ES481830A1 - Dispositivo de sustentacion y protecion de un conjunto de aparatos en conexion permanente, tales como una cuba de reactor nuclear asociada con generadores de vapor. - Google Patents
Dispositivo de sustentacion y protecion de un conjunto de aparatos en conexion permanente, tales como una cuba de reactor nuclear asociada con generadores de vapor.Info
- Publication number
- ES481830A1 ES481830A1 ES481830A ES481830A ES481830A1 ES 481830 A1 ES481830 A1 ES 481830A1 ES 481830 A ES481830 A ES 481830A ES 481830 A ES481830 A ES 481830A ES 481830 A1 ES481830 A1 ES 481830A1
- Authority
- ES
- Spain
- Prior art keywords
- supporting
- generators
- steam generators
- shielding device
- nuclear steam
- 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.)
- Expired
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)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Plasma & Fusion (AREA)
- Thermal Sciences (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
- Cable Accessories (AREA)
- Casings For Electric Apparatus (AREA)
- Magnetic Resonance Imaging Apparatus (AREA)
Abstract
Dispositivo de sustentación y protección de un conjunto de aparatos en conexión permanente, tales como una cuba de reactor nuclear asociada con generadores de vapor para constituir el circuito primario de una caldera nuclear, y del tipo que comprende una estructura metálica que envuelve al menos parcialmente a dicho conjunto y lo sostiene por medio de órganos de apoyo, caracterizado porque con vistas a mantener el eje de la cuba y de sus generadores asociados rigurosamente fijo en dicha estructura, la misma se compone de una parte, de una estructura inferior sobre la que reposa la cuba con sus generadores por medio de elementos en saliente soldados sobre la cuba y los generadores y que presentan una forma poligonal en sección transversal para apoyarse sobre cojinetes de mandrilado poligonal correspondientes provistos en dicha estructura, y de otra parte, de una estructura superior formando tapa cuya parte central forma con preferencia las paredes de la piscina de descarga de la cuba y cuyaparte externa forma paredes laterales que envuelven a dichos generadores a la vez que los mantienen dentro de la estructura.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7820405A FR2434461A1 (fr) | 1978-06-23 | 1978-06-23 | Nouveau dispositif de supportage et de protection pour chaudieres nucleaires |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| ES481830A1 true ES481830A1 (es) | 1980-08-16 |
Family
ID=9210489
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| ES481830A Expired ES481830A1 (es) | 1978-06-23 | 1979-06-22 | Dispositivo de sustentacion y protecion de un conjunto de aparatos en conexion permanente, tales como una cuba de reactor nuclear asociada con generadores de vapor. |
Country Status (9)
| Country | Link |
|---|---|
| US (1) | US4511532A (es) |
| EP (1) | EP0012042B1 (es) |
| JP (1) | JPS5517094A (es) |
| AT (1) | ATE626T1 (es) |
| CA (1) | CA1147871A (es) |
| DE (1) | DE2961956D1 (es) |
| ES (1) | ES481830A1 (es) |
| FR (1) | FR2434461A1 (es) |
| SU (1) | SU1036256A3 (es) |
Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2533064B2 (fr) * | 1981-11-09 | 1986-05-16 | Alsthom Atlantique | Local nucleaire avec chaudiere et enceinte de confinement resistant aux seismes |
| FR2526572B1 (fr) * | 1982-05-06 | 1988-04-15 | Commissariat Energie Atomique | Dispositif de supportage de chaudiere nucleaire |
| US5152253A (en) * | 1991-01-28 | 1992-10-06 | Westinghouse Electric Corp. | Vessel structural support system |
| US5268944A (en) * | 1992-06-24 | 1993-12-07 | Westinghouse Electric Corp. | Nuclear reactor having a polyhedral primary shield and removable vessel insulation |
| CN104508754B (zh) | 2012-04-25 | 2017-04-05 | Smr发明技术有限公司 | 核蒸汽供给系统 |
| US12512230B2 (en) | 2012-05-04 | 2025-12-30 | Smr Inventec, Llc | Passively-cooled spent nuclear fuel pool 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 |
| WO2013188018A1 (en) | 2012-05-04 | 2013-12-19 | Holtec International, Inc. | Space saver flanged joint for a nuclear reactor vessel |
| CN106098109A (zh) * | 2016-07-05 | 2016-11-09 | 上海核工程研究设计院 | 一种核反应堆系统 |
| CN105931677A (zh) * | 2016-07-05 | 2016-09-07 | 上海核工程研究设计院 | 一种核反应堆系统 |
| US12057240B2 (en) * | 2018-07-02 | 2024-08-06 | Invap S.E. | Compact reactor with horizontal steam generators and pressurizer |
| US20230127207A1 (en) * | 2019-12-23 | 2023-04-27 | Terrapower, Llc | Methods and systems for improved test fuel reactor |
