Bulletin de droit nucléaire n° 103 - Vol. 2019/2
Nuclear Energy Agency - NEA OECD N. 7670 ¦ Date published: 2023

Le Bulletin de droit nucléaire est une publication internationale unique en son genre destinée aux juristes et aux universitaires en droit nucléaire. Ses lecteurs bénéficient d’informations exhaustives qui font autorité sur les développements qui touchent ce droit. Publié gratuitement en ligne deux fois par an, en anglais et en français, il propose des articles thématiques rédigés par des experts juridiques renommés, rend compte du développement des législations à travers le monde et présente la jurisprudence et les accords bilatéraux et multilatéraux pertinents ainsi que les activités réglementaires des organisations internationales.

Ce numéro inclut notamment les articles et les études suivants : « Réflexions juridiques clés pour une réglementation axée sur les résultats » et « Procédure d’autorisation technologiquement neutre des réacteurs avancés : une évaluation du cadre de la NRC hier et aujourd’hui ».

Technical Approaches for the Management of Separated Civilian Plutonium
IAEA Nuclear Energy Series No. NF-T-4.11 ¦ STI/PUB/1935 ¦ 46 pages ¦ 7 figures ¦ Date published: 2023

This publication aims to outline credible technical options for managing separated plutonium. There is no attempt to rank or rate any of the options, instead the intent is to inform the reader of the technical merits of the various options and the state of their development.

It is primarily focused on Member States that have adopted a closed fuel cycle policy but can also be of value to other Member States, specifically their decision makers and other stakeholders involved in potential future nuclear fuel cycles, by informing them on life cycle options and energy policy.

Ageing Management for Nuclear Fuel Cycle Facilities
Safety Reports Series No. 118 ¦ STI/PUB/1994 ¦ 95 pages ¦ 5 figures ¦ Date published: 2023

The ageing of structures, systems and components is one of the major challenges faced by nuclear fuel cycle facilities worldwide. This publication is intended to provide information on methods, approaches, practices and strategies for ageing management of nuclear fuel cycle facilities. It provides practical information on the establishment of effective ageing management programmes for nuclear fuel cycle facilities in the operational stage and on ageing management considerations in different stages in the lifetime of a nuclear fuel cycle facility.

It also addresses the interface of ageing management with other technical areas and programmes, including maintenance, periodic testing and inspection, equipment qualification and configuration management. Best practice examples on how Member States are addressing ageing issues in nuclear fuel cycle facilities are also provided in this publication.

The Operating Organization and the Recruitment, Training and Qualification of Personnel for Research Reactors
IAEA Safety Standards Series No. SSG-84 ¦ Specific Safety Guides STI/PUB/2048 ¦ 89 pages ¦ Date published: 2023

This Safety Guide provides recommendations on the operating organization and on personnel for research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It covers the typical operating organization for research reactor facilities;

the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.5, which it supersedes.

Compliance Assurance for the Safe Transport of Radioactive Material
IAEA Safety Standards Series No. SSG-78 Specific Safety Guides ¦ STI/PUB/2033 ¦ 139 pages ¦ Date published: 2023

The transport of radioactive material is an essential activity worldwide. To ensure the protection and safety of people, property and the environment, appropriate regulations for the safe transport of radioactive material, both at the national level and at the international level, are necessary.

Competent authorities regulate the transport of radioactive material through the application of national regulations, which should be consistent with relevant international regulations. This Safety Guide provides recommendations on actions that competent authorities should take to ensure compliance with the applicable regulations for the safe transport of radioactive material.

Application of Probabilistic Methods for the Safety Assessment and the Reliable Operation of Research Reactors
Safety Reports Series No. 107 ¦ English ¦ STI/PUB/1946 ¦ 97 pages ¦ Date published: 2023

Probabilistic methods are increasingly being used to complement deterministic methods in assessing the safety and ensuring the reliability of research reactors. Addressing features specific to research reactors, this publication suggests a practical approach for the development and implementation of a project using probabilistic methods in terms of objective, scope, data and modelling, as well as the application of results to enhance safety and reliability.

This publication is intended to be used by operating organizations, regulatory bodies and technical support organizations when performing or reviewing research reactor assessments in which probabilistic methods are applied. It will ideally be read in conjunction with relevant IAEA Safety Standards Series publications and technical guidelines for safety analysis, operation and maintenance, and component reliability data for research reactors.

Determination of Environmental Remediation End States
IAEA Nuclear Energy Series No. NW-G-3.2 ¦ English¦ STI/PUB/2053 ¦ 48 pages Date published: 2023

Sites with radioactive contamination may require action to protect people and the environment and to enable transition to a different future use. To support environmental management of these sites, this publication presents a process to determine the “end state” of the site to be remediated or being remediated, and implications for the site future use and necessary controls.

The approach is intended to assist those responsible for a site in making an informed and transparent decision on what is the mutually agreed end state. It provides a common basis for all stakeholders involved in the decision-making process, who are working on achieving consensus, so that the potential for misunderstanding is reduced.

Operational Limits and Conditions and Operating Procedures for Research Reactors
IAEA Safety Standards Series No. SSG-83 Specific Safety Guides ¦ 65 pages ¦ Date published: 2023

This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.4, which it supersedes. The revised version provides specific recommendations on developing, formulating and presenting the operational limits and conditions as well as the operating procedures for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors.

The recommendations in this publication are intended for use by operating organizations of research reactors, regulatory bodies and other relevant organizations involved in a research reactor project.

Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication Facilities
IAEA Safety Standards Series No. SSG-7 (Rev. 1) Specific Safety Guides ¦ English STI/PUB/2040 ¦ 97 pages ¦ Date published: 2023

This Safety Guide provides specific recommendations on the safety of uranium and plutonium mixed oxide (MOX) fuel fabrication facilities. The potential hazards of a MOX fuel fabrication facility are release of actinides, increased radiotoxicity due to trans-uranium actinides, and nuclear criticality.

The toxicity of plutonium is high and therefore it is important that best practices be employed at all stages of the fabrication of MOX fuel, and that plutonium be handled, processed, treated and stored safely. The revised Safety Guide reflects current operational practices at MOX fuel fabrication facilities. The recommendations in this publication are aimed primarily at the operating organizations of fuel fabrication facilities, regulatory bodies and designers.

Core Management and Fuel Handling for Research Reactors
IAEA Safety Standards Series No. SSG-82 ¦ STI/PUB/2045 ¦ 51 pages ¦ Date published: 2023

This Safety Guide provides specific recommendations on core management and fuel handling for research reactors, including handling and storage of fresh fuel, irradiated fuel, core components and neutron sources, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors.

The recommendations in this publication are intended for use by operating organizations of research reactors, regulatory bodies and other relevant organizations involved in a research reactor project. This Safety Guide is a revision of lAEA Safety Standards Series No. NS-G-4.3, which it supersedes.