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GB1077384A - A method of handling and fabricating a neutron responsive fuel - Google Patents

A method of handling and fabricating a neutron responsive fuel

Info

Publication number
GB1077384A
GB1077384A GB27953/65A GB2795365A GB1077384A GB 1077384 A GB1077384 A GB 1077384A GB 27953/65 A GB27953/65 A GB 27953/65A GB 2795365 A GB2795365 A GB 2795365A GB 1077384 A GB1077384 A GB 1077384A
Authority
GB
United Kingdom
Prior art keywords
fuel
reactor
neutron
poison
fabricating
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
GB27953/65A
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 GB1077384A publication Critical patent/GB1077384A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
    • 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
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • 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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • G21C7/04—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1,077,384. Fuel elements. ATOMIC ENERGY OF CANADA. July 1, 1965 [Sept. 9, 1964], No. 27953/65. Heading G6C. The handling of a fissile fuel for a nuclear reactor is facilitated if a material of -high neutron capture cross-section, e.g. gadolinium, camarium or cadmium, is dispersed in the fuel to reduce the neutron responsive reactivity of the fuel, thereafter fabricating the fuel as required for -the nuclear reactor. The fuel fabricated in this manner has very low neutron responsive reactivity until the poison has been destroyed by subjecting the fuel to heavy neutron bombardment, such as by placing it in the operating reactor for a period of a day or more. In some cases it might be practical to make provision for reactivating poisoned fuel on site, and then the denatured fuel could be used as the initial charge of the reactor. Because the criticality hazards are small, the fabricating, shipping and storing of fuel denatured in this manner are considerably simplified. In an example, the fuel forms an annulus between an outer and an inner coolant flow tube, the fuel being sheathed with aluminium and formed of a uranium-aluminium alloy in which the poison has been dispersed by solid solution in the alloy. The quantity of the poison is chosen and distributed in the fuel so that under the netron bombardment the reactivity of the fuel is restored in a period short compared with the life of the fuel in the reactor.
GB27953/65A 1964-09-09 1965-07-01 A method of handling and fabricating a neutron responsive fuel Expired GB1077384A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA911282 1964-09-09

Publications (1)

Publication Number Publication Date
GB1077384A true GB1077384A (en) 1967-07-26

Family

ID=4142078

Family Applications (2)

Application Number Title Priority Date Filing Date
GB51163/66A Expired GB1077385A (en) 1964-09-09 1965-07-01 An improved method of operating a nuclear reactor
GB27953/65A Expired GB1077384A (en) 1964-09-09 1965-07-01 A method of handling and fabricating a neutron responsive fuel

Family Applications Before (1)

Application Number Title Priority Date Filing Date
GB51163/66A Expired GB1077385A (en) 1964-09-09 1965-07-01 An improved method of operating a nuclear reactor

Country Status (1)

Country Link
GB (2) GB1077385A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105895170A (en) * 2014-12-24 2016-08-24 康锋 Uranium 235 fission generating device condition
WO2020022964A1 (en) * 2018-07-24 2020-01-30 West Reality, S.R.O. Addition into the fuel mixture of nuclear fuel for nuclear reactors

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
IL31530A (en) * 1968-02-26 1973-03-30 Gen Electric A fuel core embodying means for reactivity and power distribution control of nuclear reactor
CA932080A (en) * 1968-09-26 1973-08-14 L. Fischer David Reactivity and power distribution control of nuclear reactor
US4626404A (en) * 1983-12-21 1986-12-02 Westinghouse Electric Corp. Annular burnable absorber rod

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105895170A (en) * 2014-12-24 2016-08-24 康锋 Uranium 235 fission generating device condition
WO2020022964A1 (en) * 2018-07-24 2020-01-30 West Reality, S.R.O. Addition into the fuel mixture of nuclear fuel for nuclear reactors
CN112368784A (en) * 2018-07-24 2021-02-12 西部现实有限公司 Additive for fuel mixtures of nuclear fuels of nuclear reactors

Also Published As

Publication number Publication date
GB1077385A (en) 1967-07-26

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