1. MYRRHA Multipurpose hYbrid Research Reactor for High-tech Applications
Contributing to the 3rd Pillar of the European Strategy for P&T

2. ESNII + summer school –– Stockholm
MYRRHA
ESNII + summer school –– Stockholm
May 18-20, 2014
Marc Schyns
SCK•CEN, Boeretang 200, 2400 Mol, Belgium or

3. Content
SCK•CEN presentation
MYRRHA project

4. www.sckcen.be Belgian Nuclear Research Centre is a foundation
cradle of nuclear research, applications and energy development in Belgium
major international player in the field of nuclear R&D
creator of "spin-off's": IRE, BN, BP, VITO
tutorship: federal Secretary of Energy Melchior Wathelet
today: ~700 staff, >50% with academic degree + 70 PhD students
annual turnover: 125 M€
45% government support
55% contract work
research towards sustainability

5. Statutory mission of SCK•CEN
research on
safety
waste management
protection of man and environment
fissile and other strategic materials
societal implications of endurable energy
training and education
services towards
nuclear industry
the medical sector
the authorities in the field of nuclear applications

6. Environment Health Safety
'Analyse'
Radiation
Effects

7. Nuclear Material Science

8. 99Mo/99mTc Production
30-40 Million medical procedures per year = patients per day
65% (peak) - 25% (yearly) from BR2
but most existing research reactors are getting old

9. research, development needs education, training
1950
1970
1990
2010
2030
2050
2070
2090
1950
1970
1990
2010
2030
2050
2070
2090
research, development needs education, training

10. Some pioneering highlights
1st pressurized water reactor outside of US: BR3
Inventor of innovative nuclear fuel: MOX
Highest performing material testing reactor in Europe: BR2
World’s first
lead-based ADS:
GUINEVERE
World’s premiere project for transmutation of nuclear waste: MYRRHA
World’s first underground laboratory for R&D on HL waste disposal: HADES

11. MYRRHA - Accelerator Driven System
Reactor
Subcritical or Critical modes
65 to 100 MWth
Accelerator
(600 MeV - 4 mA proton)
Fast
Neutron
Source
Spallation Source
Lead-Bismuth
coolant
Multipurpose
Flexible
Irradiation
Facility
Innovative & Unique

12. MYRRHA Accelerator Challenge
fundamental parameters (ADS)
particle p
beam energy
600 MeV
beam current
4 mA
mode CW
MTBF
> 250 h
challenge !
failure = beam trip > 3 s
implementation
superconducting linac
frequency
176.1 / / MHz
reliability = redundancy
double injector
“fault tolerant” scheme

13. About beam trips

14. MYRRHA Accelerator Challenge

15. MYRRHA linac

16. Reactor layout 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

17. Core and Fuel Assemblies
151 positions
37 multifunctional plugs

18. Core and Fuel Assemblies
Cladding in Ti
Wire wrap
Wrapper

19. Cooling systems Decay heat removal (DHR) through secondary loops
4 independent loops
redundancy (each loop has 100% capability)
passive operation (natural convection in primary, secondary and tertiary loop)
Ultimate DHR through RVCS (natural convection)

20. Cooling systems

21. Integration into building

22. Remote Handling

23. Remote Handling (Fuel recovery)

24. Multipurpose facility
Fuel research
Φtot = 0.5 to n/cm².s
F = 1 to n/cm².s
(ppm He/dpa ~ 10)
in medium-large volumes
Material research
FFast = 1 to n/cm².s
(En>1 MeV) in large volumes
Fission GEN IV
Fusion
Multipurpose
hYbrid
Research
Reactor for
High-tech
Applications
High energy LINAC
600 MeV – 1 GeV
Long irradiation time
50 to 100 MWth
FFast = ~1015 n/cm².s
(En>0.75 MeV)
Fundamental
research
Waste
Fth = 0.5 to n/cm².s
(En<0.4 eV)
Fth = 0.1 to n/cm².s
(En<0.4 eV)
Radio-
isotopes
Silicon
doping

