FR2243499B1 - - Google Patents
Info
- Publication number
- FR2243499B1 FR2243499B1 FR7332374A FR7332374A FR2243499B1 FR 2243499 B1 FR2243499 B1 FR 2243499B1 FR 7332374 A FR7332374 A FR 7332374A FR 7332374 A FR7332374 A FR 7332374A FR 2243499 B1 FR2243499 B1 FR 2243499B1
- Authority
- FR
- France
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
-
- 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
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
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- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Examining Or Testing Airtightness (AREA)
Priority Applications (5)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7332374A FR2243499B1 (pt-PT) | 1973-09-07 | 1973-09-07 | |
| GB3602274A GB1448927A (en) | 1973-09-07 | 1974-08-15 | Method for continuous testing of the leak-jacket of a sodium- cooled fast reactor |
| DE2441999A DE2441999C3 (de) | 1973-09-07 | 1974-09-02 | Sicherheitsbehälter für einen schnellen, natriumgekühlten Kernreaktor |
| IT69709/74A IT1020736B (it) | 1973-09-07 | 1974-09-06 | Procedimento per il controllo per manente dell ermeticita e della te di un reattore e reattore utilizzan te il procedimento |
| US05/693,879 US4076585A (en) | 1973-09-07 | 1976-06-08 | Method of continuous testing for leak-tightness and mechanical resistance of a reactor vessel jacket and a reactor in which said method is employed |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7332374A FR2243499B1 (pt-PT) | 1973-09-07 | 1973-09-07 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| FR2243499A1 FR2243499A1 (pt-PT) | 1975-04-04 |
| FR2243499B1 true FR2243499B1 (pt-PT) | 1977-07-15 |
Family
ID=9124780
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| FR7332374A Expired FR2243499B1 (pt-PT) | 1973-09-07 | 1973-09-07 |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US4076585A (pt-PT) |
| DE (1) | DE2441999C3 (pt-PT) |
| FR (1) | FR2243499B1 (pt-PT) |
| GB (1) | GB1448927A (pt-PT) |
| IT (1) | IT1020736B (pt-PT) |
Families Citing this family (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1567949A (en) * | 1976-08-12 | 1980-05-21 | Nuclear Power Co Ltd | Liquid metal cooled nuclear reactor constructions |
| SE410665B (sv) * | 1978-03-06 | 1979-10-22 | Asea Atom Ab | Biologisk skerm avsedd att omsluta en trycktank i en kernreaktor |
| DE2856013C2 (de) * | 1978-12-23 | 1985-03-14 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | Innenwandstruktur eines Spannbetonbehälters mit Leckgasleitungen zur Linerleckortung |
| JPS5713397A (en) * | 1980-06-30 | 1982-01-23 | Tokyo Shibaura Electric Co | Lining tank and its manufacture |
| US4495137A (en) * | 1981-01-21 | 1985-01-22 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Nuclear reactor |
| DE3127219A1 (de) * | 1981-07-10 | 1983-01-27 | GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen | Abschirmtransport- und/oder abschirmlagerbehaelter |
| DE3245022A1 (de) * | 1982-12-06 | 1984-06-07 | Hochtemperatur-Reaktorbau GmbH, 5000 Köln | Graphit-deckenreflektor fuer einen hochtemperatur-kleinreaktor |
| GB2157880B (en) * | 1984-04-19 | 1988-02-10 | Westinghouse Electric Corp | An improved nuclear reactor plant construction |
| CA2029545C (en) * | 1990-11-09 | 1996-04-23 | Jerry Edward Dick | Continuous containment monitoring with containment pressure fluctuation |
| US6519308B1 (en) * | 1999-06-11 | 2003-02-11 | General Electric Company | Corrosion mitigation system for liquid metal nuclear reactors with passive decay heat removal systems |
| FI20040387A0 (fi) * | 2004-03-11 | 2004-03-11 | Sulo Toivo Luomala | Paineastia |
| US8588360B2 (en) | 2007-11-15 | 2013-11-19 | The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University | Evacuated containment vessel for a nuclear reactor |
| US9984777B2 (en) | 2007-11-15 | 2018-05-29 | Nuscale Power, Llc | Passive emergency feedwater system |
| US8687759B2 (en) * | 2007-11-15 | 2014-04-01 | The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University | Internal dry containment vessel for a nuclear reactor |
| DE102009050214A1 (de) * | 2009-10-22 | 2011-07-28 | BAXI INNOTECH GmbH, 20539 | Vorrichtung zum Führen mindestens eines Fluids und Brennstoffzellenheizgerät |
| US8477040B2 (en) | 2011-01-26 | 2013-07-02 | Joseph D Jatcko | Method and apparatus for testing the integrity of a tank |
| CN113990538A (zh) * | 2021-10-22 | 2022-01-28 | 中国原子能科学研究院 | 反应堆及其堆容器 |
| WO2024091724A2 (en) * | 2022-08-19 | 2024-05-02 | Abilene Christian University | Nuclear reactor thermal management system |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| NL248734A (pt-PT) * | 1959-02-24 | |||
| US3288998A (en) * | 1963-08-16 | 1966-11-29 | United Eng & Constructors Inc | Wall structure for a nuclear reactor containment vessel |
| GB1258763A (pt-PT) * | 1968-02-23 | 1971-12-30 | ||
| FR1589148A (pt-PT) * | 1968-09-13 | 1970-03-23 | ||
| FR2096874B1 (pt-PT) * | 1970-07-09 | 1973-08-10 | Commissariat Energie Atomique |
-
1973
- 1973-09-07 FR FR7332374A patent/FR2243499B1/fr not_active Expired
-
1974
- 1974-08-15 GB GB3602274A patent/GB1448927A/en not_active Expired
- 1974-09-02 DE DE2441999A patent/DE2441999C3/de not_active Expired
- 1974-09-06 IT IT69709/74A patent/IT1020736B/it active
-
1976
- 1976-06-08 US US05/693,879 patent/US4076585A/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| DE2441999A1 (de) | 1975-03-13 |
| GB1448927A (en) | 1976-09-08 |
| IT1020736B (it) | 1977-12-30 |
| DE2441999B2 (de) | 1978-07-06 |
| DE2441999C3 (de) | 1979-03-22 |
| FR2243499A1 (pt-PT) | 1975-04-04 |
| US4076585A (en) | 1978-02-28 |
Similar Documents
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| ST | Notification of lapse |