State-of-the-Art Report on Molten Corium Concrete Interaction and Ex-Vessel Molten Core Coolability
Nuclear Energy Agency (NEA), 16/10/17, 365 p.

Since 2002, the Nuclear Energy Agency (NEA) has sponsored the Melt Coolability and Concrete Interaction (MCCI) co-operative project in two phases in order to investigate ex-vessel melt coolability and concrete interaction by means of separate-effects tests and large-scale integral tests carried out at the Argonne National Laboratory (ANL).

The second phase of the experimental programme was completed in March 2010. Key elements of this programme included the conduct of experiments involving real reactor material and associated analyses with the objectives of resolving the ex-vessel debris coolability issues and addressing remaining uncertainties related to long-term twodimensional molten core-concrete interactions under both wet and dry cavity conditions. It was expected that the achievement of these two objectives would demonstrate the efficacy of severe accident management guidelines for existing plants and provide the technical basis for better containment designs for the future plants. During both phases of the programme, a total of 13 separate effects tests were conducted to provide data on various core debris cooling mechanisms, including two specific tests to study mechanisms connected to new design features to enhance coolability by bottom water injection. In addition, six large-scale integral tests were conducted to provide data on long-term two-dimensional core-concrete interaction under both wet and dry cavity conditions and one specific one-dimensional large scale test was conducted to investigate the approach for augmenting ex-vessel corium coolability based on an externally-cooled surface concept. These tests provided a broad database to support the development and validation of models and codes with an aim to assess the behaviour of the full size plants under given conditions. The Committee on the Safety of Nuclear Installations (CSNI) held a seminar in November 2010 where the major outcomes of the MCCI Project and other complementary experimental activities were presented and discussed. One of the recommendations of this wrap-up seminar was: “The preparation of a state-of-the-art report on melt coolability and core concrete interactions that captures the last thirty years of international research results”. A consensus was reached to start with the preparation of the recommended report. A proposal was discussed within the framework of the Working Group on Risk Assessment (WGAMA) and endorsed by the CSNI in late 2011. The mandate and the need for a comprehensive state-of-the-art report (SOAR) can be illustrated by the number of questions raised and discussed during MCCI Project and WGAMA meetings. These questions are: What can be learnt from the experimental data base including the last results of the MCCI Project and complementary national or European projects?; What progress has been made and what is the level of remaining uncertainties on the modelling of corium concrete interaction and molten core coolability?; What could be concluded about the capabilities of the codes to predict corium concrete interaction and molten core coolability with respect to containment integrity assessment in plant application?; What are the remaining issues and opportunities to define further experimental or analytical activities?

Extraído de: http://www.oecd-nea.org/tools/publication?query=&div=&lang=&period=6m&sort=title&filter=1#p7392

Sistema de Gestión de Instalaciones Nucleares
Colección de Normas de Seguridad del OIEA, 2017, 176 p.

El objetivo de esta publicación es dar recomendaciones y orientaciones complementarias de las que figuran en la Referencia (International Atomic Energy Agency, Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Installations, Safety Series No 50-C/SG-Q, OIEA (Vienna), 1996.)

para instaurar, aplicar, evaluar y mejorar constantemente un sistema de gestión que integre elementos correspondientes a la seguridad tecnológica, la salud, el medio ambiente, la seguridad física, la calidad y la economía. Todos los temas tratados corresponden a los requisitos establecidos en la Referencia.

Extraído de: http://www-pub.iaea.org/MTCD/Publications/PDF/P1392_S_web.pdf

Extraído de: http://www-pub.iaea.org/books/IAEABooks/10666/The-Management-System-for-Nuclear-Installations

Generic Post-closure Safety Assessment for Disposal of Disused Sealed Radioactive Sources in Narrow Diameter Boreholes
IAEA TECDOC, 2017, 320 p.

