GB1298600A - Nuclear reactors - Google Patents

Nuclear reactors

Info

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
Application number
GB03023/70A
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.)
Atomic Energy of Canada Ltd AECL
Original Assignee
Atomic Energy of Canada Ltd AECL
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 Atomic Energy of Canada Ltd AECL filed Critical Atomic Energy of Canada Ltd AECL
Publication of GB1298600A publication Critical patent/GB1298600A/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
    • 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)
  • 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.
GB03023/70A 1969-04-21 1970-03-18 Nuclear reactors Expired GB1298600A (en)

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)

Also Published As

Publication number Publication date
DE2019225A1 (en) 1970-10-22
FR2044735A1 (en) 1971-02-26

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PLNP Patent lapsed through nonpayment of renewal fees