GB984692A - Improvements in nuclear reactor installations - Google Patents

Improvements in nuclear reactor installations

Info

Publication number
GB984692A
GB984692A GB24763/61A GB2476361A GB984692A GB 984692 A GB984692 A GB 984692A GB 24763/61 A GB24763/61 A GB 24763/61A GB 2476361 A GB2476361 A GB 2476361A GB 984692 A GB984692 A GB 984692A
Authority
GB
United Kingdom
Prior art keywords
gas
reactor
fuel
graphite
pressure vessel
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
GB24763/61A
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.)
Babcock International Ltd
Original Assignee
Babcock and Wilcox Ltd
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 Babcock and Wilcox Ltd filed Critical Babcock and Wilcox Ltd
Publication of GB984692A publication Critical patent/GB984692A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/32Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/322Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Abstract

984,692. Reactors. BABCOCK & WILCOX Ltd. July 7, 1961 [July 8, 1960], No. 24763/61. Heading G4G. In a gas cooled nuclear reactor circulation of the gas is effected, without a pump, by thermally induced gas flow through vertical ducting connecting the reactor pressure vessel with a heat exchange chamber above it. As shown, the reactor core 1 is cooled by the vertical flow of gas through channels 101, up duct 7 to pressure vessel 5 containing steam generator 4. The gas when cooled at 5 moves down through the annular space 108 to the lower pressure vessel space 110. The gas may be nitrogen, helium, or carbon dioxide at high pressure, and the reactor core is graphite with graphite-cased uranium oxide or carbide fuel elements. The plant is mounted in the ground within the vertical shaft 3. The heat release rate of the core is adjusted by control of the throttling valve 8 in the gas circuit. An automatic safety device directs the steam generated at 4 to a receiver when radio-active contaminations is detected. The gas in container 5 may be caused to recirculate round or by-pass the generator 4. To assist in the rapid removal of heat from the tube 7 at shut-down, cooling ducts may be arranged concentrically about 7. In an alternative reactor construction, not shown, the fuel is in the form of a mass of graphite spheres encasing fissile and fertile material held in a container of moderating material. As fresh fuel is added the resistance to coolant gas flow increases. This is allowed for by admitting gas to the fuel mass at progressively higher levels.
GB24763/61A 1960-07-08 1961-07-07 Improvements in nuclear reactor installations Expired GB984692A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DED0033741 1960-07-08

Publications (1)

Publication Number Publication Date
GB984692A true GB984692A (en) 1965-03-03

Family

ID=7041868

Family Applications (1)

Application Number Title Priority Date Filing Date
GB24763/61A Expired GB984692A (en) 1960-07-08 1961-07-07 Improvements in nuclear reactor installations

Country Status (1)

Country Link
GB (1) GB984692A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2767981A4 (en) * 2011-10-14 2015-06-17 Mitsubishi Heavy Ind Ltd High-temperature gas reactor steam generator system

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2767981A4 (en) * 2011-10-14 2015-06-17 Mitsubishi Heavy Ind Ltd High-temperature gas reactor steam generator system
US9959945B2 (en) 2011-10-14 2018-05-01 Mitsubishi Heavy Industries, Ltd. High temperature gas cooled reactor steam generation system

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