GB870891A - Improvements in or relating to nuclear reactors - Google Patents

Improvements in or relating to nuclear reactors

Info

Publication number
GB870891A
GB870891A GB12955/59A GB1295559A GB870891A GB 870891 A GB870891 A GB 870891A GB 12955/59 A GB12955/59 A GB 12955/59A GB 1295559 A GB1295559 A GB 1295559A GB 870891 A GB870891 A GB 870891A
Authority
GB
United Kingdom
Prior art keywords
moderator
fuel
flow
coolant flow
core
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
GB12955/59A
Inventor
Ian Douglas Neilson
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.)
HAWKER SIDDELEY NUCLEAR POWER
Original Assignee
HAWKER SIDDELEY NUCLEAR POWER
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 HAWKER SIDDELEY NUCLEAR POWER filed Critical HAWKER SIDDELEY NUCLEAR POWER
Priority to GB12955/59A priority Critical patent/GB870891A/en
Priority to FR824455A priority patent/FR1255200A/en
Publication of GB870891A publication Critical patent/GB870891A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • 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)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

870,891. Nuclear reactors. HAWKER SIDDELEY NUCLEAR POWER CO. Ltd. April 11, 1960 [April 16, 1959], No. 12955/59. Class 39(4). In a heterogeneous reactor using uranium fuel enriched with up to 1% Pu by weight and having one organic liquid as coolant and moderator in an under-moderated lattice, the organic liquid is divided into two flows in the core: a fast-moving coolant flow adjacent to the fuel, and a slower moderator flow separated from the fuel by and occupying twice as much core volume as the coolant flow. The moderator flow is adjusted to produce littlerise in moderator temperature in the core so that the response of the reactor depends on the negative temperature coefficient of reactivity of the fuel. The Figure shows stainless steelclad fuel rods F enclosed by tubes T inside which is the coolant flow and between which is the moderator flow, at M. The two flows pass through separate heat exchangers; the coolant flow can be switched to the moderator heat exchanger for emergency cooling, this exchanger being smaller and more easily shielded. The moderator can be drained off in an emergency.
GB12955/59A 1959-04-16 1959-04-16 Improvements in or relating to nuclear reactors Expired GB870891A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB12955/59A GB870891A (en) 1959-04-16 1959-04-16 Improvements in or relating to nuclear reactors
FR824455A FR1255200A (en) 1959-04-16 1960-04-15 Improvements to nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB12955/59A GB870891A (en) 1959-04-16 1959-04-16 Improvements in or relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB870891A true GB870891A (en) 1961-06-21

Family

ID=10014180

Family Applications (1)

Application Number Title Priority Date Filing Date
GB12955/59A Expired GB870891A (en) 1959-04-16 1959-04-16 Improvements in or relating to nuclear reactors

Country Status (1)

Country Link
GB (1) GB870891A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103117098A (en) * 2013-02-04 2013-05-22 中国核动力研究设计院 Square fuel assembly structure suitable for supercritical water-cooled reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103117098A (en) * 2013-02-04 2013-05-22 中国核动力研究设计院 Square fuel assembly structure suitable for supercritical water-cooled reactor

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