ISO 12807:2018
Safe transport of radioactive materials — Leakage testing on packages
Safe transport of radioactive materials — Leakage testing on packages
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 85
- Дата публикации:
- 26 сентября 2018 г.
- Издание:
- ISO IS 12807 edition 2 version 1
- ICS:
- 13.280
This document specifies gas leakage test criteria and test methods for demonstrating that packages used to transport radioactive materials comply with the package containment requirements defined in the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material for: — design verification; — fabrication verification; — preshipment verification; — periodic verification; — maintenance verification. This document describes a method for relating permissible activity release of the radioactive contents carried within a containment system to equivalent gas leakage rates under specified test conditions. This approach is called gas leakage test methodology. However, in this document it is recognized that other methodologies might be acceptable, provided that they demonstrate that any release of the radioactive contents will not exceed the regulatory requirements, and subject to agreement with the competent authority. This document provides both overall and detailed guidance on the complex relationships between an equivalent gas leakage test and a permissible activity release rate. Whereas the overall guidance is universally agreed upon, the use of the detailed guidance shall be agreed upon with the competent authority during the Type B(U), Type B(M) or Type C packages certification process. It should be noted that, for a given package, demonstration of compliance is not limited to a single methodology. While this document does not require particular gas leakage test procedures, it does present minimum requirements for any test that is to be used. It is the responsibility of the package designer or consignor to estimate or determine the maximum permissible release rate of radioactivity to the environment and to select appropriate leakage test procedures that have adequate sensitivity. This document pertains specifically to Type B(U), Type B(M) or Type C packages for which the regulatory containment requirements are specified explicitly.
Abstract
Overview
ISO 12807:2018 - Safe transport of radioactive materials - Leakage testing on packages provides gas leakage test criteria and methods to demonstrate that transport packages meet the containment requirements of the IAEA Regulations for the Safe Transport of Radioactive Material. The standard defines a gas leakage test methodology that relates permissible radioactive activity release rates to equivalent gas leakage rates under specified test conditions. It applies specifically to Type B(U), Type B(M) and Type C packages and covers verification at multiple stages: design, fabrication, preshipment, periodic and maintenance.
Key topics and technical requirements
- Gas leakage test methodology: Describes how to convert regulatory permissible activity release (activity per unit time) into an equivalent gas leakage rate for testing purposes.
- Permissible activity release rates: Responsibility of the package designer or consignor to estimate the maximum permissible release of radioactivity and select appropriately sensitive tests.
- Minimum test requirements: The document does not mandate specific procedures but specifies minimum requirements for any leakage test intended to demonstrate compliance.
- Verification stages: Procedures and permissible test leakage rates are defined for design verification, fabrication verification, preshipment verification, periodic verification and maintenance verification.
- Selection and performance of tests: Guidance on selecting suitable leak test methods and on test sensitivity, performance, recording of results and quality management systems.
- Calculations & supporting material: Annexes include preferred leakage test methods, methods of calculation, conversion tables, worked examples and rationale to support implementation.
- Competent authority interaction: Detailed guidance may require agreement with the competent authority during certification of Type B/U, B(M) or C packages; alternative methodologies are acceptable if they demonstrate regulatory compliance.
Practical applications and who uses this standard
- Nuclear packaging designers and manufacturers - to verify containment performance during design and fabrication.
- Consignors and shippers of radioactive materials - to perform preshipment and periodic leakage verification and to select test methods with adequate sensitivity.
- Regulatory bodies and competent authorities - to assess conformity of leakage test results with IAEA containment requirements.
- Test laboratories and quality assurance personnel - to apply the standard’s minimum test requirements, calculation methods and reporting formats.
- Maintenance teams - to confirm containment is retained after repairs or over service life.
Related standards and references
- International Atomic Energy Agency (IAEA) - Regulations for the Safe Transport of Radioactive Material (normative reference in ISO 12807:2018).
- ISO/TC 85 (Nuclear energy, nuclear technologies and radiological protection) - technical committee responsible for this standard.
ISO 12807:2018 is essential for organizations that must demonstrate containment of radioactive contents through validated leakage testing aligned to IAEA regulatory limits.
Технические детали
- Технический комитет
- ISO/TC 85/SC 5 - Nuclear installations, processes and technologies
- SKU
- ISO 12807:2018
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