GB796989A - Improvements relating to neutronic reactor fuels - Google Patents

Improvements relating to neutronic reactor fuels

Info

Publication number
GB796989A
GB796989A GB3576/57A GB357657A GB796989A GB 796989 A GB796989 A GB 796989A GB 3576/57 A GB3576/57 A GB 3576/57A GB 357657 A GB357657 A GB 357657A GB 796989 A GB796989 A GB 796989A
Authority
GB
United Kingdom
Prior art keywords
alloy
section
neutron capture
capture cross
improvements relating
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
GB3576/57A
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of GB796989A publication Critical patent/GB796989A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C28/00—Alloys based on a metal not provided for in groups C22C5/00 - C22C27/00
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C43/00—Alloys containing radioactive materials
    • 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
    • G21C3/60—Metallic fuel; Intermetallic dispersions
    • 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

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Metallurgy (AREA)
  • Physics & Mathematics (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Dispersion Chemistry (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)

Abstract

Reactor fuel elements consist of an alloy of U 235 with a metal having a low neutron capture cross section such as Al or Zr, the alloy containing a finely divided uniform dispersion of a material such as B which has a high neutron capture cross section but which transforms, on absorbing neutrons, to a material having a low neutron capture cross section. Preferably the amount of U 235 in the alloy is 15-23 per cent and the alloy contains natural B in the range 0.1-0.5 per cent. Material enriched in B10 may be used in place of natural B in which case the range of proportions for this material may be reduced. The alloy may be made by bubbling BCl3 gas through a bath of molten Al at a temperature of about 800 DEG C. U is then added, and the bath temperature increased to 900-1100 DEG C. to melt the U and incorporate it in the alloy.
GB3576/57A 1956-02-06 1957-02-01 Improvements relating to neutronic reactor fuels Expired GB796989A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US56341856A 1956-02-06 1956-02-06
US65233557A 1957-04-12 1957-04-12

Publications (1)

Publication Number Publication Date
GB796989A true GB796989A (en) 1958-06-25

Family

ID=27073282

Family Applications (2)

Application Number Title Priority Date Filing Date
GB3576/57A Expired GB796989A (en) 1956-02-06 1957-02-01 Improvements relating to neutronic reactor fuels
GB33724/57A Expired GB826529A (en) 1956-02-06 1957-10-29 Improvements relating to neutronic reaction fuels

Family Applications After (1)

Application Number Title Priority Date Filing Date
GB33724/57A Expired GB826529A (en) 1956-02-06 1957-10-29 Improvements relating to neutronic reaction fuels

Country Status (6)

Country Link
BE (2) BE554737A (en)
CH (2) CH373478A (en)
DE (2) DE1027809B (en)
FR (1) FR1168553A (en)
GB (2) GB796989A (en)
NL (2) NL102703C (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2984613A (en) * 1959-04-09 1961-05-16 Charles H Bassett Fuel element for nuclear reactors
DE1176766B (en) * 1958-03-14 1964-08-27 Babcock & Wilcox Co Gas-tight, ceramic fuel element for nuclear reactors with burnable neutron poisons for regulation
US3263004A (en) * 1964-10-08 1966-07-26 Charles H Bean Process of making a sintered, homogeneous dispersion of nuclear fuel and burnable poison
DE1244308B (en) * 1964-06-19 1967-07-13 Atomic Energy Authority Uk Fast nuclear reactor
US4818477A (en) * 1984-07-10 1989-04-04 Westinghouse Electric Corp. PCI resistant fuel and method and apparatus for controlling reactivity in a reactor core

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1176766B (en) * 1958-03-14 1964-08-27 Babcock & Wilcox Co Gas-tight, ceramic fuel element for nuclear reactors with burnable neutron poisons for regulation
US2984613A (en) * 1959-04-09 1961-05-16 Charles H Bassett Fuel element for nuclear reactors
DE1244308B (en) * 1964-06-19 1967-07-13 Atomic Energy Authority Uk Fast nuclear reactor
US3263004A (en) * 1964-10-08 1966-07-26 Charles H Bean Process of making a sintered, homogeneous dispersion of nuclear fuel and burnable poison
US4818477A (en) * 1984-07-10 1989-04-04 Westinghouse Electric Corp. PCI resistant fuel and method and apparatus for controlling reactivity in a reactor core

Also Published As

Publication number Publication date
BE562262A (en) 1957-11-30
NL102703C (en) 1962-05-15
NL110127C (en) 1964-07-15
DE1027809B (en) 1958-04-10
CH373478A (en) 1963-11-30
GB826529A (en) 1960-01-13
DE1043528B (en) 1958-11-13
CH393555A (en) 1965-06-15
FR1168553A (en) 1958-12-10
BE554737A (en) 1957-08-05

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