GB1414823A - Nuclear power plant - Google Patents

Nuclear power plant

Info

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
Application number
GB2468273A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
OTHERS
Original Assignee
OTHERS
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by OTHERS filed Critical OTHERS
Priority to GB2468273A priority Critical patent/GB1414823A/en
Publication of GB1414823A publication Critical patent/GB1414823A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • G21D5/08Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy 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.
GB2468273A 1973-05-23 1973-05-23 Nuclear power plant Expired GB1414823A (en)

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)

* Cited by examiner, † Cited by third party
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

Cited By (6)

* Cited by examiner, † Cited by third party
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

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