25. Motivation for transmutation
spent fuel reprocessing
no reprocessing
Uranium
naturel
Time (years)
Relative radiotoxicity
transmutation
of spent fuel
Duration Reduction 1.000x
Volume Reduction 100x

26. Fast Neutron are unavoidable for transmutation
To transmute MAs, we need to fission them
The ration Fission/Capture is more favorable with fast neutrons

27. European Strategy for P&T
The implementation of P&T of a large part of the high-level nuclear wastes in Europe needs the demonstration of its feasibility at an “engineering” level. The respective R&D activities could be arranged in four “building blocks”:
Demonstration of the capability to process a sizable amount of spent fuel from commercial LWRs in order to separate plutonium (Pu), uranium (U) and minor actinides (MA),
Demonstration of the capability to fabricate at a semi-industrial level the dedicated fuel needed to load in a dedicated transmuter (JRC/ITU),
Design and construction of one or more dedicated transmuters,
Provision of a specific installation for processing of the dedicated fuel unloaded from the transmuter, which can be of a different type than the one used to process the original spent fuel unloaded from the commercial power plants, together with the fabrication of new dedicated fuel.

28. P&T inspired many Euratom projects
TOPIC
FP5
FP6
FP7
Coupling
MUSE
DM2 ECATS
FREYA
Fuels
FUTURE
DM3 AFTRA
FAIRFUELS
Materials
MEGAPIE
DM4 DEMETRA
MATTER
SPIRE, TECLA
GETMAT
Design
PDS-XADS
DM1 DESIGN
CDT
MAX
ADOPT
EUROTRANS
SERIM G4
Thermal-Hydraulics
ASCHLIM
THINS
LFR -
ESLY
LEADER
Infrastructures
VELLA, MTRI3
ADRIANA, SARGEN, NEWLANCER
Scenario Studies
PATEROS
ARCAS
Safety
SEARCH, SILER, MAXSIMA
28 M€
31 M€
31 M€

29. Is sub-criticality a luxury?
Both Critical reactors as well as ADS can be used as MAs transmuters
Nevertheless, critical reactors, heavily loaded with MAs, can experience severe safety issue due to reactivity effet induced by a smaller fraction of delayed neutrons.
ADS can operate in a more flexible and safer manner even if heavily loaded with MAs hence leading to efficient transmutation therefore we say that sub-criticality is not a luxury but a necessity.
Proton Beam
Spallation Target
accelerator

30. ADS is the most efficient system for burning MAs
Pu Production Rate (grams / GWh)
MA Production Rate (grams / GWh)
* Mike Cappiello, (LANL), “The Potential Role of Accelerator Driven Systems in the US”, ICRS-10/RPS’2004, Madeira (PT), 2004

31. FP6-PATEROS A European approach to P&T
P&T useful for countries
in phase out
with active nuclear programme
Reduction of volume & heat load of waste
P&T should be seen at a regional/European level
Scenario studies: 4 country groups
A: stagnant or phase-out
B: continuation and Pu optimisation for FRs
C: subset of A in “nuclear renaissance”
D: non-nuclear to go nuclear

32. Even with completely different national NE policies European solution for HLW works with ADS
Advantages for A
ADS shared with B
ADS burn A’s Pu& MA
Smaller Fu-Cycle units & shared
SHARED
Scenario 1 objective: elimination of A’s spent fuel by 2100
A = Countries Phasing Out, B = Countries Continuing

33. If an ADS can’t produce electricity than it can’t also transmute !
Indeed, the 1st Objectif of an ADS is to burn efficiently and in a concentrated manner MAs !
If it burns MAs, this means it produces heat that can be turned into electricity.
The total thermal efficiency of an ADS is related to the two following yields:
The accelerator yield hacc = P->reactor / Pe (Acc)
The yield of the thermal-dynamic cycle of the sub-critical reactor hth= Pe (net) / Pth

34. MYRRHA: hTotal = 0.14 ΔPe = +12 MWe 600 MeV x 4 mA = 2.4 MW
hacc = 0.15
Pacc = 16 MWe
Pth = 85 MWth
hth = 0.33
Pe = 28 MWe
ΔPe = +12 MWe

