ARIS related publications

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	Advances in Small Modular Reactor Technology Developments (2022)
	A supplement to the IAEA Advanced Reactor Information System (ARIS), the biannual booklet presents Member States with a comprehensive yet concise overview of the advances on Small Modular Reactor Technology developments of major lines of technology. There are more than eighty (80) SMR designs under different stages of development and deployment in 18 Member States. The Akademik Lomonosov floating power unit in the Russian Federation with two-module KLT-40S has been in commercial operation since May 2020. The HTR-PM demonstration plant in China was connected to the grid in December 2021. The CAREM25 in Argentina is under construction aiming for grid connection in 2026. The ACP100 in China started construction in July 2021 targeting operation by end of 2026. The NuScale Power Module™ in the United States of America has received Standard Design Approval in September 2020. The 2022 Edition is enriched with annexes that give readers with various technical charts and tables. For the first time that the booklet presents insights on the economic challenges in deployment, enabling design features to facilitate decommissioning and a summary on experimental testing for design verification and validation.
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	Advanced Large Water Cooled Reactors (2020)
	This Booklet offers an overview of the status of advanced, large WCRs with a capacity of 700 MWe or more. It includes descriptions of specific large light and heavy water reactors available for immediate and near-term deployment. Light water reactors are the most prevalent among the operating NPPs throughout the world, both in numbers and in total generated power. Current LWR technologies have proven to be economical, safe and reliable, and they have a mature infrastructure. Heavy water reactors also represent a significant proportion of the world's reactor installations with improved fuel cycle flexibility and can, for example, burn the spent fuel from LWRs with no major reactor design changes. This booklet is intended as a complementary publication to the ARIS database and the IAEA guidance document for evaluating the technology for NPPs, Nuclear Reactor Technology Assessment for Near Term Deployment (IAEA Nuclear Energy Series No. NP-T-1.10).
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	Advances in Small Modular Reactor Technology Developments (2020)
	This booklet reports current advances in the technology development of Small Modular Reactors in the form of brief, yet comprehensive design descriptions contributed by design organizations and reactor vendors in the IAEA Member States. There are seventy-two (72) Small Modular and Micro-Reactor designs described in this booklet representing all the major technology lines. Major milestones have been reached in SMR technology deployment. The Akademik Lomonosov floating power unit with two modules of KLT40S has started commercial operation in May 2020 in the Russian Federation. Two more SMRs are in advanced stage of construction and expected to start operation between 2021 and 2023, in China and Argentina respectively. Dozens of other SMR designs are aiming for construction by 2030 in several Member States including embarking countries. For the first time, the booklet contains dedicated sections on fuel cycle approach, waste management and disposal plans. This booklet is enriched with a set of annexes that provide Member States' readers with various charts and tables to understand the essential technical facts of these designs. This booklet is a supplement to the IAEA Advanced Reactor Information System (ARIS).
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	Advances in Small Modular Reactor Technology Developments (2018)
	This booklet reports current advances in the design and technology development of Small Modular Reactors through the contributions made by design organizations and vendors in the IAEA member states. All the major SMR technology lines are included and the designs are presented in sections that cover land based and marine based water-cooled reactors, high temperature gas cooled reactors, liquid metal, sodium and gas-cooled fast neutron spectrum reactors, molten salt reactors and other designs. This booklet is intended as a supplement to the IAEA Advanced Reactor Information System (ARIS)
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	Advances in Small Modular Reactor Technology Developments (2016)
	This booklet is reporting the advances in design and technology developments of Small Modular Reactors of all the major technology lines within the category of SMRs. It covers land based and marine based water-cooled reactors, high temperature gas cooled reactors, liquid metal, sodium and gas-cooled fast neutron spectrum reactors and molten salt reactors. This booklet is intended as a supplement to the IAEA Advanced Reactor Information System (ARIS)
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	Advanced Large Water Cooled Reactors (2015)
	Member states, both those considering their first nuclear power plant and those with notions to expand their existing programmes, are vitally interested in obtaining current information about designs for reactors that are deployable now or in the near term. The booklet provides an overview of the status of advanced, large (700 MWe or more) water cooled reactors. The objective is to provide Member States with a brief overview of the large nuclear power plants considered currently deployable. It should be regarded as a complementary publication to the ARIS database.
