Nuclear and Radiological Safety - Waste Repositories
http://www.iaea.org/worldatom/Books/1999Pubs/nrswr99.shtml

Hydrogeological Investigation of Sites for the Geological Disposal of Radioactive Waste
Technical Reports Series No. 391
This report, which has been prepared as part of the IAEA sub-programme on radioactive waste disposal, discusses the approaches used in the hydrogeological investigation of repository sites. It is based on experience gained in the Member States on those rock types considered as having the potential to host a repository.
(Date 1999, ISBN 92-0-100299-8)

Nuclear and Radiological Safety - Radioactive Waste Management
Safety Standard Series
http://www.iaea.org/worldatom/Books/1999Pubs/nrsrwm99.shtml

Near Surface Disposal of Radioactive Waste: Safety Requirements
Safety Standards Series No. WS-R-1
This Safety Requirements publication sets out the basic safety requirements related to the disposal of radioactive wastes in near surface repositories. As a Safety Requirements publication it is supported by a number of associated Safety Guides which provide guidance on the implementation of the requirements. Its principles are derived from the Safety Fundamentals publication: Safety Series No. 111-F, The Principles of Radioactive Waste Management. It includes requirements for the protection of human health, for the assessment procedures needed to ensure that safety is achieved, and technical requirements for waste acceptance and for siting, design, construction, operation and closure of the repository and the post-closure phase.
(Date 1999, ISBN 92-0-101099-0)

Safety Assessment for Near Surface Disposal of Radioactive Waste: A Safety Guide
Safety Standards Series No. WS-G-1.1
This Safety Guide provides recommendations on how to meet the requirements related to safety assessment in the Safety Requirements publication, Safety Standards Series No. WS-R-1, Near Surface Disposal of Radioactive Waste (1999). It addresses the subject of safety assessment for near surface disposal of radioactive waste and provides guidance on approaches to performing safety assessments in the context of near surface repositories.
(Date 1999, ISBN 92-0-101299-3)

Decommissioning of Nuclear Plants and Research Reactors: Safety Guide
Safety Standards Series No. WS-G-2.1
This Safety Guide addresses the subject of how to meet the requirements for decommissioning of nuclear power plants and research reactors laid down in the Safety Requirements publication, Safety Standards Series No. WS-R-2, Predisposal Management of Radioactive Waste, Including Decommissioning. It provides guidance to national authorities and operating organisations on the planning and safe management of the decommissioning of such installations.
(Date 1999, ISBN 92-0-102599-8)

Decommissioning of Medical, Industrial and Research Facilities: Safety Guide
Safety Standards Series No. WS-G-2.2
This Safety Guide addresses the subject of how to meet the requirements for the decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored, as laid down in the Safety Requirements publication, Safety Standards Series No. WS-R-2, Predisposal Management of Radioactive Waste, Including Decommissioning. It provides guidance to national authorities and operating organisations, particularly to those in developing countries (as such facilities are predominant in these countries) on the planning and safe management of the decommissioning of such facilities.
(Date 1999, ISBN 92-0-102099-6)

Nuclear Fuel Cycle and Waste Management - Waste Management
http://www.iaea.org/worldatom/Books/1999Pubs/nfcwmwm99.shtml

State of the Art Technology for Decontamination and Dismantling of Nuclear Facilities
Technical Reports Series No. 395
This report is a review of the current state of the art of technologies used for the decommissioning of nuclear facilities, including technologies for decontamination and dismantling, waste management and remote systems. It summarises practical experience gained over the last 10 to 15 years in the field of decommissioning
(Date 1999, ISBN 92-0-102499-1)

IAEA Technical Documents (TECDOCs)
http://www.iaea.org/worldatom/Books/TecDoc/

IAEA-TECDOC-1145 Handling, conditioning and storage of spent sealed radioactive sources. M. Al-Mughrabi, Waste Technology/NEFW, June 2000

IAEA-TECDOC-1148 Site characterization techniques used in environmental restoration activities. W.E. Falck, Waste Technology/NEFW, June 2000

IAEA-TECDOC-1131 Restoration of environments affected by residues from radiological accidents: Approaches to decision making. C. Nogueira De Oliveira,
Radiation Safety/NSRW, May 2000

IAEA-TECDOC-1133 The decommissioning of WWER type nuclear power plants. M. Laraia, Nuclear Fuel Cycle and Waste Technology/NEFW, February 2000

IAEA-TECDOC-1129 Inspection and verification of waste packages for near surface disposal. M. Raynal, Waste Technology/NEFW, December 1999

IAEA-TECDOC-1130 Recycle and reuse of materials and components from waste streams of nuclear fuel cycle facilities. V. Efremenkov, Waste Technology/NEFW, December 1999

IAEA-TECDOC-1124 On-site disposal as a decommissioning strategy. M. Laraia, Nuclear Fuel Cycle and Waste Technology/NEFW, November 1999

IAEA-TECDOC-1109 Use of natural analogues to support radionuclide transport models for deep geological repositories for long lived radioactive wastes. M. Raynal, Waste Technology/NEFW, October 1999

IAEA-TECDOC-1115 Minimization of waste from uranium purification, enrichment and fuel fabrication. V. Efremenkov, Waste Technology/NEFW, October 1999

IAEA-TECDOC-1096 Review of the factors affecting the selection and implementation of waste management technologies. V. Friedrich, Nuclear Fuel Cycle and Waste Technology/NEFW August 1999

IAEA-TECDOC-1097 Maintenance of records for radioactive waste disposal. K.W. Han,
Waste Technology/NEFW, August 1999

IAEA-TECDOC-1100 Survey of wet and dry spent fuel storage. P. Dyck, Nuclear Fuel Cycle and Waste Technology/NEFW, August 1999

IAEA-TECDOC-1103 Status and trends in spent fuel reprocessing. P. Dyck / M. Crijns, Nuclear Fuel Cycle and Waste Technology/ NEFW, August 1999

IAEA-TECDOC-1105 Inventory of radioactive waste disposals at sea. R.C. Rastogi, Waste Safety/NSRW, August 1999

IAEA-TECDOC-1111 Report of the international workshop on Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management and Nuclear Fuel Cycle Facilities, (Vienna, 1-2 July 1999), (Supplement to IAEA-TECDOC-1073 and IAEA-TECDOC-1087). E. Warnecke /R. Shani, Nuclear Fuel Cycle and Waste Technology/NSRW, August 1999

IAEA-TECDOC-1089 Storage of spent fuel from power reactors. P. Dyck, Nuclear Fuel Cycle and Waste Technology/NEFW, July 1999

IAEA-TECDOC-1086 Technologies for remediation of radioactively contaminated sites. D. Stritzke, Nuclear Fuel Cycle and Waste Technology/NEFW, June 1999

IAEA-TECDOC-1088 Technical options for the remediation of contaminated groundwater. E. Falck, Waste Technology/NEFW, June 1999

IAEA-TECDOC-1073 Safety measures to address the year 2000 issue at radioactive waste management facilities. E. Warnecke, Waste Safety/NSRW, April 1999

IAEA-TECDOC-1075 Radioactivity in the Arctic Seas. P.P. Povinec, Radiometrics/NAML April 1999

IAEA-TECDOC-1076 Communications on nuclear, radiation, transport and waste safety. P. Wieland, Nuclear Installation Safety/NSNI, April 1999

IAEA-TECDOC-1077 Critical groups and biospheres in the context of radioactive waste disposal. I.F. Vovk, Waste Safety/NSRW, April 1999

IAEA-TECDOC-1081 Spent fuel storage and transport cask decontamination and modification. M.J. Crijns, Nuclear Fuel Cycle and Waste Technology/NEFW, April 1999

IAEA-TECDOC-1068 Application of radiological exclusion and exemption principles to sea disposal. K.-L. Sjoeblom, Waste Safety/NSRW, March 1999

IAEA-TECDOC-1061 Remote technology in spent fuel management. P.H. Dyck, Nuclear Fuel Cycle Material/NEFW, January 1999

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