GB972204A - Steam generating nuclear reactors - Google Patents

Steam generating nuclear reactors

Info

Publication number
GB972204A
GB972204A GB9182/63A GB918263A GB972204A GB 972204 A GB972204 A GB 972204A GB 9182/63 A GB9182/63 A GB 9182/63A GB 918263 A GB918263 A GB 918263A GB 972204 A GB972204 A GB 972204A
Authority
GB
United Kingdom
Prior art keywords
fuel
cluster
steam generating
colandria
moderator
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
GB9182/63A
Inventor
Albert Green
Donald Wilfred Lawson
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB9182/63A priority Critical patent/GB972204A/en
Publication of GB972204A publication Critical patent/GB972204A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear 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)

Abstract

972, 204. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Feb. 18, 1964 [March 7, 1963], No. 9182/63. Drawings to Specification. Heading G6C. In a steam generating nuclear reactor, vertical clusters of fuel rods are cooled by a current of light water which a vertical tube within the cluster carries a flow of light water operating as a moderator. The latter is prevented from boiling by a throttle control of its rate of flow. Each fuel cluster is mounted in a pressure tank located in a colandria tube of a tank containing heavy water moderator. The pressure and colandria tubes are separated by a CO 2 atmosphere. The arrangement produces a radiol distribution of thermal neutron flux which is more uniform and of a higher average value than when the vertical tube within the cluster is replaced by fuel. Each fuel rod is formed of UO 2 pellets contained in a zirconium alloy can. Specification 897,232 is referred to.
GB9182/63A 1963-03-07 1963-03-07 Steam generating nuclear reactors Expired GB972204A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB9182/63A GB972204A (en) 1963-03-07 1963-03-07 Steam generating nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB9182/63A GB972204A (en) 1963-03-07 1963-03-07 Steam generating nuclear reactors

Publications (1)

Publication Number Publication Date
GB972204A true GB972204A (en) 1964-10-07

Family

ID=9866984

Family Applications (1)

Application Number Title Priority Date Filing Date
GB9182/63A Expired GB972204A (en) 1963-03-07 1963-03-07 Steam generating nuclear reactors

Country Status (1)

Country Link
GB (1) GB972204A (en)

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