Family Cites Families (30)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CA540455A (en) * | 1957-05-07 | M. Dow Dewey | Vacuum cleaner filter bag safety device | |
| FR335545A (fr) * | 1903-09-25 | 1904-01-29 | Jacques Rebour | Joint de cardan pour transmission de mouvement |
| FR3036E (fr) * | 1903-09-25 | 1904-08-12 | Jacques Rebour | Joint de cardan pour transmission de mouvement |
| DE840335C (de) * | 1949-08-17 | 1952-06-05 | Windenfabrik Gottfried Schober | Wellenkupplung mit einem in eine Muffe des einen Wellenendes eingesteckten UEbertragungsteil |
| US2952019A (en) * | 1956-05-07 | 1960-09-06 | Schlumberger Well Sureying Cor | Methods and apparatus for investigating materials |
| GB889758A (en) * | 1958-01-31 | 1962-02-21 | English Electric Co Ltd | Improvements relating to nuclear reactors |
| NL242128A (es) * | 1958-08-11 | |||
| US3190807A (en) * | 1960-09-07 | 1965-06-22 | Combustion Eng | Pressure tube reactor |
| US3045724A (en) * | 1960-10-07 | 1962-07-24 | Mitchell Robert Irving | Circular saw guide and square attachment |
| US3254399A (en) * | 1962-11-23 | 1966-06-07 | Crawford Fitting Co | Bulkhead support and fastening means |
| US3264863A (en) * | 1963-05-27 | 1966-08-09 | Maropis Nicholas | Method and apparatus for detecting incipient boiling of a liquid |
| US3353875A (en) * | 1964-07-27 | 1967-11-21 | Maxwell R Karge | Linear motion bearing assembly |
| FR1440418A (fr) * | 1964-08-28 | 1966-05-27 | Reactor Centrum Nederland | Construction de support d'un réacteur nucléaire |
| FR1489557A (fr) * | 1965-08-17 | 1967-07-21 | Reactor Centrum Nederland | Support de réacteur permettant la dilatation des conduites qui s'y raccordent |
| US3454466A (en) * | 1967-12-29 | 1969-07-08 | Atomic Energy Commission | Nuclear reactor containment system for metropolitan sites |
| AT312112B (de) * | 1970-06-23 | 1973-12-27 | Waagner Biro Ag | Tragkonstruktion |
| US3984282A (en) * | 1970-08-05 | 1976-10-05 | Nucledyne Engineering Corporation | Passive containment system for a nuclear reactor |
| US3659909A (en) * | 1970-10-26 | 1972-05-02 | James Egbert | Bearing constructions |
| US3716451A (en) * | 1970-11-30 | 1973-02-13 | Stone & Webster Eng Corp | Nuclear reactor power plant structural support system |
| US3937651A (en) * | 1971-05-21 | 1976-02-10 | Siemens Aktiengesellschaft | Nuclear reactor facility |
| BE792742A (fr) * | 1971-12-21 | 1973-06-14 | Babcock & Wilcox Co | Perfectionnements aux echangeurs de chaleur |
| US3771499A (en) * | 1971-12-30 | 1973-11-13 | Combustion Eng | Steam generator cradle support |
| FR2214938B1 (es) * | 1973-01-23 | 1976-05-14 | Commissariat Energie Atomique | |
| US3947322A (en) * | 1973-05-25 | 1976-03-30 | Siemens Aktiengesellschaft | Reactor pressure vessel support arrangement |
| US3916944A (en) * | 1973-06-28 | 1975-11-04 | Combustion Eng | Reactor vessel supported by flexure member |
| DE2341489C3 (de) * | 1973-08-16 | 1979-02-22 | Siemens Ag, 1000 Berlin Und 8000 Muenchen | Kernreaktoranlage |
| AT336056B (de) * | 1974-01-10 | 1977-04-12 | Voest Ag | Loslager fur den tragzapfen eines konverters |
| FR2311388A1 (fr) * | 1975-05-12 | 1976-12-10 | Commissariat Energie Atomique | Dispositif de supportage d'une chaudiere nucleaire |
| DE2706164A1 (de) * | 1977-02-14 | 1978-08-17 | Kraftwerk Union Ag | Aus kuehlmittelpumpe und dampferzeuger bestehende baueinheit, vorzugsweise fuer berstgesicherte kernreaktoranlagen |
| US4115194A (en) * | 1977-02-22 | 1978-09-19 | The Babcock & Wilcox Company | Reactor pressure vessel support |
-
1978
- 1978-06-23 FR FR7820405A patent/FR2434461A1/fr active Granted
-
1979
- 1979-06-14 CA CA000329822A patent/CA1147871A/en not_active Expired
- 1979-06-15 US US06/048,802 patent/US4511532A/en not_active Expired - Lifetime
- 1979-06-18 EP EP79400401A patent/EP0012042B1/fr not_active Expired
- 1979-06-18 DE DE7979400401T patent/DE2961956D1/de not_active Expired
- 1979-06-18 AT AT79400401T patent/ATE626T1/de not_active IP Right Cessation
- 1979-06-22 SU SU792784923A patent/SU1036256A3/ru active
- 1979-06-22 ES ES481830A patent/ES481830A1/es not_active Expired
- 1979-06-23 JP JP7959579A patent/JPS5517094A/ja active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| EP0012042B1 (fr) | 1982-01-27 |
| CA1147871A (en) | 1983-06-07 |
| JPS5517094A (en) | 1980-02-06 |
| US4511532A (en) | 1985-04-16 |
| EP0012042A1 (fr) | 1980-06-11 |
| FR2434461B1 (es) | 1982-11-26 |
| ATE626T1 (de) | 1982-02-15 |
| FR2434461A1 (fr) | 1980-03-21 |
| SU1036256A3 (ru) | 1983-08-15 |
| DE2961956D1 (en) | 1982-03-11 |
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