FR2041724A1 - Gas circuit for gas cooled nuclear reactor - Google Patents
Gas circuit for gas cooled nuclear reactorInfo
- Publication number
- FR2041724A1 FR2041724A1 FR6915505A FR6915505A FR2041724A1 FR 2041724 A1 FR2041724 A1 FR 2041724A1 FR 6915505 A FR6915505 A FR 6915505A FR 6915505 A FR6915505 A FR 6915505A FR 2041724 A1 FR2041724 A1 FR 2041724A1
- Authority
- FR
- France
- Prior art keywords
- exchanger
- gas
- core
- caisson
- walls
- 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.)
- Withdrawn
Links
- 239000011513 prestressed concrete Substances 0.000 abstract 1
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
- G21C1/326—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
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
- G21C13/036—Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
Abstract
Reactor core is placed in prestressed concrete caisson, in the walls of which are a number of vertical shafts. Each of these contains a heat exchanger, with connections at bottom for secondary heat exchange medium inlet and outlet. An annular space between exchanger and shaft walls allows flow of cooled gas from exit of exchanger back to core. A first tube passing through the caisson walls links exchanger to a collector for hot gas in the core. A second tube passes through caisson and exits into core near first tube's exit point and is linked to annular space. A blower above exchanger causes gas circulation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR6915505A FR2041724A1 (en) | 1969-05-13 | 1969-05-13 | Gas circuit for gas cooled nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR6915505A FR2041724A1 (en) | 1969-05-13 | 1969-05-13 | Gas circuit for gas cooled nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| FR2041724A1 true FR2041724A1 (en) | 1971-02-05 |
Family
ID=9033986
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| FR6915505A Withdrawn FR2041724A1 (en) | 1969-05-13 | 1969-05-13 | Gas circuit for gas cooled nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| FR (1) | FR2041724A1 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2408804A1 (en) * | 1977-11-15 | 1979-06-08 | Steinmueller Gmbh L & C | HIGH TEMPERATURE GAS OUTLET IN THE FORM OF A BEAM OF TUBES FOR PRESSURE CONTAINER OF CAST IRON OR CONCRETE |
| EP0006800A1 (en) * | 1978-06-23 | 1980-01-09 | COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel | Liquid-metal cooled fast nuclear reactor |
-
1969
- 1969-05-13 FR FR6915505A patent/FR2041724A1/en not_active Withdrawn
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2408804A1 (en) * | 1977-11-15 | 1979-06-08 | Steinmueller Gmbh L & C | HIGH TEMPERATURE GAS OUTLET IN THE FORM OF A BEAM OF TUBES FOR PRESSURE CONTAINER OF CAST IRON OR CONCRETE |
| EP0006800A1 (en) * | 1978-06-23 | 1980-01-09 | COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel | Liquid-metal cooled fast nuclear reactor |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| RE | Withdrawal of published application |