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Coordinación y edición - CNEN/CIN (Brasil) con la colaboración de los países de la RRIAN - Colaborador especial - Máximo Rudelli (Argentina)

Año 3 - Nº 29 - Diciembre 2008
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Moving Forward with Geological Disposal of Radioactive Waste
Nuclear Energy Agency (NEA), 1 September 2008, 24 p.

The NEA Radioactive Waste Management Committee (RWMC) has underscored the environmental and ethical basis for geological disposal as well as its technical feasibility in a number of previous collective statements. In the intervening period there have been advances and evolving views regarding the appropriate methodologies, policies, and decision-making processes. In addition much further practical experience has accumulated regarding the development of geological repositories. The RWMC expresses herewith, in a concise form,

its collective views on why geological disposal remains an appropriate waste management choice for the disposal of the most hazardous and long-lived radioactive wastes, on the current status of geological disposal, on challenges and opportunities for implementation, and expectations for further developments.

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IAEA Safety Glossary: Terminology Used in Nuclear Safety and Radiation ProtectionMultilingual 2007 Edition – Including the IAEA Safety FundamentalsArabic–Chinese–English–French

The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage. It has been in use since April 2000. The IAEA Safety Glossary, 2007 Edition, is a revised and updated version. The primary purpose

of the Safety Glossary is to harmonize terminology and usage in the IAEA Safety Standards. The Safety Glossary is a source of information for users of the IAEA Safety Standards and other safety related IAEA publications. The Safety Glossary also provides guidance primarily for the drafters and reviewers of safety standards and other publications, including IAEA technical officers and consultants, and members of technical committees, advisory groups, working groups and bodies for the endorsement of safety standards.
 STI/PUB/1355, 0 figures; 2008, ISBN 978-92-0-058908-9, Multilingual, CD-ROM. 35.00 Euro. Date of Issue: 18 November 2008.

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Inspección reglamentaria de las instalaciones nucleares y función coercitiva reglamentaria: Guía de seguridad
Colección de normas de seguridad Nº  GS-G-1.3
STI/PUB/1130, 54 pp.; 0 figures; 2008, ISBN 978-92-0-309208-1



Extraído de: http://www-pub.iaea.org/mtcd/publications/PubDetails.asp?pubId=7368

Heavy Component Replacement in Nuclear Power Plants: Experience and Guidelines 
IAEA Nuclear Energy Series, 2008, 97 p.

Component replacement is often the most feasible solution to solve the problems associated with primary water stress corrosion cracking of Alloy 600. Even if mitigation and/or repair were a local solution, replacement offers many advantages when addressing the assortment of potentially susceptible parts contained in a major component. This publication focuses on heavy components replacement considered strategic for nuclear power plant life management but not

included in current maintenance activities carried out by utilities. The major and heavy components to be considered are: steam generators for pressurized water reactors (PWRs) and pressurized heavy water reactors (PHWRs); reactor vessel heads for PWR plants; reactor internal components for boiling water reactor (BWR) plants; reactor vessel internals for PWR plants; pressurizers for PWR plants; reactor coolant piping/recirculation piping for PWR and BWR plants, and fuel channel and feeder pipes in PHWRs.

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Conduct of Operations at Nuclear Power Plants Safety Guide 
IAEA Safety Standards Series, 2008, 55 p.

This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions.

Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

Extraído de:  http://www-pub.iaea.org/MTCD/publications/PubDetails.asp?pubId=7942

Analytical Benchmarks for Nuclear Engineering Applications
Case Studies in Neutron Transport Theory
Nuclear Energy Agency (NEA), 01 Septmebr 2008, 296 p.

Preservation of know-how in the nuclear field is promoted through the activities of the OECD Nuclear Energy Agency Data Bank. One area of importance concerns methods for solving radiation transport problems, especially with regard to neutrons. This handbook (in the form of a case study), prepared by Barry D. Ganapol, is the result of such an initiative. It is a compilation of solutions to the transport equation for which analytical representations can be found. It is designed for educational use

in courses on analytical transport methods and numerical methods with application to reactor physics. In addition, it contains elements for the continuous improvement of transport methods and for computer code verification. The areas of neutron slowing down, thermalization and one-, two- and three-dimensional neutron transport theory are covered. A series of training courses, based on this compilation of solutions has recently begun.

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A Syllabus for the Education and Training of Radiation Oncology Nurses 
Training Course CD Series No.  28

To commemorate its first 50 years, the IAEA has issued a photographic history of the organization and its work. The book addresses the fundamental concepts that underline the work of the IAEA — the natural evolution of security and development as the two aspects of the same ideal: “Atoms for Peace”. The successes and challenges that have shaped the organization

over the past half century are recorded and key events from the IAEA's past and present are detailed. These include President Eisenhower's 'Atoms for Peace' speech, the establishment of safeguards regimes, the international response to the Chernobyl accident and the awarding of the Nobel Peace Prize in 2005, as well as ongoing endeavours in fields ranging from sustainable energy production to human health and agricultural productivity. This publication is an attractive and informative introduction to the work of the IAEA, issued at a time of unprecedented international interest in the safe, secure and peaceful exploitation of nuclear science and technology.
IAEA-TCS-28/CD, 2008, English, CD-ROM

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Diseño de los sistemas de manipulación y almacenamiento del combustible de las centrales nucleares. Guía de seguridad 
 Colección de normas de seguridad Nº  NS-G-1.4

This Safety Guide supersedes Safety Series No. 50-SG-D10 with the same title issued in 1984. The purpose of this Safety Guide is to provide detailed recommendations for the design of fuel handling and storage systems in nuclear power plants. This publication is intended for use by organizations designing, manufacturing, constructing and operating fuel handling and storage facilities in nuclear power plants, as well as by regulatory bodies.

Contents: 1. Introduction; 2. Fuel handling and storage systems and their functions; 3. General design basis 4. Systems for the handling and storage of fresh fuel; 5. Systems for the handling and storage of irradiated fuel and other core components; 6. Handling of fuel casks; 7. Fuel handling at sites with several reactors; 8. Quality assurance and documentation; Annex: flow charts for typical systems for the handling and storage of irradiated fuel.
 STI/PUB/1156, 61 pp.; 4 figures; 2008, ISBN 978-92-0-309108-4, Spanish

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Derivation of the Source Term and Analysis of the Radiological Consequences of Research Reactor Accidents 
IAEA Safety Reports Series, 2008, 178 p.

This report provides a set of suggested methods and practices for determining the source term and analysing the radiological consequences of research reactor accidents. It provides safety analysts, regulators, and reactor facility management and operations staff, with the calculation methods and techniques necessary for deriving the source term. This includes all factors relevant to the formation of radioactive releases, and for estimating on- and off-site radiological consequences. The

specific examples of methods and techniques provided are also intended to meet the requirements and recommendations for performing safety analyses for research reactor facilities, particularly for preparing safety analysis reports.

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