gezeigt, daß diese Stellen schwer zugänglich sind, da die Tragkonsolen teilweise von den Abstützkonstruktionen in die der Behälter eingehängt ist verdeckt werden. Weiterhin hat es sich als nachteilig gezeigt, daß durch das Anschweißen der Tragkonsolen unerwünschte Spannungen in den entsprechenden Behälterbereichen entstehen.So far, the support brackets designed as welded constructions welded to the container (DT-PS 21 01 965). The connection seams with the container as well as the weld seams of the support brackets themselves are due to the great weight the container is very heavily used. These welds are therefore in the context of Container inspections to be carried out at regular intervals are also one Repeated ultrasound testing. When performing the repeat exams it has been shown to be disadvantageous that these places are difficult to access because the support brackets are partially suspended from the support structures in which the container is located is to be covered. Furthermore, it has been shown to be disadvantageous that the Welding on the support brackets unwanted stresses in the corresponding container areas develop.
Der Erfindung liegt die Aufgabe zugrunde die Tragkonsolen derart auszubilden, daß keine Schweißnähte auftreten und trotzdem eine homogene Verbindung zwischen Behälter und Tragkonsolen entsteht.The invention is based on the object of designing the support brackets in such a way that that no welds occur and still a homogeneous connection between Container and support brackets are created.
Gelöst wird die Aufgabe dadurch, daß Tragkonsolen und Ring oder Rohrplatte aus einem Stück geschmiedet sind.The object is achieved in that support brackets and ring or tube plate are forged from one piece.
Damit erübrigt sich eine Wiederholungsprüfung und die vorgenannten Nachteile wie Unzugänglichkeit und unerwünschte Spannungen im Verbindungsbereich Behälter/Tragkonsole treten erst gar nicht auf.This means that a repeat test and the aforementioned are superfluous Disadvantages such as inaccessibility and undesirable tension in the connection area The container / support bracket does not appear at all.
In einer weiteren Ausgestaltung der erfindungsgemäßen Anordnung wird vorgeschlagen die Tragkonsolen als umlaufenden Kragen auszubilden.In a further embodiment of the arrangement according to the invention proposed to train the support brackets as a circumferential collar.
Gemäß einer bevorzugten Ausführungsform weisen Ring (Schuß) und Kragen die gleiche Höhe auf.According to a preferred embodiment, the ring (weft) and collar have the same height.
Die Herstellung des Schusses mit Kragen wird durch diese Maßnahme wesentlich erleichtert, da in diesem Falle diese beiden Elemente einen glatten Ring ohne Absätze bilden.The production of the weft with collar is made by this measure much easier, since in this case these two elements form a smooth ring form without paragraphs.
Anhand der schematischen Zeichnungen (Fig. 1- 4) wird die erfindungsgemäße Tragkonsolenausbildung beschrieben.Based on the schematic drawings (Fig. 1- 4) the invention Support bracket training described.
Es zeigen: Fig. 1 im Längsschnitt einen Reaktordruckbehälter mit Tragkonsolen.They show: FIG. 1 in longitudinal section a reactor pressure vessel with support brackets.
Fig. 2 einen Schnitt entlang der Linie A-A der Fig. 1 Fig. 3 eine andere Ausbildung der Tragkonsolen.Fig. 2 is a section along the line A-A of Fig. 1; Fig. 3 is a different training of the support brackets.
Fig. 4 eine weitere Ausbildung der Tragkonsolen.Fig. 4 shows a further embodiment of the support brackets.
Fig. 5 die Anordnung der Tragkonsolen an der Rohrplatte eines Dampferzeugers Die Fig. 1 zeigt einen Reaktordruckbehälter 1 der aus mehreren geschmiedeten Ringen (Schüssen) 2 und einem Boden 8 zusammengeschweißt ist. Die Tragkonsolen 3 bilden mit einem Ring 2 ein einstückiges Schmiedestück und sind segmentförmig am Umfang dieses Ringes angeordnet(Fig. 2). Die Einrichtung 5 zur Abstützung des Reaktordruckbehälters ist strichpunktiert angedeutet.5 shows the arrangement of the support brackets on the tube plate of a steam generator Fig. 1 shows a reactor pressure vessel 1 made of several forged rings (Shots) 2 and a bottom 8 is welded together. The support brackets 3 form with a ring 2 a one-piece forging and are segment-shaped on the circumference arranged this ring (Fig. 2). The device 5 for supporting the reactor pressure vessel is indicated by dash-dotted lines.
Eine andere Ausbildung der Tragkonsolen zeigt Fig. 3. Hier sind die Tragkonsolen als umlaufender Kragen 4 ausgebildet.Another design of the support brackets is shown in Fig. 3. Here are the Support brackets designed as a circumferential collar 4.
Nach einer weiteren vorteilhaften Ausgestaltung (Fig. 4) weist der Kragen 4 die gleiche Höhe (h) auf wie der Ring 2, so daß Kragen 4 und Ring 2 einen glatten Ring ohne Absätze bilden. Diese Ausgestaltung kann selbstverständlich auch bei der Ausbildung nach Fig. 3 zur Anwendung kommen.According to a further advantageous embodiment (FIG. 4), the Collar 4 the same height (h) as the ring 2, so that collar 4 and ring 2 one Form a smooth ring without heels. This configuration can of course also be used come in the training of Fig. 3 for use.
Die Fig. 5 zeigt den Teilschnitt durch einen Dampferzeuger 6 bei dem die Tragkonsolen 3 an die Rohrplatte 7 angeschmiedet sind.Fig. 5 shows the partial section through a steam generator 6 in the the support brackets 3 are forged onto the tube plate 7.
