The fast-spectrum transmutation experimental facility
FASTEF: main design achievements (part 1: Core &
Primary system) within the FP7-CDT collaborative project
of the European Commission
Didier De Bruyn & Rafaël Fernandez (SCK•CEN),
Luigi Mansani (Ansaldo), Antony Woaye-Hune (AREVA),
Massimo Sarotto (ENEA) & Evaldas Bubelis (KIT)
ICAPP’12 Conference
Chicago, 24-28 June 2012
Copyright © 2012
SCK•CEN
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Table of contents
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Purpose of the MYRRHA project at SCK•CEN
Place of FP7 CDT project in this frame
Conclusions of WP2 related to primary system
Illustrations of design today
Way ahead to construction
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Fission generates High-Level Nuclear Waste
Fuel
U235
U235
n
Minor Actinides
Actinides
n
Neutron
Uranium
Fission
n
n
U238
U238
Pu
Np
Am
Cm
Plutonium
Neptunium
Americium
Curium
Minor Actinides
high radiotoxicity long lived waste
that are difficult to store due to:
 Long lived (>1,000 years)
 Highly radiotoxic
 Heat emitting
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Relative radiotoxicity
Motivation for Transmutation
spent fuel
reprocessing
transmutation
of spent fuel
no
reprocessing
Uranium
naturel
Time (years)
Duration Reduction
1.000x
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Volume Reduction
100x
MYRRHA is an Accelerator Driven System
Reactor
Accelerator
• Subcritical mode
• 65 to 100 MWth
(600 MeV - 4 mA proton)
Spallation Source
Multipurpose
Flexible
Irradiation
Facility
Fast
Neutron
Source
Lead-Bismuth
coolant
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Continuity: SCK•CEN has a long tradition
of «first of a kind»
1st pressurized water
reactor (PWR)
outside of US (BR3)
World first underground
laboratory for R&D on HL
waste disposal (HADES)
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Inventor of
innovative nuclear
fuel (MOX fuel)
Highest performing
material testing reactor
in Europe (BR2)
World first
lead based ADS
(GUINEVERE)
World premiere project
for transmutation of
nuclear waste
The place of MYRRHA in ESNII
European Sustainable Nuclear Industrial Initiative
2008
SFR
2012
2020
ASTRID
Prototype
(SFR)
Reference
technology
MYRRHA
ETPP European
demonstration reactor
(LFR)
LFR
Alternative technology
GFR
Supporting infrastructures, research facilities
MYRRHA
Fast spectrum
irradiation facility
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ALLEGRO
Experimental reactor
(GFR)
MYRRHA is an international project
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Table of contents
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Purpose of the MYRRHA project at SCK•CEN
Place of FP7 CDT project in this frame
Conclusions of WP2 related to primary system
Illustrations of design today
Way ahead to construction
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The CDT project aimed at going further:
 Starting from the outcome of different FP projects
(PDS-XADS, EUROTRANS) and national
initiatives (MYRRHA),
 Obtain a more advanced design of a flexible
irradiation facility, FASTEF, able to work in both
sub-critical and critical mode,
 Setting also up a centralised multi-disciplinary
team, based at Mol for its core group,
 Concentrating on primary and core systems (this
paper) and on reactor building design & plant
layout (other paper – session 9.05),
 The project started in April 2009 for a duration of
36 months.
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Table of contents
 Purpose of the MYRRHA project at SCK•CEN
 Place of FP7 CDT project in this frame
 Conclusions of WP2 related to primary
system
 Illustrations of design today
 Way ahead to construction
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FASTEF is a performing, rubust facility
 Maximum core power amounts 100 MWth;
 High fast flux intensity obtained by maximizing
poxer density;
 Many positions available in the core to host
experiments;
 All components in reactor vessel designed to be
removable;
 Diaphragm separates hot and cold coolant;
 Safety analyses demonstrate robustness against
transients.
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Table of contents
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Purpose of the MYRRHA project at SCK•CEN
Place of FP7 CDT project in this frame
Conclusions of WP2 related to primary system
Illustrations of design today
Way ahead to construction
13
Reactor layout
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Reactor Vessel
Reactor Cover
Core Support Structure
 Core Barrel
 Core Support Plate
 Jacket
Core
 Reflector Assemblies
 Dummy Assemblies
 Fuel Assemblies
Spallation Target Assembly and Beam Line
Above Core Structure
 Core Plug
 Multifunctional Channels
 Core Restraint System
Control Rods, Safety Rods, Mo-99 production units
Primary Heat Exchangers
Primary Pumps
Si-doping Facility
Diaphragm
 IVFS
IVFHS
 IVFHM
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Reactor Vessel
 Main dimensions
 Height: about 12.200 m
 Inner diameter: 8 m
 Wall thickness: 80 mm
 Material
 AISI 316L
 Weight
 About 320 ton
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Reactor Cover
 Main dimensions
 Height: 2 m
 Outer diameter: 9.3 m
 Material
 AISI 316L
 Concrete
 Weight
 About 340 ton
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Reactor Cover
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Diaphragm
 Main dimensions
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Double plate design
Baffle
In-vessel fuel storage
Height: about 9.8 m
Inner diameter: 7.7 m
Wall thickness: 50 mm
Lower plate thickness: 80 mm
Upper plate thickness: 50 mm
 Material
 AISI 316L
 Weight
 About 190 ton
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Core and Fuel Assemblies
 151 positions & 37 multifunctional plugs
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Table of contents





Purpose of the MYRRHA project at SCK•CEN
Place of FP7 CDT project in this frame
Conclusions of WP2 related to primary system
Illustrations of design today
Way ahead to construction
20
The project schedule
 2010 – 2014: Front End Engineering Design; file
for the Belgian Government
 2015: Tendering & Procurement
 2016 – 2018: Civil Engineering & construction of
components
 2019: On site assembly
 2020 – 2022: Commissioning at progressive
power
 2023: Progressive start-up
 2024 – 20??: Full exploitation
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Copyright notice
Copyright © 2012 - SCKCEN
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SCK•CEN
Studiecentrum voor Kernenergie
Centre d'Etude de l'Energie Nucléaire
Stichting van Openbaar Nut
Fondation d'Utilité Publique
Foundation of Public Utility
Registered Office: Avenue Herrmann-Debrouxlaan 40 – BE-1160 BRUSSEL
Operational Office: Boeretang 200 – BE-2400 MOL
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