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GB917776A - Method of measuring the amount of material fissile by thermal neutrons and present in any arbitrary substance, particularly for controlling the state of exhaustion of fuel elements in nuclear reactors - Google Patents

Method of measuring the amount of material fissile by thermal neutrons and present in any arbitrary substance, particularly for controlling the state of exhaustion of fuel elements in nuclear reactors

Info

Publication number
GB917776A
GB917776A GB29166/61A GB2916661A GB917776A GB 917776 A GB917776 A GB 917776A GB 29166/61 A GB29166/61 A GB 29166/61A GB 2916661 A GB2916661 A GB 2916661A GB 917776 A GB917776 A GB 917776A
Authority
GB
United Kingdom
Prior art keywords
fuel elements
gamma rays
amount
antimony
exhaustion
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
GB29166/61A
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.)
BBC BROWN BOVERI and CIE
BBC Brown Boveri AG Germany
Original Assignee
BBC BROWN BOVERI and CIE
Brown Boveri und Cie AG Germany
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 BBC BROWN BOVERI and CIE, Brown Boveri und Cie AG Germany filed Critical BBC BROWN BOVERI and CIE
Publication of GB917776A publication Critical patent/GB917776A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/063—Burn-up control
    • 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)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

917,776. Fuel elements. BROWN BOVERI & CIE. A.G. Aug. 11, 1961 [Sept. 2, 1960], No. 29166/61. Class 39 (4). A method of testing a fuel element or other material to determine the amount of fissile material it contains, comprises exposing the element or material to a thermal neutron flux and counting the fast neutrons produced. In the apparatus shown radioactive antimony 1 is arranged in one side of a beryllium block 3, the beryllium serving to convert gamma rays from the antimony into neutrons and also serving as a moderator. Fuel elements, which may be spherical, are introduced into a guide tube 4 and fast neutrons produced in them are detected by thorium 232 fission chambers 8-11 which have a good discrimination against gamma rays and slow neutrons. A lead shield 5 shields the counters from gamma rays from the antimony 1 and shields the beryllium block 3 from gamma rays from the fuel elements. The apparatus is surrounded by a shield 2 and may be calibrated by testing fuel elements of known fissile content; it may be applied to testing fuel elements which have been removed from a nuclear reactor.
GB29166/61A 1960-09-02 1961-08-11 Method of measuring the amount of material fissile by thermal neutrons and present in any arbitrary substance, particularly for controlling the state of exhaustion of fuel elements in nuclear reactors Expired GB917776A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEB0059202 1960-09-02

Publications (1)

Publication Number Publication Date
GB917776A true GB917776A (en) 1963-02-06

Family

ID=6972366

Family Applications (1)

Application Number Title Priority Date Filing Date
GB29166/61A Expired GB917776A (en) 1960-09-02 1961-08-11 Method of measuring the amount of material fissile by thermal neutrons and present in any arbitrary substance, particularly for controlling the state of exhaustion of fuel elements in nuclear reactors

Country Status (2)

Country Link
GB (1) GB917776A (en)
NL (1) NL268298A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1261607B (en) * 1966-03-01 1968-02-22 Brown Boveri Krupp Reaktor Method for differentiating between identical operating elements of a nuclear reactor, the reactor core of which is a stack of these operating elements
US6035010A (en) * 1996-10-15 2000-03-07 European Atomic Energy Community (Euratom) Monitor for measuring both the gamma spectrum and neutrons emitted by an object, such as spent nuclear fuel
CN111968768A (en) * 2020-08-14 2020-11-20 兰州大学 Nuclear fuel burnup depth measuring device and method based on active neutron space intensity distribution

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1261607B (en) * 1966-03-01 1968-02-22 Brown Boveri Krupp Reaktor Method for differentiating between identical operating elements of a nuclear reactor, the reactor core of which is a stack of these operating elements
US6035010A (en) * 1996-10-15 2000-03-07 European Atomic Energy Community (Euratom) Monitor for measuring both the gamma spectrum and neutrons emitted by an object, such as spent nuclear fuel
CN111968768A (en) * 2020-08-14 2020-11-20 兰州大学 Nuclear fuel burnup depth measuring device and method based on active neutron space intensity distribution

Also Published As

Publication number Publication date
NL268298A (en)

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