atw 2018-05v6

inforum

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

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