35. EFIT: hTotal = 0.32 ΔPe = +126 MWe 600 MeV x 20 mA = 12 MW hacc = 0.35
Pacc = ~34 MWe
Pth = 400 MWth
hth = 0.40
Pe = 160 MWe
ΔPe = +126 MWe

36. JADS: hTotal = 0.37 ΔPe = +293 MWe 1500 MeV x 20 mA = 30 MW
hacc = 0.45
Pacc = ~67 MWe
Pth = 800 MWth
hth = 0.45
Pe = 360 MWe
ΔPe = +293 MWe

37. But MYRRHA is more than research on ADS & Transmutation

38. Multipurpose facility
Fuel research
Φtot = 0.5 to n/cm².s
F = 1 to n/cm².s
(ppm He/dpa ~ 10)
in medium-large volumes
Material research
FFast = 1 to n/cm².s
(En>1 MeV) in large volumes
Fission GEN IV
Fusion
Multipurpose
hYbrid
Research
Reactor for
High-tech
Applications
High energy LINAC
600 MeV – 1 GeV
Long irradiation time
50 to 100 MWth
FFast = ~1015 n/cm².s
(En>0.75 MeV)
Fundamental
research
Waste
Fth = 0.5 to n/cm².s
(En<0.4 eV)
Fth = 0.1 to n/cm².s
(En<0.4 eV)
Radio-
isotopes
Silicon
doping

39. Material Irradiation Performances Critical@100 MW
IPS in Chan [0 0 0]
IPS in Chan [2 0 0]
Sample n°
dpa/EFPY
Φtot 8
18.1
2.38E+15
16.2
2.12E+15 7
23.0
2.85E+15
20.7
2.54E+15 6
25.9
3.19E+15
23.3 5
27.5
3.37E+15
24.5
3.02E+15 4
27.2
3.39E+15
3.03E+15 3
25.7
3.23E+15
22.9
2.89E+15 2
22.3
2.92E+15
19.9
2.62E+15 1
17.3
2.50E+15
15.5
2.23E+15

40. Irradiation capabilities of IPS Sub-critical @ 73 MW
Total flux, n/(cm2s)
Fast
(> 0.75 MeV) flux, n/(cm2s)
Radiation damage,
DPA/FPY
Helium production, appm/FPY
Ratio
appm He/DPA 1
2.64×1015
4.20×1014
22.3
7.66
0.343 2
2.72×1015
4.29×1014
23.0
10.41
0.452 3
2.75×1015
23.1
5.94
0.257 4
4.18×1014
22.5
6.59
0.293 5
2.70×1015
4.35×1014
22.7
6.52
0.288 6
2.68×1015
4.23×1014
22.8
10.78
0.474

41. Prepare the path for Fusion DEMO Irradiation capabilities under the spallation target
+10 cm
0 cm
-30 cm

42. MYRRHA-IMIFF for fusion material
In critical mode (fast reactor), appmHe/dpa ~ 0.2 to 1  not optimal for fusion materials experiments
In sub-critical mode (ADS), high appmHe/dpa ratio is reached, specially in the region of the window of spallation source
Volume of 1 lt with appmHe/dpa ~ 12 close to spallation target
Useful volume
30 lt with range from 5 to 20 appmHe/dpa

43. MYRRHA for fusion irradiations
Estimated damage induced in DEMO and proposed
irradiation conditions in IFMIF and MYRRHA-IMIFF

44. Multipurpose facility
Fuel research
Φtot = 0.5 to n/cm².s
F = 1 to n/cm².s
(ppm He/dpa ~ 10)
in medium-large volumes
Material research
FFast = 1 to n/cm².s
(En>1 MeV) in large volumes
Fission GEN IV
Fusion
Multipurpose
hYbrid
Research
Reactor for
High-tech
Applications
High energy LINAC
600 MeV – 1 GeV
Long irradiation time
50 to 100 MWth
FFast = ~1015 n/cm².s
(En>0.75 MeV)
Fundamental
research
Waste
Fth = 0.5 to n/cm².s
(En<0.4 eV)
Fth = 0.1 to n/cm².s
(En<0.4 eV)
Radio-
isotopes
Silicon
doping

