NF ISO 14850-1
Nuclear energy - Waste-packages activity measurement - Part 1 : high-resolution gamma spectrometry in integral mode with open geometry
ISO 14850:2004 describes a procedure for measurements of gamma-emitting radionuclide activity in homogeneous objects such as unconditioned waste (including process waste, dismantling waste, etc.), waste conditioned in various matrices (bitumen, hydraulic binder, thermosetting resins, etc.), notably in the form of 100 L, 200 L, 400 L or 800 L drums, and test specimens or samples, (vitrified waste), and waste packaged in a container, notably technological waste. It also specifies the calibration of the gamma spectrometry chain. The gamma energies used generally range from 0,05 MeV to 3 MeV.
ISO 14850:2004 describes a procedure for measurements of gamma-emitting radionuclide activity in homogeneous objects such as unconditioned waste (including process waste, dismantling waste, etc.), waste conditioned in various matrices (bitumen, hydraulic binder, thermosetting resins, etc.), notably in the form of 100 L, 200 L, 400 L or 800 L drums, and test specimens or samples, (vitrified waste), and waste packaged in a container, notably technological waste. It also specifies the calibration of the gamma spectrometry chain. The gamma energies used generally range from 0,05 MeV to 3 MeV.
Le présent document s'adresse à tous ceux qui sont concernés par la caractérisation de la radioactivité des déchets au moyen d'une mesure par spectrométrie gamma non destructive et édicte des recommandations qui restent parfois générales du fait de la diversité et des situations rencontrées, du matériel pouvant être utilisé.
ISO 19017:2015 is applicable to gamma radiation measurements on radioactive waste. Radioactive waste can be found in different forms and exhibit a wide range of characteristics, including the following: - raw or unconditioned waste, including process waste (filters, resins, control rods, scrap, etc.) and waste from dismantling or decommissioning; - conditioned waste in various forms and matrices (bitumen, cement, hydraulic binder, etc.); - very low level (VLLW), low level (LLW), intermediate level (ILW) and high level radioactive waste (HLW); - different package shapes: cylinders, cubes, parallelepipeds, etc. Guidance is provided in respect of implementation, calibration, and quality control. The diversity of applications and system realizations (ranging from research to industrial systems, from very low level to high level radioactive waste, from small to large volume packages with different shapes, with different performance requirements and allowable measuring time) renders it impossible to provide specific guidance for all instances; the objective of this International Standard is, therefore, to establish a set of guiding principles. Ultimately, implementation is to be performed by suitably qualified and experienced persons and based on a thorough understanding of the influencing factors, contributing variables and performance requirements of the specific measurement application. This International Standard assumes that the need for the provision of such a system will have been adequately considered and that its application and performance requirements will have been adequately defined through the use of a structured requirements capture process, such as data quality objectives (DQO). It is noted that, while outside the scope of this International Standard, many of the principles, measurement methods, and recommended practices discussed here are also equally applicable to gamma measurements of items other than radioactive waste (e.g. bulk food, water, free-standing piles of materials) or to measurements made on radioactive materials contained within non-traditional packages (e.g. in transport containers).
- Avant-proposiv
- Introductionv
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1 Domaine d'application1
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2 Termes, définitions et symboles1
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3 Principe3
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4 Détecteurs et appareillages auxiliaires4
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4.1 Dispositifs mécaniques4
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4.2 Détecteur et préamplificateur4
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4.3 Amplificateur5
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4.4 Convertisseur analogique-numérique5
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4.5 Analyseur multicanal et système de traitement des données5
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4.6 Blindage5
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4.7 Collimateur5
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4.8 Écrans5
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5 Étalonnage5
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5.1 Principe de l'étalonnage6
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5.2 Appareillage spécifique à l'étalonnage7
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5.3 Mesurages à effectuer11
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5.4 Estimation de l'incertitude d'étalonnage12
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6 Mode opératoire13
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7 Interprétation des résultats13
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7.1 Expression de l'activité13
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7.2 Évaluation de l'incertitude14
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7.3 Limite de détection15
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8 Validation des résultats16
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9 Présentation des résultats16
- Annexe A (informative) Transformations des radionucléides - Énergie et intensité des émissions (ICRP, publication 38)18
- Bibliographie20
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