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This document specifies the test devices, test procedures，data analysis, test report，quality control of swelling pressure test for buffer material under coupled thermo-hydro-mechanical conditions for the geological disposal of high-level radioactive waste. This is one of three key tests of buffer material under these conditions. Specifically, the test temperature range of those tests is from room temperature to 90 ℃, because the buffer material will experience such temperature conditions during early disposal process. This document is Part 1 of a three-part series comprising the following: Part 1 – Swelling pressure test Part 2 – Hydraulic conductivity test Part 3 – Triaxial compression strength test The series is applicable to the whole process of testing of buffer material under coupled thermo-hydro-mechanical conditions for geological disposal of high-level radioactive waste. This document is applicable to the swelling pressure test specifically.

The document provides:

— guidelines for determining the thermal effects to consider on fire barriers inside a given room;

— guidelines for determining the global performance of the fire barriers based on standard test characterization;

— guidelines for assessing the need for additional tests to verify the robustness of the solution.

Requirements of applicable standards, numerical tools validation and verification (V&V), and the expected qualification of fire resistance laboratories are detailed.

The limitations of the method's applicability and scope are discussed.

The purpose and justification of this document is to describe a new methodology for the verification of the efficiency of fire barriers, which is initially based on a standardized fire resistance test.

The significance of this work relates to the fact that the present methodology will enhance the level of safety by providing more realism to hazards analysis in combination with standardized test data. It completes the standard ISO-fire rating required for justifying the performance.

The most relevant benefit of this method concerns the determination of the global performance of a barrier in a fire of extended duration compared to the classification given by the ISO-fire rating.

This document specifies a test method for low temperature mechanical properties of electrical insulation materials of superconducting magnets made from cable-in-conduit with stainless steel jacket for application.

The important superconducting magnets mainly include magnetic confinement fusion experimental devices and other magnet confinement fusion devices. The main insulation materials include glass fibres, polyimide films and resin systems. The main mechanical properties include tensile strength, shear strength, compression shear stress, push-out strength and the strength after fatigue.

This document establishes the organizational, design, construction, operational, and quality-assurance requirements applicable to heterogeneous, thermal-spectrum research reactors with power levels up to several tens of megawatts. It defines the minimum expectations for management structure, project governance, safety culture, quality assurance, documentation control, and lifecycle oversight necessary to

ensure safe, compliant, and effective reactor operation.

The document applies to new research reactors and, where practicable, to existing or legacy reactors using a graded approach consistent with IAEA SSR-3[6] a nd I AEA S SG-22.[10] It addresses administrative and operational controls, procurement and inspection processes, training and qualification, radiation protection, and change management throughout the reactor lifecycle, including modifications and decommissioning.

This document does not prescribe detailed technical design specifications; rather, it provides the framework within which such specifications are developed, reviewed, and controlled. Additional guidance may be required for reactors exceeding the stated power range or for specialized reactor types such as fast spectrum systems or facilities incorporating advanced experimental features.

This document specifies the content and structure of specifications for research and test reactors, including sections relevant to radioactive waste management, spent fuel management, and decommissioning considerations for existing and new fission research reactors. It identifies the organizational, technical, and procedural elements that support the pre-decommissioning preparatory phase and associated operational interfaces. The scope includes guidance on defining decommissioning tasks, characterizing waste streams, and establishing administrative and operational arrangements that support safe and effective decommissioning. Considerations related to organizational capacity, turnover of research personnel, and the development of safety and safeguards competencies are addressed where relevant. The document also provides guidance on needs-based waste management pathways applicable to research reactors located on open or publicly accessible campuses or research centres. Safety and protection considerations addressed in this document include administrative and operational controls, as well as waste management and storage arrangements associated with decommissioning activities in areas with varying levels of access control. While many waste-management and decommissioning principles are common across nuclear facilities, this document applies these principles specifically to research and test reactors, reflecting their operational characteristics, scale, and regulatory context.