The objective of this TECDOC is to document a generic safety assessment (GSA) for this borehole disposal concept, with the purpose of identifying the concept’s key safety features, under varying disposal system conditions,

in order to support the concept design and licensing processes, and facilitate its site specific implementation.

Extraído de: http://www-pub.iaea.org/MTCD/Publications/PDF/TE-1824_web.pdf

Extraído de: http://www-pub.iaea.org/books/IAEABooks/12263/Generic-Post-closure-Safety-Assessment-for-Disposal-of-Disused-Sealed-Radioactive-Sources-in-Narrow-Diameter-Boreholes

Draft Joint Report of ICRU and ICRP for Consultation: Operational Quantities for External Radiation Exposure – Final Draft July 2017
International Commission on Radiation Units and Measurements (ICRU),
International Commission on Radiological Protection (ICRP), July 2017, 202 p.

The Commission defines a set of operational dose quantities for the determination of the exposure of external radiation by measurement or calculation.

These assessments serve as estimates of values of the protection quantities defined by the International Commission on Radiological Protection (ICRP) that are generally not measurable. The set of ICRU operational dose quantities in current use was defined 30 years ago. The rationale for operational quantities has been examined taking into account the recent changes in the definitions of the protection quantities (ICRP, 2010); the changes in the fields of application of the operational quantities and protection quantities in medicine, scientific research, and natural sources of radiation; and the extension of types of particles and range of energies contributing to doses to workers and members of the public. The previous operational quantities were based on the dose equivalent that would be produced at a depth in the hypothetical ICRU 4-element sphere, and on dose equivalent in soft tissue at a point in the body. The investigations which have been carried out that have led to the recommendations given in this Report have included the study the values of weighted absorbed doses at different depths in tissue-equivalent phantoms and the combination of different depths. The operational quantities recommended in this Report are defined in terms of radiometric and dosimetric quantities at a point in space multiplied by values of conversion coefficients to the protection quantities, effective dose, absorbed dose in the lens of the eye, and absorbed dose in local skin, calculated for broad parallel beams incident on the body. The relationship of the recommended operational quantities to the protection quantities has been investigated. The impact of changes on routine measurement practice, including instrument design and calibration has been considered.

Extraído de: http://www.icrp.org/page.asp?id=355

Recommendations and procedures for preparedness and health surveillance of populations affected by a radiation accident
Shamisen Project (European Commission funded), 2017, 54 p.

The EU-OPERRA SHAMISEN project started in December 2015, with the goal of producing a set of recommendations that would contribute to health surveillance and related communication with affected populations after nuclear accidents.

Experience suggested that this was an area that had not been sufficiently addressed in current accident response planning in many European countries. It was also recognised that an update of emergency preparedness in this area was needed for a number of reasons. These include the fact that existing recommendations had a technical focus, with less attention paid to social, ethical, psychological issues and that the information tended to be directed towards the decisions made by experts rather than for support of affected populations. Finally, there have been a number of changes in legal and ethical requirements for health surveillance and epidemiological studies (e.g., related to data protection) that need consideration.

IAEA-RML-2015-01 Proficiency Test for Determination of Radionuclides in Sea Water
IAEA Analytical Quality in Nuclear Applications Series, 2017, 72 p.

The IAEA Environment Laboratories (IAEA-EL) in Monaco and Seibersdorf regularly organize proficiency tests (PT) for radionuclides in environmental samples to support laboratories in IAEA Member States.

The organization and the results of a second PT organized in cooperation with the Nuclear Regulation Authority (NRA) in Japan are described in this publication. Nine laboratorios associated with the IAEA Technical Cooperation project RCA RAS/7/021 entitled ‘Marine Benchmark Study on the Possible Impact of the Fukushima Radioactive Releases in the Asia-Pacific Region’ also took part in the exercise.

Extraído de: http://www-pub.iaea.org/MTCD/Publications/PDF/AQ-51_web.pdf

Evaluación del emplazamiento de instalaciones nucleares
Colección de normas de seguridad del OIEA, 2017, 29 p.