45. MYRRHA - Concept ISOL@MYRRHA - Concept MYRRHA - Concept
thin refractory metal foils
carbide powders
liquid targets
surface ion source
ECR ion source
RILIS

46. Beam-Splitting System (Concept)
Questions:
- Is there a (big) interest for the users community to upgrade the linac from 600 MeV to 1 GeV?
600 MeV
~ mA
pulsed beam
(up to 250 Hz)
MeV
2 - 4 mA CW

47. Applications (ISOL@MYRRHA Applications)
Nuclear Physics
Astro-physics
Atomic Physics
Fundamental Interactions
Medical Applications
Day
Week
Month
Year
Typical Beam Time/Experiment
Condensed Matter
Chemistry
Biology
d<r2>, m, Q
Masses
Decay (log ft, Pxn/yp)
Reactions (s, B(E2), C2S)
QED tests in HCI
Rare decays: GTGR, bxn/yp, cluster decay, SHE Extreme precision: e.g., crystal spectrometry
Prototyping
Ft values, Correlations (b-n,…), EDM
Correlations (b-n, ...), EDM: Statistics + control systematic effects of setup
Mössbauer, b-NMR, PAC, EC-SLI
Systematic sample measurements
SHE chemistry
Mn, Fe, Ni, Cu, Zn b-NMR in proteins
Radiopharmacy (prototyping)
Radiotherapy (prototyping)
Systematic production of Radiopharmaceuticals
Dedicated radiotherapy center
Ultra-high selectivity: LIST configuration
Bohr-Weisskopf: A- and g-factors

48. - Highlights

49. Multipurpose facility
Fuel research
Φtot = 0.5 to n/cm².s
F = 1 to n/cm².s
(ppm He/dpa ~ 10)
in medium-large volumes
Material research
FFast = 1 to n/cm².s
(En>1 MeV) in large volumes
Fission GEN IV
Fusion
Multipurpose
hYbrid
Research
Reactor for
High-tech
Applications
High energy LINAC
600 MeV – 1 GeV
Long irradiation time
50 to 100 MWth
FFast = ~1015 n/cm².s
(En>0.75 MeV)
Fundamental
research
Waste
Fth = 0.1 to n/cm².s
(En<0.4 eV)
Radio-
isotopes
Silicon
doping
Fth = 0.5 to n/cm².s
(En<0.4 eV)

50. Production of space specific radioisotopes in MYRRHA thermal neutron flux-traps
Core lay-out:
In reflector positions
Cooled by water
In thermalized neutron field
Transport by rabbit system
Positions also usable for
testing of materials in
thermal field!
=> Both are possible in MYRRHA:
Testing of materials/fuels in fast (core) field
Testing of materials/fuels in thermalized (peripheral) field
Target plates in IPS:

51. priority list projects
European Context
Knowledge
Economy
Energy
Independence
ESFRI
European Strategic Forum for Research Infrastructure
SET Plan
European Strategic Energy Plan
Confirmed on ESFRI
priority list projects
in ESNII
(SNETP goals)

52. Belgian commitment: secured International consortium: under construction
2nd phase (11 y)
others 576 M€
960 M€
(2009)
Consortium
Belgium 324 M€
(36 M€/y x 9 y)
Belgium 60 M€
(12 M€/y x 5 y)

53. management and investment structure
The project schedule
Front End
Engineering
Design
2015
Tendering &
Procurement
Construction of
components &
civil engineering
2019
On site
assembly
Commissioning
2023
Progressive
start-up
2024-
Full
exploitation
Minimise
technological
risks
Secure
the licensing
Secure a sound
management and investment structure
PDP
preliminary
dismantling
plan
PSAR
preliminary
safety
assesment
EIAR
environmental impact
assesment
FEED
(Front End
Engineering
Design)
Central
Project
Team
Owner
Consortium
Group
Owner
Engineering
Team

