FR1485611A - Safety closing device placed between the compartments of a safety building for nuclear reactors - Google Patents
Safety closing device placed between the compartments of a safety building for nuclear reactorsInfo
- Publication number
- FR1485611A FR1485611A FR56535A FR56535A FR1485611A FR 1485611 A FR1485611 A FR 1485611A FR 56535 A FR56535 A FR 56535A FR 56535 A FR56535 A FR 56535A FR 1485611 A FR1485611 A FR 1485611A
- Authority
- FR
- France
- Prior art keywords
- safety
- compartments
- closing device
- device placed
- nuclear reactors
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
- G21C9/008—Pressure suppression by rupture-discs or -diaphragms
-
- 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)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR56535A FR1485611A (en) | 1965-04-07 | 1966-04-05 | Safety closing device placed between the compartments of a safety building for nuclear reactors |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DES0096428 | 1965-04-07 | ||
FR56535A FR1485611A (en) | 1965-04-07 | 1966-04-05 | Safety closing device placed between the compartments of a safety building for nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
FR1485611A true FR1485611A (en) | 1967-06-23 |
Family
ID=25998039
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR56535A Expired FR1485611A (en) | 1965-04-07 | 1966-04-05 | Safety closing device placed between the compartments of a safety building for nuclear reactors |
Country Status (1)
Country | Link |
---|---|
FR (1) | FR1485611A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4238289A (en) * | 1974-01-23 | 1980-12-09 | Westinghouse Electric Corp. | Nuclear reactor condenser door arrangement |
WO2000031748A1 (en) * | 1998-11-20 | 2000-06-02 | Siemens Aktiengesellschaft | Nuclear power installation |
EP1122743A1 (en) * | 2000-01-24 | 2001-08-08 | General Electric Company | Systems and methods for maintaining integrity of a primary containment vessel in a nuclear reactor |
-
1966
- 1966-04-05 FR FR56535A patent/FR1485611A/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4238289A (en) * | 1974-01-23 | 1980-12-09 | Westinghouse Electric Corp. | Nuclear reactor condenser door arrangement |
WO2000031748A1 (en) * | 1998-11-20 | 2000-06-02 | Siemens Aktiengesellschaft | Nuclear power installation |
EP1122743A1 (en) * | 2000-01-24 | 2001-08-08 | General Electric Company | Systems and methods for maintaining integrity of a primary containment vessel in a nuclear reactor |
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