atw 2018-05v6

atw Vol. 63 (2018) | Issue 5 ı May
DECOMMISSIONING AND WASTE MANAGEMENT 312
e-learning, induction
'generic' training course
as introduction
specific, topical courses
for specialisation
| | Tab. 2.
ELINDER Decommissioning Training Modules.
Basics on nuclear industrial applications and radiation safety
Overview of: regulation and standards, status of the play, experience
feedback, waste management, technical and organisational issues, radiation
safety, stakeholder involvement
Decommissioning planning and cost assessment
Licensing and environmental impact assessment
Programme and project management
Decommissioning Safety
Waste and material management
Decontamination and Dismantling techniques
Metrology for Waste Characterisation and Clearance
Environmental remediation and site release
well as on her/his actual and targeted
level of knowledge, skills and competences.
5.3 ELINDER qualification
To ensure a coherent and harmonised
approach, shared minimum quality
criteria including learning outcomes
will be defined for acceptance of the
course modules within the ELINDER
programme and receiving the
“ELINDER stamp” (Figure 4).
In a next step, the programme will
be aligned to enable the certification
of specific job profiles in nuclear
decommissioning, following the
ECVET credit system.
6 Conclusions
The nuclear decommissioning business
is expected to grow in the coming
decades. The delivery of related
education and training programmes is
still at an early stage of development.
The opportunity could be taken to
harmonise quality criteria and learning
outcomes, which allows more
transparency for the industrial actors
but also facilitate the promotion of
competences in this field.
The ELINDER project aims to
provide a European answer to these
prospects. The programme has been
prepared with a variety of experienced
partners and with the IAEA,
and is actually implemented from
2018 on.
References
[1] Education and Training in Decommissioning
– Needs, Opportunities and
Challenges for Europe,
ISBN 978-92-79-51836-2 (2015).
[2] ECTS Users' Guide, European Commission,
ISBN 978-92-79-09728-7 (2009).
[3] Recommendation of the European
Parliament and of the Council on the
establishment of a European Credit
System for Vocational Education and
Training, 2009/C 155/02, O.J. of the EU
dd. 8.7.2009.
[4] Top-Down Workforce Demand from
Energy Scenarios: Sensitivity Analysis,
European Commission (2016).
Authors
Pierre Kockerols
Hans Günther Schneider
Daniela Santopolo
EUROPEAN COMMISSION
Joint Research Centre
21, Rue Champ de Mars
1049 Bruxelles, Belgium
The New CASTOR® geo – A Comprehensive
Solution For Transport and
Storage of Spent Nuclear Fuel, MOX
and Damaged Fuel
Linus Bettermann and Roland Hüggenberg
Dry interim storage has become a common solution for the disposal of spent fuel in recent years worldwide.
However, in particular the complete defueling of NPP prior to decommissioning and dismantling will dramatically
increase the demand especially for non-standard fuel. Here we present the new dry storage system by GNS for
international markets with its capability to also store MOX and damaged spent fuel.
Introduction
Dry interim storage systems for spent
fuel assemblies have been in use
worldwide for more than three
decades by now. Starting with the first
CASTOR® dry storage systems by GNS
in the early 80s, this proven and
reliable technology has enhanced the
safe storage of spent fuel in countless
NPP worldwide. More than 1300
CASTOR® casks have been loaded and
safely stored over the past decades all
over the world, including Germany,
the US, South Africa and several
eastern European countries. This
made the CASTOR® cask system a
well known and internationally established
trademark for the safe transport
and storage of spent nuclear fuel
and high-level waste.
The sound operational record is
backed by a common design philosophy
that remained unchanged for
various CASTOR® cask types. The
casks feature a monolithic cask
body made of ductile cast iron with
machined cooling fins to improve the
heat dissipation. Neutron shielding is
provided by means of polyethylene
neutron moderators, filled in drilled
bore holes in the casks wall. This is a
major benefit in safety compared to
neutron moderators that are attached
to the outside of the cask wall, when
it comes to thermal accidents. The
CASTOR® casks are closed by a bolted
double lid system. Both independent
lids are sealed with metal gaskets that
are suitable for longterm interim
storage. During storage both lids are
permanently monitored to observe
leak tightness. All cask components
Decommissioning and Waste Management
The New CASTOR® geo – A Compre hensive Solution For Transport and Storage of Spent Nuclear Fuel, MOX and Damaged Fuel ı Linus Bettermann and Roland Hüggenberg