54. MYRRHA international network

55. International Members Consortium – Phase 1 As of early 2012
INVESTMENT PHASE
International Members Consortium – Phase 1 As of early 2012 BE
EU countries
Asian country EU
ROW
SCK•CEN
(on behalf of Belgian
Federal
Government)
EU country
Public foundation
EU participation
ROW participation
Belgian Federal Ministry
of Energy
(50%)
of Science Policy (50%)
40 %
Major European partners
A major Asian partner
EU FP7 (RTD) / SET-Plan (Energy)
(*) European Research Infrastructure Consortium
«ERIC» (*)
Contribution to investment capital
(960 M€’09)
Participation vehicle
(Consortium members)
Primary «investors»
IPR
management rules tbd

56. International Members Consortium - Phase 2
OPERATION PHASE
International Members Consortium - Phase 2
Members of Consortium
Individual research of a member of Consortium
Collaborative research amongst members of Consortium
- 3 years program commitment
CLOSED/
SHARED
INFORMATION
for MoC
Open User Facility
Governments funding
Criteria of research excellence
Independant program access committee (PAC)
Collaborative research
- Distribution of information to participants
Contract research…..
Commercial services RI
NTD Silicon
~25%
OPEN INFORMATION
SHARED INFORMATION
for participants
CLOSED
«ERIC» (*)
(*) European Research Infrastructure Consortium
BENEFITS for Members of Consortium
Board position to control overal operation
Priority of access
Potential benefit of low price (compensation profit from commercial revenues)
Capacity transfer flexibility (rules tbd)
SCK•CEN
as qualified and licenced operator of the MYRRHA infrastructure under contractual arrangement with ERIC

57. ECR source & Injector Building
MYRRHA: EXPERIMENTAL ACCELERATOR DRIVEN SYSTEM A pan-European, innovative and unique facility at Mol (BE)
BR2 reactor
(existing)
Utilities
buildings
MYRRHA reactor
building
MYRRHA LINAC
high energy tunnel
ECR source & Injector Building

58. SCK•CEN in brief
SCK•CEN is an internationally renowned research centre
SCK•CEN’s innovative research is directed to the safe application of nuclear energy on both short and long term;
SCK•CEN contributes in an important manner to non-power related society-relevant applications of nuclear energy;
SCK•CEN emphasizes the need for fundamental knowledge, education and training: the SCK•CEN Academy for Nuclear Science and Technology;
SCK•CEN has an innovative future-oriented project MYRRHA;

59. Conclusions
MYRRHA As a Multipurpose Fast Spetrum irradiation facility selected by ESFRI, is responding to:
The issue of addressing the nuclear waste legacy of present reactor technology through advance options (ADS, P&T)
The SNETP need for a multipurpose research infrastructure expressed in its Strategic Research Agenda whatever the considered technology for Gen.IV systems
The Objective of Belgium and SCK•CEN to maintain a high level expertise in the country in the nuclear safety, nuclear technology and nuclear competencies independently of the future of NE
The objective of the European Commission to make available a series of relevant irradiations facilities for the fusion material research community towards the DEMO construction
Secure society needs for RI for medical applications and Dopped-Si for renewable Energy

60. Q&A

61. Copyright © 2013 - SCKCEN SCK•CEN
PLEASE NOTE!
This presentation contains data, information and formats for dedicated use ONLY and may not be copied, distributed or cited without the explicit permission of the SCK•CEN. If this has been obtained, please reference it as a “personal communication. By courtesy of SCK•CEN”.
SCK•CEN
Studiecentrum voor Kernenergie
Centre d'Etude de l'Energie Nucléaire
Belgian Nuclear Research Centre
Stichting van Openbaar Nut
Fondation d'Utilité Publique
Foundation of Public Utility
Registered Office: Avenue Herrmann-Debrouxlaan 40 – BE-1160 BRUSSELS
Operational Office: Boeretang 200 – BE-2400 MOL