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	Advances in Small Modular Reactor Technology Developments (2014)
	The IAEA has been regularly publishing booklets on the status of SMR technology developments with the objective to provide Member States, including those considering initiating a nuclear power programme and those already having practical experience in nuclear power, a balance and objective overview of the status of SMR designs. This booklet is reporting the advances in global development of small modular reactor designs and technologies. This booklet covers only water-cooled and high temperature gas cooled small modular reactor designs and technologies. This booklet is intended as a supplement to the IAEA Advanced Reactor Information System (ARIS)
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	Nuclear Reactor Technology Assessment for Near Term Deployment (IAEA NE Series NP-T-1.10)
	Several IAEA Member States have embarked on initiatives to establish or reinvigorate nuclear power programmes. In response, the IAEA has developed several guidance and technical publications to identify with Member States the complex tasks associated with such an undertaking and to recommend the processes that can be used in the performance of this work. A major challenge in this undertaking, especially for newcomer Member States, is the process associated with reactor technology assessment (RTA) for near term deployment. Reactor technology assessment permits the evaluation, selection and deployment of the best technology to meet the objectives of the nuclear power programme. Documenting and defending the basis for this RTA decision making requires and deserves technical approaches that are developed on the basis of best practices. This report demonstrates how RTA is performed and how the process and results of this work enable decision making for nuclear power planning and implementation for each of the above tasks. The ARIS database provide detailed information on advanced reactor designs that may be helpful in the RTA process.
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	Status of Innovative Fast Reactor Designs and Concepts (2013)
	The IAEA has been supporting the development of fast reactors and related fuel cycles for almost fifty years. It plays a prominent role, representing for the interested Member States a major international forum for scientific and technical cooperation in this field. Furthermore the IAEA publishes technical reports which provide comprehensive and detailed information on the different aspects of the fast neutron system science and technology. This booklet provides Member States with an overview of the status of innovative fast reactor designs and concepts that are currently under development. The report is intended as a supplementary booklet to the IAEA’s Advanced Reactor Information System (ARIS)
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	Status of Small and Medium Sized Reactor Designs (2012)
	The objective of this booklet is to provide Member States, including those considering initiating a nuclear power programme and those already having practical experience in nuclear power, with a brief introduction to the IAEA Advanced Reactors Information System (ARIS) by presenting a balanced and objective overview of the status of SMR designs. This report is intended as a supplementary booklet to ARIS.
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	Status of Small and Medium Sized Reactor Designs
	A Supplement to the IAEA Advanced Reactors Information System (ARIS)
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	Advances in High Temperature Gas Cooled Reactor Fuel Technology
	This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These com e two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
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	Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to the PBMR-400, PBMM, GT-MHR, HTR-10 and the ASTRA Critical Facility
	This publication presents the findings of an IAEA coordinated research project (CRP) focusing on validation of the safety and operational aspects of high temperature gas cooled reactors (HTGRs) under projected and actual operating conditions. Specifically, it documents the results of a benchmark analysis of the ASTRA critical facility at the Kurchatov Institute in the Russian Federation, with respect to the development of pebble-bed high temperature modular reactor (PBMR-400). It also presents results of benchmark analyses performed for the HTR-10 experimental reactor in China, and the pebble-bed micro model test facility in South Africa.
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	Fast Reactors and Related Fuel Cycles: Challenges and Opportunities (FR09)
	This is the proceedings of an international conference on fast reactors and related fuel cycles convened to exchange experience and innovative ideas in order to achieve progress in this field. Fast reactor programmes are currently on an accelerated growth path in many countries of the world, and the last international fast reactor conference was held almost twenty years ago. The scope of discussion included key scientific and technological areas, such as fuels and materials development, safety, advanced simulation, component and system design, and coolant technology, in which innovation is pursued to ensure that the next generations of fast reactor fuel cycles will achieve their potential. The accompanying CD-ROM contains the contributed papers and posters, summaries of 150 oral presentations and the young generation event.
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	Status of Fast Reactor Research and Technology Development
	Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues discussed are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. The summary includes national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance of fast reactors.
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