FR1375157A - Nuclear steam production facilities - Google Patents
Nuclear steam production facilitiesInfo
- Publication number
- FR1375157A FR1375157A FR945469A FR945469A FR1375157A FR 1375157 A FR1375157 A FR 1375157A FR 945469 A FR945469 A FR 945469A FR 945469 A FR945469 A FR 945469A FR 1375157 A FR1375157 A FR 1375157A
- Authority
- FR
- France
- Prior art keywords
- production facilities
- steam production
- nuclear steam
- nuclear
- facilities
- 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
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/322—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/08—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
- G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/02—Biological shielding ; Neutron or gamma shielding
- G21C11/04—Biological shielding ; Neutron or gamma shielding on waterborne craft
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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
-
- 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)
- Plasma & Fusion (AREA)
- Life Sciences & Earth Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Chemical & Material Sciences (AREA)
- General Health & Medical Sciences (AREA)
- Molecular Biology (AREA)
- Health & Medical Sciences (AREA)
- Biomedical Technology (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR945469A FR1375157A (en) | 1962-08-23 | 1963-08-23 | Nuclear steam production facilities |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US219086A US3151034A (en) | 1962-08-23 | 1962-08-23 | Consolidated nuclear steam generator arrangement |
FR945469A FR1375157A (en) | 1962-08-23 | 1963-08-23 | Nuclear steam production facilities |
Publications (1)
Publication Number | Publication Date |
---|---|
FR1375157A true FR1375157A (en) | 1964-10-16 |
Family
ID=26203008
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR945469A Expired FR1375157A (en) | 1962-08-23 | 1963-08-23 | Nuclear steam production facilities |
Country Status (1)
Country | Link |
---|---|
FR (1) | FR1375157A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2482355A1 (en) * | 1980-05-06 | 1981-11-13 | Tokyo Shibaura Electric Co | NUCLEAR REACTOR USING LIQUID METAL FOR PRIMARY AND SECONDARY HEATERS |
WO1991004559A1 (en) * | 1989-09-15 | 1991-04-04 | Ecs-Power Systems Inc. | Nuclear reactor plant |
US6594333B2 (en) * | 2001-11-16 | 2003-07-15 | Japan Nuclear Cycle Development Institute | Thermal load reducing system for nuclear reactor vessel |
-
1963
- 1963-08-23 FR FR945469A patent/FR1375157A/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2482355A1 (en) * | 1980-05-06 | 1981-11-13 | Tokyo Shibaura Electric Co | NUCLEAR REACTOR USING LIQUID METAL FOR PRIMARY AND SECONDARY HEATERS |
WO1991004559A1 (en) * | 1989-09-15 | 1991-04-04 | Ecs-Power Systems Inc. | Nuclear reactor plant |
US6594333B2 (en) * | 2001-11-16 | 2003-07-15 | Japan Nuclear Cycle Development Institute | Thermal load reducing system for nuclear reactor vessel |
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