GB1021434A - Continuous neutron flux measurement process and a device for performing the same - Google Patents

Continuous neutron flux measurement process and a device for performing the same

Info

Publication number
GB1021434A
GB1021434A GB8030/64A GB803064A GB1021434A GB 1021434 A GB1021434 A GB 1021434A GB 8030/64 A GB8030/64 A GB 8030/64A GB 803064 A GB803064 A GB 803064A GB 1021434 A GB1021434 A GB 1021434A
Authority
GB
United Kingdom
Prior art keywords
reactor
volume
volumes
neutron flux
measuring
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
GB8030/64A
Inventor
Yves Hubert Henri Wilmart
Jean Laxague
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.)
Groupement Atomique Alsacienne Atlantique SA
Alsacienne Atom
Original Assignee
Groupement Atomique Alsacienne Atlantique SA
Alsacienne Atom
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 Groupement Atomique Alsacienne Atlantique SA, Alsacienne Atom filed Critical Groupement Atomique Alsacienne Atlantique SA
Publication of GB1021434A publication Critical patent/GB1021434A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00Measuring neutron radiation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108Measuring reactor flux
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Molecular Biology (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Measurement Of Radiation (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,021,434. Reactors. GROUPEMENT ATOMIQUE ALSACIENNE ATLANTIQUE. Feb. 26, 1964 [Feb. 26, 1963], No. 8030/64. Heading G6C. The neutron flux in a nuclear reactor is continuously measured by passing one or more series of equal volumes of a neutron-activatable fluid through the reactor, in each series one volume passing freely through the reactor and the other volume or volumes being slowed down for a definite period of time at the point or points of measurement, measuring the activities of the volumes at the outlet of the reactor and, from the differences in activity between the volume which passed directly through the reactor and the other volume or volumes, determining the neutron flux at the point or points of measurement. Argon is suitable as the neutronactivatable fluid, A-40 giving by a n-γ reaction A-41 which decays to K-41 with the emission of #- and #-radiations. Preferably the #-radiation is measured. In one arrangement, a number of measuring channels are distributed throughout a reactor core, each channel consisting of a compensating duct and a measuring duct. The latter includes an activation chamber which comprises a cylinder having a conical entry and exit at the ends and fitted internally with either a number of symmetrically disposed baffles or a helical guiding ramp.
GB8030/64A 1963-02-26 1964-02-26 Continuous neutron flux measurement process and a device for performing the same Expired GB1021434A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR926106A FR1357745A (en) 1963-02-26 1963-02-26 Device for continuous measurement of neutron fluxes

Publications (1)

Publication Number Publication Date
GB1021434A true GB1021434A (en) 1966-03-02

Family

ID=8797949

Family Applications (1)

Application Number Title Priority Date Filing Date
GB8030/64A Expired GB1021434A (en) 1963-02-26 1964-02-26 Continuous neutron flux measurement process and a device for performing the same

Country Status (6)

Country Link
BE (1) BE644372A (en)
DE (1) DE1265882B (en)
FR (1) FR1357745A (en)
GB (1) GB1021434A (en)
LU (1) LU45504A1 (en)
NL (1) NL6401822A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0529496A1 (en) * 1991-08-23 1993-03-03 Westinghouse Electric Corporation Power distribution measuring system employing gamma detectors outside of nuclear reactor vessel

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4990304A (en) * 1989-01-27 1991-02-05 Westinghouse Electric Corp. Instrumentation tube features for reduction of coolant flow-induced vibration of flux thimble tube

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AT220256B (en) * 1959-06-12 1962-03-12 Atomic Energy Authority Uk Method and device for determining the neutron flux distribution in a nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0529496A1 (en) * 1991-08-23 1993-03-03 Westinghouse Electric Corporation Power distribution measuring system employing gamma detectors outside of nuclear reactor vessel

Also Published As

Publication number Publication date
LU45504A1 (en) 1964-04-24
FR1357745A (en) 1964-04-10
NL6401822A (en) 1964-08-27
DE1265882B (en) 1968-04-11
BE644372A (en) 1964-06-15

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