Applicability Of Iaea Safety Standards To Non Water Cooled Reactors And Small Modular Reactors
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| Author | : IAEA |
| Publisher | : International Atomic Energy Agency |
| Total Pages | : 293 |
| Release | : 2023-06-12 |
| Genre | : Technology & Engineering |
| ISBN | : 9201275234 |
In response to an increase in global activities related to non-water-cooled reactors and small modular reactors, this new Safety Report documenting areas of novelty of these technologies when compared to the current fleet of reactors has been developed. The impact of these areas of novelty on the applicability and completeness of the IAEA safety standards is assessed in the publication. Gaps and areas for additional consideration are identified. The review undertaken to develop this report encompassed the safety standards related to the lifetime of these reactor technologies. The publication also considers the interface between safety, security, and safeguards in the design of these technologies.
| Author | : International Atomic Energy Agency |
| Publisher | : |
| Total Pages | : 0 |
| Release | : 2024-01-31 |
| Genre | : Technology & Engineering |
| ISBN | : 9789201273239 |
In response to an increase in global activities related to non-water-cooled reactors and small modular reactors, this new Safety Report documents the safety standards related to the lifetime of these reactor technologies. The publication also considers the interface between safety, security, and safeguards in the design of these technologies.
| Author | : International Atomic Energy Agency |
| Publisher | : IAEA Tecdoc Series No. 1785 |
| Total Pages | : 0 |
| Release | : 2016 |
| Genre | : Technology & Engineering |
| ISBN | : 9789201007162 |
This publication presents technology developers and users with common considerations, approaches and measures for enhancing the defence in depth and operability of water cooled small modular reactor (SMR) design concepts to cope with extreme natural hazards. Indicative requirements to prevent an accident such as the Fukushima Daiichi accident from recurring are also provided for States planning to adopt water cooled SMR designs and technologies. This publication was produced within the framework of the IAEA Action Plan on effectively utilizing research and development.
| Author | : |
| Publisher | : |
| Total Pages | : 0 |
| Release | : 2011 |
| Genre | : Nuclear facilities |
| ISBN | : |
"This Safety Guide provides guidance on the establishment of a national nuclear safety infrastructure as a key component of the overall preparations required for emerging nuclear power programmes. It provides recommendations, presented in the form of 200 sequential actions, on meeting the applicable IAEA safety requirements during the first three phases of the development of a nuclear power programme. It is intended for use by persons or organizations participating in the preparation and implementation of a nuclear power programme, including government officials and legislative bodies, regulatory bodies, operating organizations and external support entities."--Provided by publisher.
| Author | : International Atomic Energy Agency |
| Publisher | : |
| Total Pages | : 0 |
| Release | : 2012 |
| Genre | : Technology & Engineering |
| ISBN | : 9789201215109 |
On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.
| Author | : IAEA |
| Publisher | : |
| Total Pages | : 0 |
| Release | : 2021-04-30 |
| Genre | : |
| ISBN | : 9789201308207 |
Focuses on the engineering judgement necessary to apply each of the design requirements in SSR-2/1 (Rev. 1), and also the entire set of requirements, to light water cooled and high temperature gas cooled SMRs.
| Author | : International Atomic Energy Agency |
| Publisher | : |
| Total Pages | : 34 |
| Release | : 2014 |
| Genre | : Reference |
| ISBN | : 9789201154132 |
This Safety Guide provides recommendations and guidance on how to meet the requirements established in Specific Safety Requirements No. SSR-2/1 and in General Safety Requirements No. GSR Part 4 for the identification of structures, systems and components (SSCs) important to safety in nuclear power plants and for their classification on the basis of their function and safety significance. This Safety Guide is intended primarily for use by organizations involved in the design of nuclear power plants, as well as by regulatory bodies and their technical support organizations. The Safety Guide can also be applied to other nuclear installations subject to appropriate adjustments relevant to the specific design of the type of the facility being considered.
| Author | : International Atomic Energy Agency |
| Publisher | : IAEA |
| Total Pages | : 98 |
| Release | : 2004 |
| Genre | : Business & Economics |
| ISBN | : |
This Safety Guide is intended primarily for use with land based stationary thermal nuclear power plants but it may, in parts, have a wider applicability to other nuclear facilities. It provides recommendations and guidance on the possible format and content of a SAR in support of a request to the State regulatory body for authorization to construct and or operate a nuclear power plant. As such, it contains recommendations on meeting the requirements of Safety guide GS-R-1 "Legal and governmental infrastructure for nuclear, radioactive waste and transport safety" (2000, ISBN 9201008007)
| Author | : International Atomic Energy Agency |
| Publisher | : International Atomic Energy Agency |
| Total Pages | : 85 |
| Release | : 2019-09-24 |
| Genre | : Technology & Engineering |
| ISBN | : 9789201021199 |
Deterministic safety analysis is an essential component of safety assessment, particularly for safety demonstration of the design of nuclear power plants (NPPs). The objective of deterministic safety analysis is to confirm that safety functions can be fulfilled and that the necessary structures, systems and components, in combination with operator actions, are effective in keeping the releases of radioactive material from the plant below acceptable limits. Deterministic safety analysis, supplemented by further specific information and analysis, including probabilistic safety analysis, is also intended to demonstrate that the source term and the potential radiological consequences of different plant states are acceptable, and that the possibility of certain conditions arising that could lead to an early or a large radioactive release can be considered as 'practically eliminated'. The publication has been updated to maintain consistency with current IAEA safety requirements and to reflect lessons from the Fukushima Daiichi accident. It takes into account current practices and experience from deterministic safety analyses for NPPs being performed around the world.
| Author | : International Atomic Energy Agency |
| Publisher | : International Atomic Energy Agency |
| Total Pages | : 74 |
| Release | : 2019-05-22 |
| Genre | : Technology & Engineering |
| ISBN | : 9789201019196 |
There is considerable interest in both developing and developed countries in the design of innovative water cooled reactors (WCRs) and, owing to the higher thermal efficiency and significant system simplifications, supercritical water cooled reactors (SWCRs). Compared to conventional WCRs the SCWR concept requires extensive, comprehensive research and development (R&D). Fundamental research in understanding important phenomena has been completed successfully in providing information required for the next step of development. Currently, a few concepts have been assessed as being technical feasible, and several other concepts are under development. These concepts are described in this publication, together with detailed analysis of remaining gaps requiring future R&D.
