GB1298600A - Nuclear reactors - Google Patents
Nuclear reactorsInfo
- Publication number
- GB1298600A GB1298600A GB03023/70A GB1302370A GB1298600A GB 1298600 A GB1298600 A GB 1298600A GB 03023/70 A GB03023/70 A GB 03023/70A GB 1302370 A GB1302370 A GB 1302370A GB 1298600 A GB1298600 A GB 1298600A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reactor
- coolant
- preheaters
- heats
- power plant
- 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
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 abstract 4
- 239000002826 coolant Substances 0.000 abstract 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 2
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 abstract 1
- 229910052797 bismuth Inorganic materials 0.000 abstract 1
- 238000009835 boiling Methods 0.000 abstract 1
- 238000001816 cooling Methods 0.000 abstract 1
- 229910052805 deuterium Inorganic materials 0.000 abstract 1
- 239000007788 liquid Substances 0.000 abstract 1
Classifications
-
- 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
- G21D5/04—Reactor and engine not structurally combined
- G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
- G21D5/12—Liquid working medium vaporised by reactor coolant
- G21D5/14—Liquid working medium vaporised by reactor coolant and also superheated by reactor coolant
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
1298600 Nuclear power plant ATOMIC ENERGY OF CANADA Ltd 18 March 1970 [21 April 1969] 13023/70 Heading G6C In a nuclear reactor power plant, superheated steam is generated in heat exchangers heated by the reactor coolant. The reactor core comprises independent coolant flow paths connected separately to the evaporator and superheater exchangers. Heavy water flowing in the tubes 2, 3 of the reactor core 1, heats the preheaters 10, 11 and heavy water flowing in the separate tubes 4, 5, heats the superheaters 12, 13. Superheated steam passes to the turbines 15, 17 and is returned as feed water, by the pump 14 to the preheaters. In a further embodiment, a deuterium moderated reactor has two separate cooling circuits, one using boiling light water and the other employing an organic coolant. Alternatively, liquid lead-bismuth is employed as the core coolant.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US81789369A | 1969-04-21 | 1969-04-21 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1298600A true GB1298600A (en) | 1972-12-06 |
Family
ID=25224121
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB03023/70A Expired GB1298600A (en) | 1969-04-21 | 1970-03-18 | Nuclear reactors |
Country Status (3)
| Country | Link |
|---|---|
| DE (1) | DE2019225A1 (en) |
| FR (1) | FR2044735A1 (en) |
| GB (1) | GB1298600A (en) |
-
1970
- 1970-03-18 GB GB03023/70A patent/GB1298600A/en not_active Expired
- 1970-04-20 FR FR7014298A patent/FR2044735A1/fr not_active Withdrawn
- 1970-04-21 DE DE19702019225 patent/DE2019225A1/en active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| FR2044735A1 (en) | 1971-02-26 |
| DE2019225A1 (en) | 1970-10-22 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US2865827A (en) | Power generation from liquid metal nuclear fuel | |
| CN103928064A (en) | Thermally-operated conversion system | |
| ES350798A1 (en) | Steam cooled nuclear reactor power system | |
| US3085056A (en) | Method and apparatus for generating and superheating steam from nuclear energy | |
| GB886323A (en) | Nuclear reactors | |
| CN203070789U (en) | Thermally-operated conversion system | |
| GB1298600A (en) | Nuclear reactors | |
| US3197380A (en) | Power plant for superheating the steam originating from the steam generator of a nuclear pressurized water reactor | |
| US3228846A (en) | Boiling water nuclear reactor with breeder blanket superheater | |
| US2796396A (en) | Method of intermittently operating a neutronic reactor | |
| GB1153075A (en) | Improvements in Nuclear Reactor Power Plants | |
| GB1389904A (en) | Nuclear power generating systems | |
| ES454363A1 (en) | Auxiliary cooling device for the primary fluid heat exchanger of a nuclear reactor | |
| GB1057996A (en) | Improvements in and relating to nuclear reactors | |
| GB1161654A (en) | Process for Sodium Heated Modules | |
| JPS5231251A (en) | Solar-thermal power generation system | |
| GB785886A (en) | Improvements in or relating to nuclear reactors | |
| GB1297951A (en) | ||
| GB906556A (en) | Means for the generation of superheated steam in nuclear reactors | |
| GB1115354A (en) | Improvements in nuclear reactors | |
| GB1137616A (en) | Coolant salt for a molten salt breeder reactor | |
| Chen et al. | Exergy Analysis for Main Heat Transfer System of CEFR | |
| GB1468308A (en) | Nuclear power plant | |
| Gabaraev et al. | The use of supercritical parameters of a coolant—A promising path to development of nuclear power plant water-cooled reactors in the 21st century | |
| US3715272A (en) | Method of operating a nuclear reactor facility with a steam cooled fast breeder reactor as the heat source |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PLNP | Patent lapsed through nonpayment of renewal fees |