ISO 12807-2018 PDF

Full title and description

ISO 12807:2018 — Safe transport of radioactive materials — Leakage testing on packages. This International Standard specifies principles, test criteria and gas-leakage test methods to demonstrate that transport packages for radioactive material meet containment requirements. It provides a methodology for relating permissible radioactive activity release to equivalent gas leakage rates and gives minimum requirements for leakage tests used for design verification, fabrication verification, preshipment, periodic and maintenance verification of Type B(U), Type B(M) and Type C packages.

Abstract

ISO 12807:2018 establishes a gas-leakage test approach and supporting procedures to assess and verify the containment performance of radioactive material packages. The standard describes how to determine permissible activity release rates, how to convert those activity-release limits into equivalent gas leakage rates under defined test conditions, and the minimum sensitivity, test arrangements and record-keeping needed for valid verification. It recognises alternative acceptable methodologies where agreement with the competent authority exists, but sets out minimum requirements for any leakage-testing procedure intended to demonstrate compliance with transport regulations.

General information

• Status: Published (confirmed current following ISO review in 2023)
• Publication date: September 2018 (2018-09)
• Publisher: International Organization for Standardization (ISO)
• ICS / categories: 13.280; 27.120.30
• Edition / version: Edition 2 (2018)
• Number of pages: 85

Scope

This standard applies to the leakage testing of packages intended for the transport of radioactive material where regulatory containment requirements are specified (notably Type B(U), Type B(M) and Type C packages). It covers the determination of permissible activity release rates for both normal and accident conditions of transport, the selection and performance of appropriate gas-leakage tests, conversion of activity-release limits to equivalent gas-leakage rates, test sensitivity and uncertainty considerations, and the stages at which testing is required (design, fabrication, preshipment, periodic and maintenance verification). The document provides guidance for use during certification and inspection processes and allows for alternative methodologies when accepted by the competent authority.

Key topics and requirements

• Definitions and terminology specific to leakage testing for radioactive transport packages.
• Methodology to relate permissible radioactive activity release to equivalent gas leakage rates.
• Minimum requirements for gas-leakage test methods and apparatus, including sensitivity and detection limits.
• Specified test stages: design verification, fabrication verification, preshipment verification, periodic verification and maintenance verification.
• Guidance on selecting appropriate test methods and on agreement with competent authorities for alternative approaches.
• Procedures for performing tests, recording results and reporting evidence of compliance.
• Consideration of normal and accident transport conditions, and treatment of aerosols, gases and multiphase contents.
• Uncertainty analysis, acceptance criteria and limits for equivalent capillary leak diameters and leakage rates.

Typical use and users

ISO 12807:2018 is used by package designers and manufacturers, certification authorities, test laboratories, consignors and carriers of radioactive materials, and regulatory and compliance specialists. It is applied during design and type testing of transport packages, during manufacturing quality verification, prior to shipment of radioactive consignments, and as part of periodic or maintenance inspections to ensure ongoing containment integrity.

Related standards

This standard is intended to be used in conjunction with the IAEA Regulations for the Safe Transport of Radioactive Material and other international and national transport regulations. It is related to other ISO standards developed by ISO/TC 85 (nuclear energy), and is referenced alongside national leakage-test practices (for example recognized national test methods and industry documents). Specific packaging and transport standards for particular materials (such as packaging for uranium hexafluoride) and complementary test standards or national leakage-test standards may also be relevant when applying ISO 12807.

Keywords

leakage testing; radioactive material; transport packages; containment; gas-leakage test; Type B packages; Type C packages; permissible activity release; test sensitivity; certification; IAEA transport regulations

FAQ

Q: What is this standard?

A: ISO 12807:2018 provides requirements and guidance for leakage testing of radioactive-material transport packages to demonstrate containment performance and compliance with transport regulations.

Q: What does it cover?

A: It covers the methodology to determine permissible activity release rates, conversion to equivalent gas leakage rates, minimum test requirements and procedures, test stages (design, fabrication, preshipment, periodic and maintenance) and considerations for both normal and accident conditions of transport.

Q: Who typically uses it?

A: Package designers and manufacturers, test laboratories, certification bodies, regulatory authorities, consignors and carriers involved in the transport of radioactive material.

Q: Is it current or superseded?

A: The 2018 edition (Edition 2) is published and was reviewed and confirmed in 2023; it is the current edition unless a subsequent revision has been published after that review.

Q: Is it part of a series?

A: ISO 12807 is part of the body of ISO standards and guidance developed by ISO/TC 85 (Nuclear energy) and its subcommittees addressing transportation and packaging of radioactive material; it is commonly used alongside the IAEA Regulations for the Safe Transport of Radioactive Material and other related national and international standards.

Q: What are the key keywords?

A: Leakage testing, containment, transport packages, radioactive material, gas-leakage rate, permissible activity release, Type B, Type C, preshipment test, periodic verification.