Mit der erfindungsgemäßen Anordnung werden Tragkonsolen für die eingangs genannten Behälter geschaffen, die ohne Schweißverbindungen auskommen und somit keine aufwendige Wiederholungsprüfung erforderlich machen.With the arrangement according to the invention, support brackets for the initially created container that do without welded connections and thus do not require a costly repeat test.
LeerseiteBlank page
Claims (3)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19762642352 DE2642352A1 (en) | 1976-09-21 | 1976-09-21 | Nuclear vessel assembled from forged rings by welding - has support flange forged integrally with ring or tube-plate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19762642352 DE2642352A1 (en) | 1976-09-21 | 1976-09-21 | Nuclear vessel assembled from forged rings by welding - has support flange forged integrally with ring or tube-plate |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE2642352A1 true DE2642352A1 (en) | 1978-03-23 |
Family
ID=5988415
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DE19762642352 Pending DE2642352A1 (en) | 1976-09-21 | 1976-09-21 | Nuclear vessel assembled from forged rings by welding - has support flange forged integrally with ring or tube-plate |
Country Status (1)
| Country | Link |
|---|---|
| DE (1) | DE2642352A1 (en) |
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6389094B1 (en) * | 1997-08-29 | 2002-05-14 | General Electric Company | Integral forged shroud flange for a boiling water reactor |
| WO2010057210A1 (en) * | 2008-11-17 | 2010-05-20 | Nuscale Power, Inc. | Seismically isolated containment vessel |
| CN102859606A (en) * | 2010-02-05 | 2013-01-02 | 斯姆尔有限公司 | Nuclear reactor system having natural circulation of primary coolant |
| EP2852955A4 (en) * | 2012-05-21 | 2016-07-27 | Smr Inventec Llc | Passive reactor containment protection system |
| US9881703B2 (en) | 2013-12-31 | 2018-01-30 | Nuscale Power, Llc | Seismic attenuation system for a nuclear reactor |
| US10403407B2 (en) | 2013-12-31 | 2019-09-03 | Nuscale Power, Llc | Managing dynamic forces on a nuclear reactor system |
| US10665354B2 (en) | 2012-05-21 | 2020-05-26 | Smr Inventec, Llc | Loss-of-coolant accident reactor cooling system |
| US10672523B2 (en) | 2012-05-21 | 2020-06-02 | Smr Inventec, Llc | Component cooling water system for nuclear power plant |
| US10720249B2 (en) | 2012-05-21 | 2020-07-21 | Smr Inventec, Llc | Passive reactor cooling system |
| US11901088B2 (en) | 2012-05-04 | 2024-02-13 | Smr Inventec, Llc | Method of heating primary coolant outside of primary coolant loop during a reactor startup operation |
| US11935663B2 (en) | 2012-05-21 | 2024-03-19 | Smr Inventec, Llc | Control rod drive system for nuclear reactor |
-
1976
- 1976-09-21 DE DE19762642352 patent/DE2642352A1/en active Pending
Cited By (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6389094B1 (en) * | 1997-08-29 | 2002-05-14 | General Electric Company | Integral forged shroud flange for a boiling water reactor |
| WO2010057210A1 (en) * | 2008-11-17 | 2010-05-20 | Nuscale Power, Inc. | Seismically isolated containment vessel |
| US20100124304A1 (en) * | 2008-11-17 | 2010-05-20 | Nuscale Power, Inc. | Seismically isolated containment vessel |
| CN102272858A (en) * | 2008-11-17 | 2011-12-07 | 纽斯高动力有限公司 | Seismically isolated containment vessel |
| US8848855B2 (en) * | 2008-11-17 | 2014-09-30 | Nuscale Power, Llc | Seismically isolated containment vessel |
| CN102272858B (en) * | 2008-11-17 | 2016-01-06 | 纽斯高动力有限责任公司 | Shock insulation containment vessel |
| CN102859606A (en) * | 2010-02-05 | 2013-01-02 | 斯姆尔有限公司 | Nuclear reactor system having natural circulation of primary coolant |
| US11901088B2 (en) | 2012-05-04 | 2024-02-13 | Smr Inventec, Llc | Method of heating primary coolant outside of primary coolant loop during a reactor startup operation |
| US9786393B2 (en) | 2012-05-21 | 2017-10-10 | Smr Inventec, Llc | Passive reactor containment protection system |
| US10665354B2 (en) | 2012-05-21 | 2020-05-26 | Smr Inventec, Llc | Loss-of-coolant accident reactor cooling system |
| US10672523B2 (en) | 2012-05-21 | 2020-06-02 | Smr Inventec, Llc | Component cooling water system for nuclear power plant |
| US10720249B2 (en) | 2012-05-21 | 2020-07-21 | Smr Inventec, Llc | Passive reactor cooling system |
| EP2852955A4 (en) * | 2012-05-21 | 2016-07-27 | Smr Inventec Llc | Passive reactor containment protection system |
| US11935663B2 (en) | 2012-05-21 | 2024-03-19 | Smr Inventec, Llc | Control rod drive system for nuclear reactor |
| US9881703B2 (en) | 2013-12-31 | 2018-01-30 | Nuscale Power, Llc | Seismic attenuation system for a nuclear reactor |
| US10403407B2 (en) | 2013-12-31 | 2019-09-03 | Nuscale Power, Llc | Managing dynamic forces on a nuclear reactor system |
| USRE47965E1 (en) | 2013-12-31 | 2020-04-28 | Nuscale Power Llc | Seismic attenuation system for a nuclear reactor |
| US10964437B2 (en) | 2013-12-31 | 2021-03-30 | Nuscale Power, Llc | Managing dynamic forces on a nuclear reactor system |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| OAM | Search report available | ||
| OAP | Request for examination filed | ||
| OC | Search report available | ||
| OD | Request for examination | ||
| OHW | Rejection |