ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events

Session 20 Abstracts
12) A COMPREHENSIVE INFORMATION MANAGEMENT SYSTEM FOR EUROPEAN DISPOSAL R&D
(INMAN): A PROPOSAL FOR THE NEXT EUROPEAN FRAMEWORK PROGRAM (w/oP-59397)
Gunnar Buckau, Institute for Transuranium Elements, Joint Research Center, European Union;
Anne Delos, Vanessa Montoya, Amphos 21 (Germany/France/Spain)
ABSTRACT NOT AVAILABLE
13) DEVELOPMENT OF COMPREHENSIVE TECHNIQUES FOR COASTAL SITE
CHARACTERIZATION: INTEGRATED PALAEOHYDROGEOLOGICAL APPROACH
FOR DEVELOPMENT OF SITE EVOLUTION MODELS (wP-59259)
Kenji Amano, Tadafumi Niizato, Kunio Ota, Japan Atomic Energy Agency; Bill Lanyon, Nagra;
W Russell Alexander, Bedrock Geosciences (Japan/Switzerland)
Radioactive waste repository designs consist of multiple safety barriers which include the waste form, the canister, the engineered
barriers and the geosphere. In many waste programmes, it is considered that the three most important safety features provided
by the geosphere are mechanical stability, favourable geochemical conditions and low groundwater flux. To guarantee that a
repository site will provide such conditions for timescales of relevance to the safety assessment, any repository site characterisation
has to not only define whether these features will function appropriately today, but also to assess if they will remain adequate
up to several thousand to hundreds of thousand years into the future, depending on the repository type.
In general, this is done by studying the palaeohydrogeological evolution of a site, defining the temporal and spatial changes of
various properties and processes. These may include geology, hydrogeology, hydrochemistry and site tectonics, including uplift and
erosion processes. These key aspects are studied to build up a conceptual model for the overall site evolution over geological time,
up to the present and this is used to define the likely future evolution of the site and to assess if the main safety features will continue
to function adequately.
The collaborative programme…
SESSION 20 — PANEL: CHALLENGES WHEN SELECTING DISPOSAL OPTIONS IN THE LIGHT
OF THE NEW IAEA CLASSIFICATION SCHEME (1.17)
ABSTRACTS NOT REQUIRED
SESSION 21 — PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF INTERIM STORAGE,
GEOLOGICAL DISPOSAL, PARTITIONING & TRANSMUTATION REVERSIBILITY REGARDING
GLOBAL OPTIMIZATION OF RADWASTE MANAGEMENT (2.15)
NEW NUCLEAR PROGRAMMES MUST NOT NEGLECT WASTE MANAGEMENT (wP-59077)
Charles McCombie, Arius Association (Switzerland)
Many established nuclear power programmes have learned to their dismay that waste management and disposal are not tasks
that can be postponed at will if public and political acceptance is a prerequisite for progress. In fact, some programmes that recognised
this back in the 1970s and 1980s moved into leading positions in repository development. This happened, for example, in
Sweden and Switzerland where already in the 1970s Laws were passed specifying that safe disposal must be demonstarted before
new nuclear plants could opersate. In recent years, it has become recognised that, in order to ensure that the radioactive wastes in
any country are managed safely, it is necessary to have an established legislative and regulatory framework and also to create the
necessary organizations for implementation and for oversight of waste management operations and facility development. Guidance
on these issues is given in the Joint Convention and a number of other IAEA documents. The IAEA, and also the EC, have in addition
published key overarching advisory documents for new nuclear programmes. These are useful for strategic planning but, when
it comes to actual implementation projects, the advice tends to imply that all nuclear programmes, however large or small, should
be pressing…
SESSION 22 — PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF INTERIM STORAGE,
GEOLOGICAL DISPOSAL, PARTITIONING & TRANSMUTATION REVERSIBILITY REGARDING
GLOBAL OPTIMIZATION OF RADWASTE MANAGEMENT (2.15)
ABSTRACTS NOT REQUIRED
SESSION 23 — ADVANCED L/ILW CONDITIONING TECHNOLOGIES - PART 1 OF 2 (1.11)
1) CEMENTITIOUS MATERIALS FOR RADIOACTIVE WASTE MANAGEMENT
WITHIN IAEA COORDINATED RESEARCH PROJECT (wP-59021)
Zoran Drace, IAEA; Michael Ojovan, University of Sheffield (Austria/UK)
The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in
2007. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste
management system with various purposes and included waste packages, wasteforms and backfills as well as investigation of interactions
and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered
were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid
waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical
processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods
of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged
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