GB897483A - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- GB897483A GB897483A GB27837/59A GB2783759A GB897483A GB 897483 A GB897483 A GB 897483A GB 27837/59 A GB27837/59 A GB 27837/59A GB 2783759 A GB2783759 A GB 2783759A GB 897483 A GB897483 A GB 897483A
- Authority
- GB
- United Kingdom
- Prior art keywords
- tubes
- reactor
- water
- conduit
- heat exchanger
- 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
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/02—Reactor and engine structurally combined, e.g. portable
-
- 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
-
- 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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
897,483. Nuclear reactors. COMMISSARIAT A L'ENERGIE ATOMIQUE. Aug. 14 1959 [Aug. 14, 1958], No. 27837/59. Class 39(4). A boiling water reactor supplying steam to a heat exchanger or turbine is surrounded by an annular protective tank filled with water and containing a first group of tubes forming part of a cooling circuit and a second group of tubes, of which the inlet header communicates with the heat exchanger or turbine circuit and the outlet header communicates with the reactor vessel to return to it water condensed in the second group of tubes, the circuit thus formed operating with natural circulation and short-circuiting the heat exchanger or turbine, at least one valve being provided to check the entry of steam from the reactor into the second group of tubes. Fig. 1 shows diagrammatically a boiling water reactor suitable for use on a ship, the reactor vessel 1 containing water 2 in an external reflector and discharging steam through a conduit 3 to a heat exchanger (not shown), water being returned to the reactor through conduit 4. Round the container 1 is a biological shield tank 6 filled with water and containing several layers of metal plates, Fig. 2 (not shown); the water in the tank is cooled by sea water flowing through tubes 8. A second set of tubes 13 in the tank 6 are connected through valves 19, 20 to conduit 3, through a normally open valve 21 to a duct 26 leading to the reflector of the reactor, and through valve 22 to conduit 4. Valve 20 opens automatically if there is excess pressure in conduit 3, and if the reactor stops valves 19 and 20 are opened to short-circuit the heat exchanger through tubes 13, natural circulation being set up through conduit 3, tube 13 and duct 26. To enable the reactor to be cooled when fuel is being replaced a pump 28 is included in a circuit running from the top of tubes 13 to the duct 26 so that water can be pumped from the reflector through duct 26 and pump 28, through tubes 13, and through valves 22 (valve 21 being closed) to conduit 4 and into the reactor. The sets of tubes 8, 13 may be separated inside the tank 6 by partitions provided with apertures at the top and bottom, Fig. 2 (not shown).
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR772524 | 1958-08-14 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB897483A true GB897483A (en) | 1962-05-30 |
Family
ID=8707259
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB27837/59A Expired GB897483A (en) | 1958-08-14 | 1959-08-14 | Improvements in or relating to nuclear reactors |
Country Status (5)
| Country | Link |
|---|---|
| BE (1) | BE581548A (en) |
| DE (1) | DE1137810B (en) |
| FR (1) | FR1211537A (en) |
| GB (1) | GB897483A (en) |
| LU (1) | LU37544A1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113345609A (en) * | 2021-06-02 | 2021-09-03 | 哈尔滨工程大学 | External cooling system for pressure vessel of floating nuclear power station |
Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| NL260249A (en) * | 1960-01-20 | |||
| DE1143936B (en) * | 1960-03-25 | 1963-02-21 | Licentia Gmbh | Device for emergency cooling of a superheater reactor |
| NL265810A (en) * | 1960-06-17 | 1900-01-01 | ||
| DE1170563B (en) * | 1961-03-14 | 1964-05-21 | Licentia Gmbh | Emergency condensation system for nuclear reactors |
| DE1185309B (en) * | 1961-04-11 | 1965-01-14 | Licentia Gmbh | Device for emergency cooling of a nuclear reactor |
| FR2497387B1 (en) * | 1980-12-31 | 1985-09-06 | Framatome Sa | METHOD AND DEVICE FOR COOLING THE PRIMARY CIRCUIT OF A PRESSURE WATER NUCLEAR REACTOR |
| CN111508623B (en) * | 2020-04-29 | 2022-07-15 | 中国核动力研究设计院 | Overpressure protection device for pressure-bearing containment vessel for ship and application of overpressure protection device |
| CN114121319B (en) * | 2021-11-23 | 2022-08-05 | 西安交通大学 | Single-rod boiling critical test device and method for nuclear reactor under six-degree-of-freedom motion condition |
-
1958
- 1958-08-14 FR FR1211537D patent/FR1211537A/en not_active Expired
-
1959
- 1959-08-10 DE DEC19581A patent/DE1137810B/en active Pending
- 1959-08-10 BE BE581548A patent/BE581548A/en unknown
- 1959-08-11 LU LU37544A patent/LU37544A1/xx unknown
- 1959-08-14 GB GB27837/59A patent/GB897483A/en not_active Expired
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113345609A (en) * | 2021-06-02 | 2021-09-03 | 哈尔滨工程大学 | External cooling system for pressure vessel of floating nuclear power station |
| CN113345609B (en) * | 2021-06-02 | 2022-03-01 | 哈尔滨工程大学 | External cooling system for pressure vessel of floating nuclear power station |
Also Published As
| Publication number | Publication date |
|---|---|
| DE1137810B (en) | 1962-10-11 |
| LU37544A1 (en) | 1959-10-12 |
| BE581548A (en) | 1959-12-01 |
| FR1211537A (en) | 1960-03-16 |
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