GB1297951A - - Google Patents

Info

Publication number
GB1297951A
GB1297951A GB1900669A GB1297951DA GB1297951A GB 1297951 A GB1297951 A GB 1297951A GB 1900669 A GB1900669 A GB 1900669A GB 1297951D A GB1297951D A GB 1297951DA GB 1297951 A GB1297951 A GB 1297951A
Authority
GB
United Kingdom
Prior art keywords
reactor
heat exchanger
heated
power plant
heat
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
GB1900669A
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 filed Critical
Publication of GB1297951A publication Critical patent/GB1297951A/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
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • 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
    • 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
    • Y02E30/30Nuclear fission reactors

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

1297951 Nuclear power plant BABCOCK & WILCOX Ltd 14 July 1970 [14 April 1969] 19006/69 Heading G6C In a nuclear power plant, heat exchanger is provided to remove the reactor heat during an emergency shut-down and the decay heat subsequent to shut-down. In an emergency, the heat exchanger 17, having cooling water coils 18, is coupled by valves 11, 15 to the pressurized water or liquid sodium heat exchanger bank part 2, mounted in the cavity 4 in the concrete containment vessel 5 of the reactor 1. During normal operation, the high pressure turbine 9 is supplied with superheated steam by the exchanger bank part 3, heated by the coolant gas of reactor 1. Exhaust steam from 9 is passed to the low pressure stage 13, through the reheat transformer 12, heated from 2.
GB1900669A 1969-04-14 1969-04-14 Expired GB1297951A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB1900669 1969-04-14

Publications (1)

Publication Number Publication Date
GB1297951A true GB1297951A (en) 1972-11-29

Family

ID=10122173

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1900669A Expired GB1297951A (en) 1969-04-14 1969-04-14

Country Status (1)

Country Link
GB (1) GB1297951A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2294517A1 (en) * 1974-12-14 1976-07-09 Bbc Brown Boveri & Cie METHOD AND APPARATUS FOR EVACUATING THE RESIDUAL DISINTEGRATION HEAT OF A PRESSURIZED WATER NUCLEAR REACTOR IN THE EVENT OF A DANGER
FR2390810A1 (en) * 1977-05-13 1978-12-08 Neratoom NUCLEAR REACTOR INSTALLATION
US4587079A (en) * 1981-02-24 1986-05-06 Commissariat A L'energie Atomique System for the emergency cooling of a pressurized water nuclear reactor core
US4761260A (en) * 1986-06-27 1988-08-02 Hochtemperatur-Reaktorbau Gmbh Nuclear power plant with a high temperature reactor located in a cylindrical prestressed concrete pressure vessel
GB2497754A (en) * 2011-12-19 2013-06-26 Charles Donald Ingham A system for pre-heating a suppression material for supply to a fission reaction environment

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2294517A1 (en) * 1974-12-14 1976-07-09 Bbc Brown Boveri & Cie METHOD AND APPARATUS FOR EVACUATING THE RESIDUAL DISINTEGRATION HEAT OF A PRESSURIZED WATER NUCLEAR REACTOR IN THE EVENT OF A DANGER
FR2390810A1 (en) * 1977-05-13 1978-12-08 Neratoom NUCLEAR REACTOR INSTALLATION
US4587079A (en) * 1981-02-24 1986-05-06 Commissariat A L'energie Atomique System for the emergency cooling of a pressurized water nuclear reactor core
US4761260A (en) * 1986-06-27 1988-08-02 Hochtemperatur-Reaktorbau Gmbh Nuclear power plant with a high temperature reactor located in a cylindrical prestressed concrete pressure vessel
GB2497754A (en) * 2011-12-19 2013-06-26 Charles Donald Ingham A system for pre-heating a suppression material for supply to a fission reaction environment

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Legal Events

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