GB1068080A - Improvements in or relating to nuclear vapour generating plant - Google Patents
Improvements in or relating to nuclear vapour generating plantInfo
- Publication number
- GB1068080A GB1068080A GB46609/64A GB4660964A GB1068080A GB 1068080 A GB1068080 A GB 1068080A GB 46609/64 A GB46609/64 A GB 46609/64A GB 4660964 A GB4660964 A GB 4660964A GB 1068080 A GB1068080 A GB 1068080A
- Authority
- GB
- United Kingdom
- Prior art keywords
- pressure vessel
- coolant
- nov
- core
- flow
- 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
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
- G21C13/087—Metallic vessels
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
Abstract
1,068,080. Reactors. BABCOCK & WILCOX CO. Nov. 16, 1964 [Nov. 15, 1963; Nov. 29, 1963], No. 46609/64. Heading G6C. In a nuclear superheated steam generating plant suitable for marine use, pressurized primary water cools the reactor and produces superheated steam in a once-through flow of secondary coolant water in heat exchangers within the pressure vessel. To accommodate changes of operating conditions the flow of secondary coolant through the exchanger may be controlled. An outer chamber surrounds the pressure vessel and is water filled to serve as a biological shield. The external surface of the pressure vessel is lined with insulating and shielding material. Dissipation of decay heat during shut-down is effected by connecting the heat exchangers to an external water tank. The pressure vessel has a safety valve. Under normal operation the primary coolant is pumped vertically upwards through the core and downwards through the heat exchangers disposed round the core. Gas pressurization of the primary coolant is used. Control rods are adjusted vertically, the flow of coolant past the core is restricted and natural circulation is employed at low loads.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US324087A US3290222A (en) | 1963-11-15 | 1963-11-15 | Compact nuclear steam generator |
US326875A US3245879A (en) | 1963-11-29 | 1963-11-29 | Compact nuclear steam generator |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1068080A true GB1068080A (en) | 1967-05-10 |
Family
ID=26984269
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB46609/64A Expired GB1068080A (en) | 1963-11-15 | 1964-11-16 | Improvements in or relating to nuclear vapour generating plant |
Country Status (5)
Country | Link |
---|---|
BE (1) | BE655829A (en) |
CH (1) | CH418476A (en) |
GB (1) | GB1068080A (en) |
NL (2) | NL6413251A (en) |
NO (1) | NO115539B (en) |
-
0
- NL NL129468D patent/NL129468C/xx active
-
1964
- 1964-11-05 NO NO155439A patent/NO115539B/no unknown
- 1964-11-13 NL NL6413251A patent/NL6413251A/xx unknown
- 1964-11-14 CH CH1478964A patent/CH418476A/en unknown
- 1964-11-16 GB GB46609/64A patent/GB1068080A/en not_active Expired
- 1964-11-16 BE BE655829A patent/BE655829A/xx unknown
Also Published As
Publication number | Publication date |
---|---|
NL6413251A (en) | 1965-05-17 |
CH418476A (en) | 1966-08-15 |
NO115539B (en) | 1968-10-21 |
NL129468C (en) | |
BE655829A (en) | 1965-03-16 |
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