ISO 19017:2015

Overview - What ISO 19017:2015 covers

ISO 19017:2015, "Guidance for gamma spectrometry measurement of radioactive waste", provides international guidance and best practice principles for non-destructive gamma spectrometry assays of packages containing radioactive waste. It addresses a wide range of waste forms (raw/unconditioned, conditioned matrices such as bitumen or cement), activity levels (VLLW, LLW, ILW, HLW) and package geometries (cylinders, cubes, parallelepipeds, transport containers). The standard focuses on implementation, calibration, data evaluation and quality assurance rather than prescribing a single technical solution - recognizing the diversity of measurement systems from research to industrial scale.

Key technical topics and requirements

• Measurement equipment and geometries: Describes open and collimated detector geometries, system components (mechanical handling, radiation detectors, data acquisition, electrical controls and auxiliary equipment).
• Calibration: Guidance on energy and peak-shape calibration, efficiency calibration (including use of physical standards and numerical simulation) and the need for calibration standards that are radiologically and physically representative of waste packages.
• Attenuation correction: Principles and techniques to correct for self-attenuation and matrix/container effects; use of attenuation correction factors to recover un‑attenuated activity.
• Data evaluation: Steps for spectral processing, calculation of net peak count rates, conversion to package radionuclide activity inventory, assessment of measurement uncertainty, and calculation of detection limits.
• Quality assurance and control: Requirements for records of calibration/validation, documented procedures, routine quality control, and demonstrated staff competence.
• Implementation framework: Emphasizes use of a structured requirements-capture process (e.g., Data Quality Objectives (DQO)) and that implementation be performed by suitably qualified personnel.

Practical applications - who uses ISO 19017:2015

• Nuclear facility operators and waste-management organizations performing routine assay of radioactive waste packages.
• Laboratories and service providers offering non-destructive assay (NDA) gamma spectrometry for decommissioning, storage, transport and disposal characterization.
• Regulators and QA auditors assessing measurement programmes and compliance with radiological inventory reporting.
• Designers of gamma spectrometry systems (industrial and research) selecting detectors (including high‑purity germanium and alternative detectors), collimation strategies and calibration approaches.

ISO 19017 supports consistent, defensible gamma assay results used for inventory determination, waste classification, transport compliance and disposal decision making.

Related standards and references

• ISO 19017:2015 supersedes ISO 14850-1:2006.
• The standard references spectrum processing and uncertainty concepts also discussed in documents such as ISO 11929 and recognized nuclear metrology practices.

Keywords: ISO 19017:2015, gamma spectrometry, radioactive waste, non-destructive assay (NDA), efficiency calibration, attenuation correction, measurement uncertainty, detection limit, quality assurance, DQO.