GB1468308A - Nuclear power plant - Google Patents

Nuclear power plant

Info

Publication number
GB1468308A
GB1468308A GB82675A GB82675A GB1468308A GB 1468308 A GB1468308 A GB 1468308A GB 82675 A GB82675 A GB 82675A GB 82675 A GB82675 A GB 82675A GB 1468308 A GB1468308 A GB 1468308A
Authority
GB
United Kingdom
Prior art keywords
reactor
interface
turbine
circuit
section
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
GB82675A
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.)
RINEISKY A
Original Assignee
RINEISKY A
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 RINEISKY A filed Critical RINEISKY A
Priority to GB82675A priority Critical patent/GB1468308A/en
Publication of GB1468308A publication Critical patent/GB1468308A/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
    • G21D5/12Liquid working medium vaporised by reactor coolant
    • G21D5/14Liquid working medium vaporised by reactor coolant and also superheated by reactor coolant
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

1468308 Nuclear power plant V V ORLOV and A A RINEISKY 8 Jan 1975 826/75 Heading G6C Nuclear power plant comprises a reactor 1 arranged to transfer heat by means of a heat transfer medium to a turbine circuit at a first interface formed by a steam generator having an evaporating section 6, a superheating section 5 and an intermediate superheater 8 having, on the reactor side of the first interface, an inlet connected to an outlet of the evaporating section 6 and an outlet connected directly for recirculation of the heat transfer medium to a second, heating interface with the reactor 1, the intermediate superheater 8 being connected, on the turbine side of the first interface, in series with, and between, two stages 9, 10 of the turbine. In one embodiment (Fig. 1) in which the reactor 1 is a sodium-cooled fast reactor, the second interface is constituted by a heat-exchanger 2 at which heat is transferred from the reactor (primary) coolant circuit to a secondary circuit employing sodium; the steam generator also comprises a heating section 7 whose outlet, on the reactor side of the first interface, is connected with the outlet, on that side, of the intermediate superheater for recirulation to the heatexchanger 2. The turbine circuit employs watersteam. The turbine stages are, respectively, a high-pressure stage 9 and a low-pressure stage 10. In another embodiment (Fig. 2) the second interface is constituted by the reactor core, there being only two circuits (the reactorprimary-circuit and the turbine circuit). The turbine circuit includes a steam drum 13 supplying water to the evaporator section 6 and dry saturated steam to the superheating section 5. The reactor may be cooled by sodium, water or gas.
GB82675A 1975-01-08 1975-01-08 Nuclear power plant Expired GB1468308A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB82675A GB1468308A (en) 1975-01-08 1975-01-08 Nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB82675A GB1468308A (en) 1975-01-08 1975-01-08 Nuclear power plant

Publications (1)

Publication Number Publication Date
GB1468308A true GB1468308A (en) 1977-03-23

Family

ID=9711160

Family Applications (1)

Application Number Title Priority Date Filing Date
GB82675A Expired GB1468308A (en) 1975-01-08 1975-01-08 Nuclear power plant

Country Status (1)

Country Link
GB (1) GB1468308A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2225477A (en) * 1988-11-23 1990-05-30 Nnc Ltd Liquid metal cooled nuclear reactors
CN102162397A (en) * 2011-01-13 2011-08-24 绍兴文理学院 Cycling generating system of pressurized water reactor nuclear power gas turbine
RU2449391C2 (en) * 2010-06-16 2012-04-27 Рашид Зарифович Аминов Method to increase capacity of double-circuit nuclear power unit
EP3374719B1 (en) * 2015-11-09 2019-08-14 Framatome GmbH Depressurization and cooling system for a containment of a nuclear power plant
RU2812839C1 (en) * 2023-04-10 2024-02-02 Федеральное государственное бюджетное образовательное учреждение высшего образования "Саратовский государственный технический университет имени Гагарина Ю.А." (СГТУ имени Гагарина Ю.А.) Method for improving efficiency of emergency backup of auxiliary needs of double-circuit npp

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2225477A (en) * 1988-11-23 1990-05-30 Nnc Ltd Liquid metal cooled nuclear reactors
RU2449391C2 (en) * 2010-06-16 2012-04-27 Рашид Зарифович Аминов Method to increase capacity of double-circuit nuclear power unit
CN102162397A (en) * 2011-01-13 2011-08-24 绍兴文理学院 Cycling generating system of pressurized water reactor nuclear power gas turbine
EP3374719B1 (en) * 2015-11-09 2019-08-14 Framatome GmbH Depressurization and cooling system for a containment of a nuclear power plant
RU2812839C1 (en) * 2023-04-10 2024-02-02 Федеральное государственное бюджетное образовательное учреждение высшего образования "Саратовский государственный технический университет имени Гагарина Ю.А." (СГТУ имени Гагарина Ю.А.) Method for improving efficiency of emergency backup of auxiliary needs of double-circuit npp

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee