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Organization
and Management for Decommissioning of Large Nuclear Facilities
Technical Reports Series No. 399
This report provides information and guidance on the organization
and management of the decommissioning of large nuclear facilities
with an emphasis on organizational aspects. It identifies
the general issues to be addressed and provides an overview
of the organizational activities necessary to manage a decommissioning
project in a safe, timely and cost effective manner. The following
topics are addressed: (i) decommissioning staff, organizational
structures, roles, responsibilities, lines of communication
and reporting, interactions with external stakeholders; (ii)
use of contractors versus in-house work; (iii) quality assurance,
including monitoring activities and record-keeping; (iv) qualifications
and training; (v) work packages; and (vi) management techniques.
(Date 2000, ISBN 92-0-102300-6)
Methods
for the minimisation of Radioactive Waste from Decontamination
and Decommissioning Nuclear Facilities
Technical
Report Series No. 401
This report analyses the principles and factors to be considered
when selecting a waste minimization strategy, such as the
level of development or the availability of technology, national
policies and regulations, technical traditions and economic
considerations. Its primary objective is to identify all important
stages and components in the decision making process which
need to be considered when planning and implementing a waste
minimization programme during decommissioning operations.
(Date 2001, ISBN 92-0-100901-1)
Handling
and Processing of Radioactive Waste from Nuclear Applications
Technical Report Series No. 402
This report provides detailed information on the handling,
processing and storage techniques most widely used and recommended
for waste from non-fuel-cycle activities, i.e. radioactive
waste generated during the application of nuclear techniques
and radioisotopes in industry, medicine, research and education.
The report was designed to meet mainly the needs of developing
countries by focusing on the most simple, affordable and reliable
techniques and discussing their advantages and limitations.
(Date 2001, ISBN 92-0-100801-5)
Legal
and Governmental Infrastructure for Nuclear, Radiation, Radioactive
Waste and Transport Safety: Safety Requirements
Safety Standards Series No. GS-R-1
This Safety Requirements publication establishes the basic
requirements for legal and governmental infrastructures for
nuclear, radiation, radioactive waste and transport safety.
It should be used in conjunction with Safety Series No. 115,
International Basic Safety Standards for Protection against
Ionizing Radiation and for the Safety of Radiation Sources
(1996) and Safety Standards Series No. TS-R-1 (ST-1, Revised),
Regulations for the Safe Transport of Radioactive Material
- 1996 Edition (Revised) (2000). It supersedes both Safety
Series No 50-C-G (Rev. 1), Code on the Safety of Nuclear Power
Plants: Governmental Organization (1988) and Safety Series
No. 111-S-1, Establishing a National System for Radioactive
Waste Management (1995).
(Date 2000, ISBN 92-0-100800-7)
Decommissioning
of Nuclear Fuel Cycle Facilities
Safety Standards Series No. WS-G-2.4
This Safety Guide gives recommendations relating to the
decommissioning of nuclear fuel cycle facilities. The guidance
provided is derived from the basic principles for radioactive
waste management set out in the Safety Requirements publication,
Safety Standards Series No. WS-R-2, Predisposal Management
of Radioactive Waste, Including Decommissioning (2000), and
in Safety Series No. 111-F, The Principles of Radioactive
Waste Management:
A Safety Fundamental (1995).
(Date 2001, ISBN 92-0-101001-X)
Predisposal Management of Radioactive Waste, Including Decommissioning
Safety Standards Series No. WS-R-2
This publication establishes safety requirements relating
to the predisposal of radioactive waste arising from the operation
and decommissioning of nuclear facilities; the application
of radionuclides in industry, medicine and research; the processing
of raw materials containing naturally occurring radionuclides;
and the cleanup of contaminated sites. Safety requirements
for the relevant aspects of decommissioning of nuclear facilities
are established. The book includes provisions required to
bring radioactive waste into a state suitable for storage
or disposal in designated facilities and to ensure the safety
of the facilities. Relevant requirement and associated responsibilities
for the protection of human health and the environment are
included. The safety requirements are established on the basis
of principles set out in the Safety Fundamentals publication;
The Principles of Radioactive Waste Management (1995) (Safety
Series No. 111-F).
(Date 2000, ISBN 92-0-100300-5)
Regulatory
Control of Radioactive Discharges to the Environment Safety
Guide
Safety Standards Series No. WS-G-2.3
This Safety Guide makes recommendations concerning the regulatory
process for controlling the discharge of liquid and gaseous
effluents to the environment from normal controlled operations
of practices in which radioactive material is used. It provides
guidance on how to meet the requirements established in the
Safety Requirements publication, Safety Standards Series No.
WS-R-2, Predisposal Management of Radioactive Waste Including
Decommissioning (2000). It expands on and interprets the principles
stated in the Safety Fundamentals publications Safety Series
No. 111-F, The Principles of Radioactive Waste Management
(1995), and Safety Series No. 120, Radiation protection and
the Safety of Radiation Sources (1996). It also elaborates
on how to fulfil the requirements established in Safety Series
No. 115, International Basic Safety Standards for Protection
against Ionizing Radiation and for the Safety of Radiation
Sources (1996) and Safety Standards No. GS-R-1, Legal and
Governmental Infrastructure for Nuclear, Radiation, Radioactive
Waste and Transport Safety (2000).
(Date 2000,
ISBN 92-0-100100-1)
Safety
of Radioactive Waste Management Proceedings
Proceedings of an international conference organized in co-operation
with the EC, the OECD/NEA and the WHO, and held in Córdoba,
Spain, 13-17 March 2000. The purpose of the conference was
to provide an international forum for senior experts in the
field to discuss safety issues in radioactive waste management,
in order to promote an international consensus and to foster
information exchange on issues related to the international
corpus of safety standards and, particularly, on the implementation
of the State parties' obligations under the Joint Convention
on the Safety of Spent Fuel Management and on the Safety of
Radioactive Waste Management. These proceedings contain all
the presentations and summaries of all discussions, the opening
and closing addresses and the conclusions and recommendations
of the Chairpersons. The contributed papers are provided on
a CD-ROM which accompanies this proceedings
IAEA
Technical Documents(TECDOCS)
http://www.iaea.org/worldatom/Books/TecDoc/
IAEA-TECDOC-1273
Decommissioning Techniques for Research Reactors. M Laraia,
Nuclear Fuel Cycle and Waste Technology / NEFW, February 2002
IAEA-TECDOC 1260 Procedures and Techniques for Closure
of Near Surface Disposal Facilities for Radioactive Waste.
R Dayal, Nuclear Fuel Cycle and Waste Technology / NEFW, November
2001
IAEA-TECDOC 1256 Technical Considerations in the Design
of Near Surface Disposal Facilities for Radioactive Waste.
R Dayal, Nuclear Fuel Cycle and Waste Technology / NEFW, November
2001
IAEA-TECDOC 1255 Performance of Engineered Barrier Materials
in Near Surface Disposal Facilities for Radioactive Waste.
R Dayal, Nuclear Fuel Cycle and Waste Technology / NEFW, November
2001
IAEA-TECDOC-1243
The Use of Scientfic and Technical Results from Underground
Research Laboratory Investigations for the Geological Disposal
of Radioactive Waste. M Raynal, Nuclear Fuel Cycle and
Waste Technology / NEFW, September 2001
IAEA-TECDOC-1222
Waste Inventory Record Keeping Systems (WIRKS) for the Management
and Disposal of Radioactive Waste. G. Csullog, Nuclear
Fuel Cycle and Waste Technology / NEFW, June 2001
IAEA-TECDOC-1208
Monitoring of Geological Repositories for High Level Radioactive
Waste. M. Raynal Nuclear Fuel Cycle and Waste Technology
NEFW, April 2001
IAEA-TECDOC-1199
Characterization of Groundwater Flow for Near Surface Disposal
Facilities. R. Dayal Nuclear Fuel Cycle and Waste Technology
/ NEFW, February 2001
IAEA-TECDOC-1192
Multi-purpose container technologies for spent fuel management.
P. Dyck Nuclear Fuel Cycle and Waste Technology / NEFW, January
2001
IAEA-TECDOC-1187
Retrievability of high level waste and spent nuclear fuel.
E. Warnecke/G. Linsley Radiation and Waste Safety / NSRW,
December 2000.
IAEA-TECDOC-1177
Extrapolation of short term observations to time periods relevant
to the isolation of long lived radioactive waste. M. Raynal
Nuclear Fuel Cycle and Waste Technology / NEFW, October 2000.
IAEA-TECDOC-1183
Management of radioactive waste from the use of radionuclides
in medicine. V. Efremenkov Nuclear Fuel Cycle and Waste
Technology / NEFW, October 2000.
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.
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