FR3123128B1 - Method, system and device for determining a quantity of fissile material in a facility - Google Patents

Method, system and device for determining a quantity of fissile material in a facility Download PDF

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Publication number
FR3123128B1
FR3123128B1 FR2105247A FR2105247A FR3123128B1 FR 3123128 B1 FR3123128 B1 FR 3123128B1 FR 2105247 A FR2105247 A FR 2105247A FR 2105247 A FR2105247 A FR 2105247A FR 3123128 B1 FR3123128 B1 FR 3123128B1
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FR
France
Prior art keywords
fissile material
neutron
neutron activation
activity
determining
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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.)
Active
Application number
FR2105247A
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French (fr)
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FR3123128A1 (en
Inventor
Bernard Dumercq
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.)
Orano DS Demantelement et Services SA
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Orano DS Demantelement et Services SA
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Publication date
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Priority to FR2105247A priority Critical patent/FR3123128B1/en
Priority to EP22730962.2A priority patent/EP4341727A1/en
Priority to PCT/FR2022/050947 priority patent/WO2022243638A1/en
Publication of FR3123128A1 publication Critical patent/FR3123128A1/en
Application granted granted Critical
Publication of FR3123128B1 publication Critical patent/FR3123128B1/en
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Anticipated expiration legal-status Critical

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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
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00—Measuring neutron radiation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/003—Nuclear facilities decommissioning arrangements

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  • 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)
  • Analysing Materials By The Use Of Radiation (AREA)

Abstract

La présente invention propose un procédé et un système de détermination d’une quantité de matière fissile présentant de bonnes performances, applicable dans des environnements très irradiants, non destructive, et permettant de disposer les équipements électroniques de mesure en dehors des zones irradiantes. Ce système comporte : - un dispositif d’activation neutronique (3) adapté pour être placé dans une zone à caractériser (31) pendant une durée d’irradiation prédéterminée, le dispositif d’activation neutronique comprenant une matrice (9) en un matériau thermaliseur de neutrons, typiquement en polyéthylène haute densité, intégrant au moins une cible (11) d’activation neutronique, - un dispositif de spectrométrie gamma (5) adapté pour mesurer l’activité de ladite au moins une cible hors de ladite zone à caractériser, et - un dispositif informatique (7) configuré pour calculer un flux neutronique émis par la matière fissile à partir de la mesure de l’activité, et pour déterminer la quantité de matière fissile en fonction dudit flux neutronique en utilisant en outre des données prédéterminées relatives à la composition isotopique de ladite matière fissile. Figure pour l'abrégé : Fig. 1The present invention proposes a method and a system for determining a quantity of fissile material with good performance, applicable in very irradiating environments, non-destructive, and making it possible to place the electronic measurement equipment outside the irradiating zones. This system comprises: - a neutron activation device (3) adapted to be placed in an area to be characterized (31) for a predetermined irradiation time, the neutron activation device comprising a matrix (9) made of a thermalizing material neutrons, typically in high density polyethylene, incorporating at least one neutron activation target (11), - a gamma spectrometry device (5) suitable for measuring the activity of said at least one target outside of said zone to be characterized, and - a computer device (7) configured to calculate a neutron flux emitted by the fissile material from the measurement of the activity, and to determine the quantity of fissile material as a function of said neutron flux by further using relative predetermined data to the isotopic composition of said fissile material. Figure for the abstract: Fig. 1

FR2105247A 2021-05-20 2021-05-20 Method, system and device for determining a quantity of fissile material in a facility Active FR3123128B1 (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
FR2105247A FR3123128B1 (en) 2021-05-20 2021-05-20 Method, system and device for determining a quantity of fissile material in a facility
EP22730962.2A EP4341727A1 (en) 2021-05-20 2022-05-18 Method, system and device for determining an amount of fissile material in a facility
PCT/FR2022/050947 WO2022243638A1 (en) 2021-05-20 2022-05-18 Method, system and device for determining an amount of fissile material in a facility

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR2105247 2021-05-20
FR2105247A FR3123128B1 (en) 2021-05-20 2021-05-20 Method, system and device for determining a quantity of fissile material in a facility

Publications (2)

Publication Number Publication Date
FR3123128A1 FR3123128A1 (en) 2022-11-25
FR3123128B1 true FR3123128B1 (en) 2023-07-21

Family

ID=78212155

Family Applications (1)

Application Number Title Priority Date Filing Date
FR2105247A Active FR3123128B1 (en) 2021-05-20 2021-05-20 Method, system and device for determining a quantity of fissile material in a facility

Country Status (3)

Country Link
EP (1) EP4341727A1 (en)
FR (1) FR3123128B1 (en)
WO (1) WO2022243638A1 (en)

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB841992A (en) * 1955-09-16 1960-07-20 Vickers Electrical Co Ltd Improvements relating to nuclear reactors
DE1809525B2 (en) * 1968-11-18 1976-11-11 Kernforschungsanlage Julien GmbH, 5170 Julien NUCLEAR FUEL ELEMENT SUITABLE FOR NON-DESTRUCTION-FREE BURN DETERMINATION
JPS54159591A (en) * 1978-06-06 1979-12-17 Hitachi Ltd Nuclear fuel rod

Also Published As

Publication number Publication date
FR3123128A1 (en) 2022-11-25
WO2022243638A1 (en) 2022-11-24
EP4341727A1 (en) 2024-03-27

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