Custodian: Mohamed Al-Mughrabi
The IAEA has developed a comprehensive system of data on sealed radioactive sources (SRS). The system includes data on the actual SRS, the devices housing the sources and details of manufacturers and suppliers worldwide.
The Catalogue is a database containing specific information on industrially manufactured radiation sources and devices, including a visual guide to enable identification of the generic type of product according to its outward appearance (e.g. shape, size, weight). Based on limited information available, the catalogue assists in the characterization of specific models to allow safe handling of these items. The source characterization will include identification of source type, radionuclide, original activity intended use, design details, and manufacturer and supplier data, etc.
The target group to use this catalogue is diverse, and includes regulators, professionals dealing with orphan sources, law enforcement organizations, and waste management companies.
Custodian: John Kinker
NEWMDB contains information on the waste management infrastructure of each Member State; data on storage, processing, and disposal; significant milestones in programme and facility development/life-cycle; yearly information on trends; data on laws, regulations and regulatory authorities; current licensees; facility locations, planned and existing capacities, waste volumes in storage and disposed; and other information relevant to radioactive waste management. Most major and minor nuclear programmes are represented. At present, 66 Member States have nominated Country Coordinators; about 44 Member States regularly contribute data via the online system. The submissions represent approximately 90% of worldwide NPP energy production. The online data submission is permanently open for Member States. Data submissions to NEWMDB are requested and conducted annually. National Contact Persons (Country Coordinators) are officially designated by Member States. The NEWMDB is currently in Version 3, with a substantial upgrade of the Public User Interface.
Custodian: Alper Kahraman
A well established QA/QM system for the management of LLRW primarily considers a systematic registry of information. For a particular radioactive waste material the information sequence begins with the waste characteristics when it is declared as waste; it continues with altered specifications for each applied processing to that waste item. The final component of such an information chain should be either about a conditioned waste package (stored, disposed or transferred to another facility) or its release from regulatory control. The registry system should provide data security, should be capable to filter the required data, and track historical records.
Within these considerations, the IAEA has developed a Working Material - a computerized tool - called Radioactive Waste Management Registry (RWMR). The RWMR introduces many options for recording information on radioactive waste management activities, data processing, and generation of user defined reports. More information about its capabilities as well as its distribution policy can be found at the website of the Waste Technology Section.
Custodian: Sergey Bocharov
The database has been developed to support informational exchange between the countries participating in the IAEA Contact Expert Group for International Radioactive Waste Projects in the Russian Federation (CEG). It contains information on completed and current projects in the area of Nuclear Legacy of the Cold War in the Russian Federation. The database provides information on the scope and status of the projects, results achieved, organisations and experts involved, relevant documents, reports, photos and web-links.
Custodian: Mehmet Ceyhan
The Nuclear Fuel Cycle Information System (NFCIS) is a computerized database designed to provide information on civilian nuclear fuel cycle facilities worldwide. The purpose of NFCIS is to provide Member States and the IAEA with current, consistent, and readily accessible information on existing and planned nuclear fuel cycle facilities throughout the world.
The NFCIS contains information on facilities such as uranium ore processing, recovery of uranium from phosphoric acid, uranium refining, conversion and enrichment, uranium and mixed-oxide (MOX) fuel fabrication, wet and dry away-from-reactor spent fuel storage, reprocessing, heavy water production, production of Zircaloy, and Zircaloy tubing fabrication.
In order to provide comprehensive information on the nuclear fuel cycle industry, non-operational facilities are included in the database in addition to the operational nuclear fuel cycle facilities. The term 'non-operational facilities' refers to facilities under study, under construction, awaiting licensing, planned, standby, closed or decommissioned, cancelled projects, deferred projects and facilities of unknown status. In addition to commercial facilities, information on some laboratory, test scale and pilot plant facilities is also provided to illustrate research and developments in the field. Information in the database was published twice in 1988 and 1996 as print publication.
Custodian: Mehmet Ceyhan
World Distribution of Uranium Deposits (UDEPO) is a database of uranium deposits in the world. The database contains information on the classification, geological characteristics, geographical distribution and technical characteristics of the deposits. It covers all geographical regions of the world. To avoid unnecessary clustering and be more useful for resource assessment, only those deposits with Reasonable Assured Resources of not less than 500 tonnes U and a minimum average grade of 0.03% U are included in the database, with some exceptions.
Two documents have been published by the IAEA that include the data in the database. The first document is a map called "World Distribution of Uranium Deposits" published in 1995. A guidebook to the map contains some description of the deposits; it was published in 1996.
Custodian: Mehmet Ceyhan
The Nuclear Fuel Cycle Simulation System (VISTA) is a scenario-based computer model for the estimation of fuel cycle material, service requirements and actinide arisings.
The model uses simplified approaches to calculate the fuel cycle requirements. These simplified approaches enable the code to estimate the long-term fuel cycle requirements for both open and closed fuel cycle strategies.
The VISTA web site provides a detailed description of the simulation system, an example scenario with results, and a simple calculation tool which can be used to calculate annual material flow in a selected nuclear fuel cycle option.
Custodian: Victor Inozemtsev
The Post Irradiated Examination Facilities Database (PIE) is a technical catalogue on Post Irradiation Examination Facilities worldwide. The PIE database includes of a complete survey of the main characteristics of the hot cells and their PIE capabilities. The database provides IAEA Member States with a useful summary of the PIE facilities which will allow potential users to select the most appropriate laboratories.
The database was first published in 1996 as a working material. The IAEA has converted the catalogue to a computer database and updated it in 2003. The database is now operated in the on-line update mode and is located on the internet at http://www-nfcis.iaea.org with other nuclear fuel cycle related databases.