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Title

IFMIF; Overview of the validation activities
J. Knaster, F. Arbeiter, P. Cara, P. Favuzza, T. Furukawa, F.

Author(s)Groeschel, R. Heidinger, A. Ibarra, H. Matsumoto, A. Mosnier, H.
Serizawa, M. Sugimoto, H. Suzuki and E. Wakai

Citation
Text Version

Nuclear Fusion, 53(11), 116001
Authorhttp://jolissrch-inter.tokai-

URL

DOI

sc.jaea.go.jp/search/servlet/search?5042314
http://dx.doi.org/10.1088/0029-5515/53/11/116001

This is an Author's Accepted Manuscript of an article published
Rightin Nuclear Fusion 2013 © IOP Publishing Ltd, available online
at: http://dx.doi.org/10.1088/0029-5515/53/11/116001

Japan Atomic Energy Agency

1

IFMIF: Overview of the Validation Activities
J. Knaster1, F. Arbeiter2, P. Cara3, P. Favuzza4, F. Groeschel1, R. Heidinger3, A. Ibarra5, H.
Matsumoto1, A. Mosnier3, M. Sugimoto6, H. Suzuki6, E. Wakai6
1

IFMIF/EVEDA Project Team, Rokkasho, Japan; 2KIT, Karlsruhe, Germany; 3F4E, Garching,
Germany; 4ENEA, Brasimone, Italy; 5CIEMAT, Madrid, Spain; 6JAEA, Rokkasho, Japan.
E-mail contact of corresponding author: juan.knaster@ifmif.org
Abstract. The Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion
Materials Irradiation Facility (IFMIF), an international collaboration under the Broader Approach Agreement
between Japan Government and EURATOM, aims at allowing a rapid construction phase of IFMIF in due timewith an understanding of cost involved. The three main facilities of IFMIF: 1) the Accelerator facility, 2) the
Target facility and 3) the Test facility are the subject of validation activities that include the construction ofeither full scale prototypes or smartly devised scaled down facilities that will allow a straightforward
extrapolation to IFMIF needs. By July 2013, the engineering design activities of IFMIF matured with thedelivery of an Intermediate IFMIF Engineering Design Report (IIEDR) supported by experimental results. The
installation of a Linac of 1.125 MW (125 mA and 9 MeV) of deuterons started in March 2013 in Rokkasho(Japan). The world largest liquid Li test loop is running in Oarai (Japan) with an ambitious experimental
programme for the years ahead. A full scale High Flux Test Module that will house ~1000 small specimens
developed jointly in Europe and Japan for the Fusion programme has been constructed by KIT (Karlsruhe)
together with its He gas cooling loop. A full scale Medium Flux Test Module to carry out on-line creep
measurement has been constructed by CRPP (Villigen).

1. Introduction
In DEMO like in future fusion power plants, the deuterium-tritium nuclear fusion reactions
will generate a large quantity of 14.1 MeV neutrons that will collide with the materials of thereactor vessel. The first wall, a combination of layers of different materials that aims tomaximize the conversion of neutrons into thermal energy and breed tritium will be critically
exposed. Understanding the degradation of the mechanical properties throughout the reactor
operational life is a key parameter to allow the design and eventual facility licensing by thecorresponding nuclear authorities.
Inelastic collisions of neutrons with the nuclei in the structural materials over the thresholdincident energy of around 3 MeV will transmute heavy nuclei, which can decay releasing p +and α-particles. In turn, the elastic collisions are measured by NRT displacements per atom
(NRT dpa) [1] with a cross section inversely proportional to the average displacement energy
threshold for production of a Frenkel vacancy-interstitial atom defect pair in the material. Not
all the materials will present the same NRT dpa under same neutrons bombardment, neither
will all areas inside the reactor vessel undergo the same flux and spectrum of neutrons. In
addition, NRT dpa do not take into account the time-evolution of radiation damage in thematerials, such as recombination, migration, and coalescence of radiation defects, and in thissense they represent an atom-based approximate measure of the irradiation exposure of thematerial to the fusion neutrons. The generation of He and H from transmuted elements
together with displacement effects in the materials lattice under fusion-like neutron
bombardement has inherent uncertainties on the effects on mechanical and physical properties
that can only be overcome through testing in as close as possible conditions [2].

2
IFMIF, the International Fusion Materials Irradiation Facility, will generate a neutron flux
with a peak at around 14 MeV by (d,Li) stripping reactions thanks to two parallel deuteronaccelerators colliding in a liquid Li screen with a footprint of 20 cm x 5 cm. The energy of thebeam (40 MeV) and the current of the parallel accelerators (2 x 125 mA) have been tuned tomaximize the neutrons flux (1018 m-2s-1) to get irradiation conditions comparable to those in
the first wall of a fusion reactor in a volume of 0.5 l that will house around 1000 small
specimens [3]. This will allow the accurate determination of those properties considered
critical (fatigue, fracture toughness, crack growth rate, creep and tensile stress) of suitablematerials and allow the understanding of the degradation that will lead to design moreradiation hard components.

Figure 1. Schematic of IFMIF.

The purposed-designed reduced activation ferritic-martensitic steels (RAFM) present
typically around 80% of its constituents presenting an average displacement energy (Wigner
energy) of 40 eV that can reach over 15 dpa/year in a full power operation fusion reactor [4].
The accumulation of gas in the materials lattice is intimately related with neutron energy
threshold at around 3 MeV; neutrons below these energies do not transmute the Fe nuclei andtherefore gas is not efficiently generated. This is a major drawback for fusion materials testingin fission reactors as they present average n energies around 2 MeV. In turn, spallation
sources present a neutron spectrum with long tails reaching the hundreds MeV range
transmutation efficiency, especially for the lighter elements which have a high potential indeteriorating mechanical properties. A comparison of IFMIF with other available neutron
sources has been performed [5], where it is explained how the spectrum that IFMIF provides,
reproduces accurately fusion reactors spectrum with a flattop near the 14 MeV peak and atintermediate energies, while the closest available spallation sources, ESS and XADS, are oneorder of magnitude lower in flux in these critical range of energies.

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Figure 2. Neutron flux compared with the one DEMO will present in available and planned neutron
sources including IFMIF [5]IFMIF, presently in its Engineering Validation and Engineering Design Activities phase(IFMIF/EVEDA), started in 2007 under the framework of the Broader Approach (BA)
Agreement between EURATOM and Japan, is entering into conclusive stages [6]. In July
2013, the engineering design of IFMIF have been completed with the delivery of anIntermediate IFMIF Engineering Design Report (IIEDR) supported by experimental results[7].
An overview of the validation activities already achieved is reported. Details of on-goingvalidation activities will be provided.
2. IFMIF Validation Activities
The validation activities have been the subject of a successful Japan-Europe scientificcollaboration [8,9]. In order to produce the experimental backing of the IFMIF Design during
the EVEDA phase, 3 major prototypes have been designed and manufactured: an Accelerator Prototype (LIPAc) at Rokkasho, fully representative of the IFMIF low
energy (9 MeV) accelerator (125 mA of D+ beam in continuous wave) to be completed
in June 2017 [10,11];
 a Lithium Test Loop (ELTL) at Oarai, integrating all elements of the IFMIF lithium
target facility, already commissioned in February 2011 [12,13] complemented bycorrosion experiments performed at the LIFUS6 lithium loop at Brasimone [14]; the High Flux Test Module (different designs) [15,16] and its internals to be irradiatedin a fission reactor [17] and tested in the helium loop HELOKA [18] complemented theCreep Fatigue Test Module [19] manufactured and tested in full scale at Villigen.
While this overview has to leave to the above cited papers the description of design andexperimental details, also of the overall activities, the focus is given here to the outcome ofthe validation activities already achieved and still expected.

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2.1 The Accelerator Facility Validation activities
The accelerator requirements of the Linear IFMIF Prototype Accelerator (LIPAc), incomparison with IFMIF, are given in the following synthetic table defining its main
specifications:
TABLE I: MAIN PARAMETERS OF LIPA (COMPARED TO IFMIF ACCELERATORS)

Primary Parameters
Number of Linacs
Duty factor
Ion type
Beam intensity on target
Beam kinetic energy on target
Beam Power on target
RF Frequency
Target material
Total length
Injector length
RFQ length
MEBT length
SRF Linac length
Number of cryomodules
HEBT total length

LIPAc
1
CW
D+
125
9
1.125
175
Cu
34.0
5.0
9.8
2.3
4.6
1
9.6

IFMIF
2
CW
D+
2 x 125
40
2x5
175
Li
84.7
5.0
9.8
2.3
22.4
2x4
45.0

Units
mA
MeV
MW
MHz
m
m
m
m
m
m

The setting-up of the 1.125 MW Linac in Rokkasho, for which the first accelerator subsystems provided by the European Home Team has arrived in March 2013, requires a wellcoordinated integration and commissioning programme, due to the distributed nature of thedeliveries (see figure 3):
 The accelerator components designed, manufactured and tested by European
institutions (CEA, CIEMAT, INFN, SCK-CEN) are: Injector, Radio Frequency
Quadrupole (RFQ), Medium and High Energy Beam Transport lines, Superconducting
RF Linac, Beam Dump, 175 MHz RF Systems, Local Control Systems, Beam
Instrumentation; The conventional facilities (building and main auxiliaries), the Central Control System,
as well as the RFQ couplers, are provided by JAEA;

5

Figure 3. Layout of IFMIF accelerator validation facility with the indication of the different laboratory
contributions

As an essential element of this programme, specific central databases, management systems andprocedures is being implemented such as a documentation management system, an interface
management system, assembly procedures and a 3D configuration management of the facility[20].
The LIPAc beam is generated by an injector (4.4) using an Electron Cyclotron Resonance (ECR)
deuteron (D+) source (4.4.1). After being properly focussed and filtered along the Low Energy
Beam Transport (LEBT, 4.4.2) unit, the D+ beam is accelerated by two successive systems: anormal-conducting RFQ (4.5) and 8 superconducting Half-Wave Resonators (HWR) locatedwithin the SRF Linac (4.7) (see figure 4).

