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) Copyright © 2012 SCK•CEN ICAPP’12 Conference Chicago, 24-28 June 2012 1

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 2

Fission generates High-Level Nuclear Waste

n

Neutron

Fuel U 235

Uranium

Fission U 238 n n n U 235 U 238 Actinides Minor Actinides Pu Plutonium Np Neptunium Am Americium Cm Curium Minor Actinides

high radiotoxicity long lived waste that are difficult to store due to: 

Long lived (>1,000 years)



Highly radiotoxic



Heat emitting

3

Motivation for Transmutation

transmutation of spent fuel spent fuel reprocessing no reprocessing Uranium naturel Time (years) Duration Reduction 1.000x

4

Volume Reduction 100x

MYRRHA is an Accelerator Driven System

Accelerator

(600 MeV - 4 mA proton)

Reactor

• Subcritical mode • 65 to 100 MWth

Spallation Source Multipurpose Flexible Irradiation Facility Fast Neutron Source

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Lead-Bismuth coolant

Continuity: SCK•CEN has a long tradition of «first of a kind»

1st pressurized water reactor (PWR) outside of US (BR3) Inventor of innovative nuclear fuel (MOX fuel) Highest performing material testing reactor in Europe (BR2) World first underground laboratory for R&D on HL waste disposal (HADES) World first lead based ADS (GUINEVERE) World premiere project for transmutation of nuclear waste 6

2008 SFR 2012

The place of MYRRHA in ESNII

European Sustainable Nuclear Industrial Initiative

2020

Reference technology

ASTRID Prototype (SFR) MYRRHA ETPP European demonstration reactor (LFR) LFR

Alternative technology

GFR Supporting infrastructures, research facilities MYRRHA Fast spectrum irradiation facility

7

ALLEGRO Experimental reactor (GFR)

MYRRHA is an international project

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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 9

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 11

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

 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 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 14

Reactor layout

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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

Diaphragm

  Material  AISI 316L  Main dimensions  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 Weight  About 190 ton 18

Core and Fuel Assemblies

 151 positions & 37 multifunctional plugs 19

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 21

Copyright notice

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

CEN

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