GB1414823A - Nuclear power plant - Google Patents
Nuclear power plantInfo
- Publication number
- GB1414823A GB1414823A GB2468273A GB2468273A GB1414823A GB 1414823 A GB1414823 A GB 1414823A GB 2468273 A GB2468273 A GB 2468273A GB 2468273 A GB2468273 A GB 2468273A GB 1414823 A GB1414823 A GB 1414823A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reactor
- heat
- fast
- cooled
- gas
- 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
- 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
-
- 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
-
- 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
Abstract
1414823 Nuclear power plant E I GRISHANIN V G ILJUNIN I A KUZNETSOV V M MUROGOV and A N SHMELEV 23 May 1973 24682/73 Heading G6C In nuclear power plant comprising a steam power generating apparatus and two nuclear reactors the cooling circuits of which are arranged to effect heat transfer to the working medium of a turbine, one of the reactors is a fast fission breeder with a relatively low outlet temperature and the other has a relatively high outlet temperature. In a first embodiment (Fig. 1, not shown) the fast breeder reactor (1) gives up heat in a heatexchanger (3) to the coolant at the inlet side of another reactor (2) in series with the generating plant (6). The fast reactor uses liquid sodium or lithium as coolant and comprises metal fuel. The other reactor (2) may be a fast reactor or a steam-cooled thermal reactor using ceramic fuel. In a second embodiment (Fig. 2, not shown) the heat of the fast reactor (1) is given up in a heatexchanger (3) and the heat of another reactor (2) is given up in a heat-exchanger (7) in series with the first, to heat the working medium of the generating plant (6). The fast reactor (1) is sodium-cooled and the other reactor (2) may be a thermal reactor cooled by gas or steam, or may be a fast reactor cooled by sodium or a gas, e.g. CO 2 or He. If both are fast reactors, the first (1) uses an alloy of uranium and plutonium while the second (2) uses ceramic fuel. The working medium is vapourized in the first heat-exchanger (3) and superheated in the second (7). In a third embodiment (Fig. 3, not shown) the fast reactor (1) is divided into sub-zones (9, 10) with different outlet temperatures, the separate circuits (11, 12) being connected to respective heat-exchangers (13, 14) in series. The lower outlet temperature zone (9) uses metal fuel and the higher (10) uses ceramic fuel. The heatexchangers (13, 14) are in series with a further heat-exchanger (7) in the coolant circuit of the second reactor (2) and provide, respectively, economizer heating, vapourization and superheating of the generating plant working medium. The second reactor (2) may be a gas-graphite reactor and the fast reactor (1) may be gas- or sodium-cooled. The core of the fast reactor (1) may comprise plutonium, or uranium-235 or 233 and thorium, while the thermal reactor (r) may comprise uranium and thorium in a graphite matrix. The coolant in the fast reactor (1) may be helium when that in the thermal reactor (r) is carbon dioxide. In a fourth embodiment (Fig. 4, not shown) both reactors (1, 2) are gas-cooled and connected in a common loop (15) to the heat-exchanger (16) for heating the working medium of the generating plant (6). The fifth embodiment (Fig. 5, not shown) both reactors (1, 2) are gas-cooled and connected in a common cooling loop (15) in series with two heat-exchangers (7, 14) for heating the working medium of the generating plant (6), and the fast reactor (1) also supplies a further heat-exchanger (13) in parallel with the lower temperature heatexchanger (14) of the two others which perform superheating and evaporation/economizer functions, respectively. In another embodiment (Fig. 9, not shown) a gas-cooled fast reactor (1) is disposed inside a cavity (27) in a gas-cooled thermal reactor (2) within a housing (30). If the coolant pressure of the fast reactor (1) is higher than that of the thermal reactor (2), the former is disposed within a high-pressure shell in the housing (30). Coolant from the fast reactor (1) flows to a bottom collection plenum (29) and thence part flows through the thermal reactor (2), a first heat-exchanger (7) and blowers (28) while another part flows directly through a second heat-exchanger (3) and the gas blowers (28) from whence all the coolant is returned to the fast reactor (1). The heat-exchangers (7, 3) respectively perform superheating and evaporator/economizer functioning. In other embodiments (Figs. 6-8, not shown) one or more turbines (18, 26) is included in a closed, direct cycle circuit with the reactors (1,2) in series.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB2468273A GB1414823A (en) | 1973-05-23 | 1973-05-23 | Nuclear power plant |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB2468273A GB1414823A (en) | 1973-05-23 | 1973-05-23 | Nuclear power plant |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1414823A true GB1414823A (en) | 1975-11-19 |
Family
ID=10215620
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2468273A Expired GB1414823A (en) | 1973-05-23 | 1973-05-23 | Nuclear power plant |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1414823A (en) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4836972A (en) * | 1976-12-30 | 1989-06-06 | Fdx Patents Holding Company, N.V. | Controlled thermonuclear fusion device and method |
US4859399A (en) * | 1977-10-13 | 1989-08-22 | Fdx Patents Holding Company, N.V. | Modular fusion power apparatus using disposable core |
US5019321A (en) * | 1977-10-13 | 1991-05-28 | Fdx Patents Holding Company, N.V. | Modular fusion power apparatus using disposable core |
US5049350A (en) * | 1976-12-30 | 1991-09-17 | Fdx Patent Holding Company, N.V. | Controlled thermonuclear fusion power apparatus and method |
CN114876595A (en) * | 2022-06-08 | 2022-08-09 | 西安交通大学 | Thorium-based molten salt reactor supercritical carbon dioxide power generation system and operation method thereof |
-
1973
- 1973-05-23 GB GB2468273A patent/GB1414823A/en not_active Expired
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4836972A (en) * | 1976-12-30 | 1989-06-06 | Fdx Patents Holding Company, N.V. | Controlled thermonuclear fusion device and method |
US5049350A (en) * | 1976-12-30 | 1991-09-17 | Fdx Patent Holding Company, N.V. | Controlled thermonuclear fusion power apparatus and method |
US4859399A (en) * | 1977-10-13 | 1989-08-22 | Fdx Patents Holding Company, N.V. | Modular fusion power apparatus using disposable core |
US5019321A (en) * | 1977-10-13 | 1991-05-28 | Fdx Patents Holding Company, N.V. | Modular fusion power apparatus using disposable core |
CN114876595A (en) * | 2022-06-08 | 2022-08-09 | 西安交通大学 | Thorium-based molten salt reactor supercritical carbon dioxide power generation system and operation method thereof |
CN114876595B (en) * | 2022-06-08 | 2024-02-02 | 西安交通大学 | Thorium-based molten salt reactor supercritical carbon dioxide power generation system and operation method thereof |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed |