GB1091511A - Activity counting device in multichannel arrangement - Google Patents

Activity counting device in multichannel arrangement

Info

Publication number
GB1091511A
GB1091511A GB50057/63A GB5005763A GB1091511A GB 1091511 A GB1091511 A GB 1091511A GB 50057/63 A GB50057/63 A GB 50057/63A GB 5005763 A GB5005763 A GB 5005763A GB 1091511 A GB1091511 A GB 1091511A
Authority
GB
United Kingdom
Prior art keywords
neutron flux
foil
foils
reactor
dec
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
GB50057/63A
Inventor
George Fraysse
Walter Hage German
Israel Pelah
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.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
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 European Atomic Energy Community Euratom filed Critical European Atomic Energy Community Euratom
Priority to GB50057/63A priority Critical patent/GB1091511A/en
Priority to BE655720D priority patent/BE655720A/xx
Priority to FR996050A priority patent/FR1427758A/en
Priority to CH1523664A priority patent/CH440472A/en
Priority to US414249A priority patent/US3423586A/en
Priority to DEP1267A priority patent/DE1267348B/en
Priority to LU47524D priority patent/LU47524A1/xx
Priority to NL6414363A priority patent/NL6414363A/xx
Publication of GB1091511A publication Critical patent/GB1091511A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108—Measuring reactor flux
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T7/00—Details of radiation-measuring instruments
    • G01T7/08—Means for conveying samples received
    • G01T7/10—Means for conveying samples received using turntables
    • 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)
  • High Energy & Nuclear Physics (AREA)
  • Engineering & Computer Science (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • General Physics & Mathematics (AREA)
  • Molecular Biology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Health & Medical Sciences (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Measurement Of Radiation (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,091,511. Measuring neutron flux. EUROPEAN ATOMIC ENERGY COMMUNITY (EURATOM). Dec.17, 1964 [Dec.18, 1963], No.50057/63. Heading G1A. [Also in Division G6] To enable the flux distribution in a nuclear reactor to be investigated samples of metallic foils are distributed throughout the core and are rendered radio-active by the neutron flux. The activated foils are removed from the reactor and the activity is measured to provide a measure of the neutron flux associated with each foil. The device is stated to be suitable for Fourier analyzing the neutron flux distribution. The foils are mounted on a rotating disc and are viewed successively by a photo-multiplier tube. The output of the latter is a measure of the reactivity of the foil and thus also of the neutron flux at the position occupied by the foil in the reactor. As each foil passes the photo-multiplier, a signal is passed to the final indicating device such that the neutron flux measurement is displayed in association with the foil position.
GB50057/63A 1963-12-18 1963-12-18 Activity counting device in multichannel arrangement Expired GB1091511A (en)

Priority Applications (8)

Application Number Priority Date Filing Date Title
GB50057/63A GB1091511A (en) 1963-12-18 1963-12-18 Activity counting device in multichannel arrangement
BE655720D BE655720A (en) 1963-12-18 1964-11-13
FR996050A FR1427758A (en) 1963-12-18 1964-11-24 Multi-channel activity counter device
CH1523664A CH440472A (en) 1963-12-18 1964-11-25 Measuring device for counting radioactive decays of activated samples
US414249A US3423586A (en) 1963-12-18 1964-11-27 Activity counting device in multichannel arrangement
DEP1267A DE1267348B (en) 1963-12-18 1964-12-04 Measuring device for a plurality of activation samples
LU47524D LU47524A1 (en) 1963-12-18 1964-12-05
NL6414363A NL6414363A (en) 1963-12-18 1964-12-10

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB50057/63A GB1091511A (en) 1963-12-18 1963-12-18 Activity counting device in multichannel arrangement

Publications (1)

Publication Number Publication Date
GB1091511A true GB1091511A (en) 1967-11-15

Family

ID=10454481

Family Applications (1)

Application Number Title Priority Date Filing Date
GB50057/63A Expired GB1091511A (en) 1963-12-18 1963-12-18 Activity counting device in multichannel arrangement

Country Status (7)

Country Link
US (1) US3423586A (en)
BE (1) BE655720A (en)
CH (1) CH440472A (en)
DE (1) DE1267348B (en)
GB (1) GB1091511A (en)
LU (1) LU47524A1 (en)
NL (1) NL6414363A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2184533B1 (en) * 1972-05-19 1974-12-27 Commissariat Energie Atomique
CN114035222B (en) * 2021-10-28 2023-07-21 中国船舶重工集团公司第七一九研究所 Online neutron spectrum measuring device

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2490298A (en) * 1949-05-13 1949-12-06 Ghiorso Albert Radiation detecting apparatus
US3087063A (en) * 1959-07-28 1963-04-23 Gen Dynamics Corp System for automatically inspecting a batch of samples
US3141977A (en) * 1959-07-29 1964-07-21 Lab For Electronics Inc Apparatus for measuring the radioactivity of liquid samples

Also Published As

Publication number Publication date
NL6414363A (en) 1965-06-21
LU47524A1 (en) 1965-03-29
DE1267348B (en) 1968-05-02
US3423586A (en) 1969-01-21
CH440472A (en) 1967-07-31
BE655720A (en) 1965-05-13

Similar Documents

Publication Publication Date Title
GB1168198A (en) Detection, Identification and Analysis of Fissionable Isotopes
GB1285688A (en) Devices for use in determining distribution of neutron flux
GB1431445A (en) Automated multiple sample processing for well type radioactivity counters
GB1091511A (en) Activity counting device in multichannel arrangement
GB780219A (en) Improvements in nuclear reactors provided with a neutron flux measurement device
GB1252230A (en)
JPS5338895A (en) Device for measuring neutron bundle of reactor
JPS5267686A (en) Device for measuring spacial distribution of neutrons
GB1248030A (en) Apparatus for measuring the content of fissile substance of fuel elements or the burn-up of fuel elements, of a nuclear reactor
GB1235324A (en) A method of and apparatus for determining the content of fissile material in fuel samples or fuel elements of nuclear reactors
Brunson et al. Delayed Neutron Yields in Pu, U-233, U-238, and Th Relative to Yield in U-235
Upson An Automatic Gamma Sample Changer
Bluhm et al. CABRI hodoscope
SU667924A1 (en) Method of measuring heat power of nuclear reactor
Zaghloul et al. Neutron activation analysis without multielement standards
GB917776A (en) 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
Harris et al. Measurement of uranium and plutonium content in a fuel assembly using the RPI spent fuel assay device
DEBRUIN et al. A computer oriented system for nondestructive neutron activation analysis(Nondestructive neutron activation and spectrum analysis using gamma ray spectrometer coupled to PDP 9 computer)
Kaufmann et al. Fission and Activation Ratios in the EBR
Makarov Technique for neutron energy determination
JPS5450790A (en) Neutron flux distribution of axial derection in reactor measuring device
GB1414534A (en) Testing the functioning of a neutron detector
Beller CONTROL UNIT FOR AUTOMATIC NORMALIZATION OF FOIL COUNTING
GB1037148A (en) Device for measuring the concentration of fission products in suspension in a fluid
FR73582E (en) Improvements to nuclear reactors comprising a device for measuring neutron power