El objetivo de esta publicación es establecer los requisitos de los elementos de la evaluación del emplazamiento de una instalación nuclear, con el fin de caracterizar exhaustivamente las condiciones específicas del emplazamiento que revisten interés para la seguridad de la instalación nuclear.

Se pretende establecer los requisitos para los criterios que deben aplicarse según corresponda al emplazamiento y a sus interacciones con la instalación en los estados operacionales y en condiciones de accidente, incluidas las interacciones que podrían dar lugar a condiciones que requieran medidas de respuesta a emergencias con miras a: a) definir el alcance de la información sobre el emplazamiento propuesto que debe presentar el solicitante; b) evaluar el emplazamiento propuesto para asegurar que se tienen debidamente en cuenta los fenómenos y las características afines al emplazamiento; c) analizar las características de la población de la región y la capacidad para ejecutar planes de emergencia durante la vida útil prevista de la instalación; d) definir los peligros relacionados con el emplazamiento. Esta publicación no aborda de manera concreta las instalaciones subterráneas o frente a la costa.

Extraído de: http://www-pub.iaea.org/books/IAEABooks/11037/Site-Evaluation-for-Nuclear-Installations

Sourcebook of International Activities Related to the Development of Safety Cases for Deep Geological Repositories
Nuclear Energy Agency (NEA), 21/08/17, 64 p.
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All national radioactive waste management authorities recognise today that a robust safety case is essential in developing disposal facilities for radioactive waste.

To improve the robustness of the safety case for the development of a deep geological repository, a wide variety of activities have been carried out by national programmes and international organisations over the past years. The Nuclear Energy Agency, since first introducing the modern concept of the ?safety case?, has continued to monitor major developments in safety case activities at the international level. This Sourcebook summarises the activities being undertaken by the Nuclear Energy Agency, the European Commission and the International Atomic Energy Agency concerning the safety case for the operational and post-closure phases of geological repositories for radioactive waste that ranges from low-level to high-level waste and for spent fuel. In doing so, it highlights important differences in focus among the three organisations.

Extraído de: http://www.oecd-nea.org/tools/publication?query=&div=&lang=&period=6m&sort=title&filter=1#p7341

Research Reactors for the Development of Materials and Fuels for Innovative Nuclear Energy Systems
IAEA Nuclear Energy Series, 2017, 27 p.

This publication presents an overview of research reactor capabilities and capacities in the development of fuels and materials for innovative nuclear reactors, such as GenIV reactors. The compendium provides comprehensive information on the potential for materials and fuel testing research of 30 research reactors, both operational and in development.  

Towards an All-Hazards Approach to Emergency Preparedness and Response Prevention Mitigation Safety Preparedness Guidance Response Emergency Recovery - Lessons Learnt from Non-Nuclear Events
Nuclear Energy Agency (NEA), 2018, 104 p.

Over the years, member countries from the OECD Nuclear Energy Agency (NEA) have developed effective emergency preparedness and response (EPR) arrangements for nuclear facilities and off-site response organisations.

Experience in Modelling Nuclear Energy Systems with MESSAGE: Country Case Studies
IAEA TECDOC, 2018, 280 p.

Member States have recognized the increasing need to model future nuclear power scenarios in order to develop strategies for sustainable nuclear energy systems. The IAEA model for energy supply strategy alternatives and their general environmental impacts (MESSAGE) code is a tool that supports energy analysis and planning in Member States.

Developing a Systematic Education and Training Approach Using Personal Computer Based Simulators for Nuclear Power Programmes - Proceedings of a Technical Meeting Held in Vienna, 15–19 May 2017
IAEA TECDOC, 2018, 164 p.

This publication compiles the output and findings of a technical meeting organized by the IAEA. The use of personal computer (PC) based basic principle simulators in education and training is aimed at enhancing understanding of nuclear technologies through “learning by doing”.