Figure 4. Functional scheme of the LIPAc System.

After control and measurement of the beam parameters, the D+ current is stopped by a Beam
Dump (BD, 4.8.2). Between these systems, specific Medium Energy Beam Transport (MEBT, 4.6)
and High Energy Beam Transport (HEBT, 4.8.1) lines transport and match the beam properties tothe downstream components.

6
Amplifier chains (4.10.2), part of the RF Power System (4.10), based on tetrodes, provide the RF
power required.
A Cryoplant (4.14) is needed to cool down and maintain the 4.5 K temperature in the SRF Linac.
The beam instrumentation (4.9) is distributed along the machine, in addition to the diagnostics
included in each subsystem.
The building, completed in Rokkasho in March 2010, consists of an accelerator vault, a nuclear
heating, ventilation and air conditioning (HVAC) area, a heat exchange and cooling water area forboth radiation controlled and non-controlled areas, an access room, a control room, and a large
hall for power racks, RF systems (HVPS and RF power chains) and the 4 K refrigerator (see figure5). The accelerator vault is surrounded by 1.5 m thick concrete walls and ceiling. The descriptionsof the accelerator components, as well as their status, are presented hereafter.

Figure 5. 3D view of the LIPAc facility

IFMIF accelerator, with its 5 MW will become the most powerful Linac in the world,
however its prototype, LIPAc will on its own lead the world Linac beam power (see figure 6).

7

LIPAc

Figure 6. Beam energy vs beam power in existing worldwide hadron Linacs

2.1.1 The Injector + LEBTThe ion source delivers a continuous deuteron beam (140 mA, 100 keV) with high availability
and low emittance. It includes an ion source, based on an electron cyclotron resonance cavity,
and a Low Energy Beam Transport line (LEBT) to transport and match the extracted beam to
the RFQ entrance by means of a dual solenoid focusing scheme (see figure 7 and figure 8)[21, 22]. In addition, an electrostatic chopper will be implemented between the two solenoids
to enable the operation of LIPAc with short pulses of very sharp rise/fall times.
The injector was assembled at CEA-Saclay in order to test the components before the arrivalin Japan, scheduled at the beginning of 2013. After the first H+ beam produced in May 2011),
a test campaign was carried out in pulsed and continuous operation. Pulsed beams of 150 mA
at 100 kV and continuous beams of 100 mA at 75 kV were routinely produced. The first D+
beam was extracted in April 2012, first in pulsed mode and then in continuous mode for ashort period in order to limit the activation of the elements. However, as the continuous
operation at 100 kV was limited by HV discharges in the extraction system, a new 5 electrodesystem (instead of the former 4 electrode system aiming to minimize the beam emittance) has
been installed and injector tests started again at the end of September 2012 to complete theoptimization (ion source plasma, space charge compensation, solenoid setting) andcharacterize the beam emittance targeting RMS emittance values lower than 0.25 mm·mrad.

8

Figure 7. Beam extraction system
Figure 8. Low Energy Beam Transfer

2.1.2 The Radio Frequency Quadrupole (RFQ)The 4-vane Radio Frequency Quadrupole (RFQ) under development by INFN, will pre-bunch
the DC beam from the ion source and will accelerate the beam from 0.1 to 5 MeV. The 9.8 m
long 175 MHz cavity is composed of 18 x 0.54 m long modules flanged together and aligned
within 0.3 mm tolerance [23]. The RFQ is the world longest. The peak surface electric field islimited to a maximum value of x1.8 Kilpatrick’s criterion [24].
The RF tuning of the RFQ is ensured by 22 slug tuners per quadrant. An aluminium full scale
RFQ model was built to validate the tuning procedures and the mode stabilization by meansof bead-pull measurements(see figure 9).
After manufacturing, leak tests and dimensional checks of prototype modules to develop themachining and brazing procedures [25], the RFQ module production has started (see figure10). Three modules (plus the RF plug) have been completed before the end of 2012 for highpower tests, planned at the beginning of 2013 at INFN-Legnaro.

Figure 9. Aluminium full scale RFQ model to validate tuning procedures

The RF power (about 1300 kW) is injected by 8 loop couplers, using 6 1/8” RF windows.
High power tests have been performed with a high-Q load circuit at JAEA-Tokai. Final

9
acceptance tests and RF conditioning in TW mode of two complete couplers (waveguide,
window and tip modules) will be performed at INFN-Legnaro on a specific test bench
including a coupling cavity. The manufacturing of the other couplers will start just after
approval of the acceptance tests [26].

Figure 10. First RFQ module completed (Module 16)

The final acceptance of the entire RFQ will be performed during summer 2014; the final
delivery to Rokkasho will take place in October 2014.
2.1.3 The Medium Energy Beam Transport (MEBT)The main function of the MEBT [27] is to match efficiently the RFQ output beam profile to
the SRF input, transversally and longitudinally (see figure 11). The longitudinal forces areapplied to the beam by means of two RF resonant cavities. A 5-gap interdigital H-mode
configuration has been selected as a buncher cavity as the best compromise in terms of total
power dissipation, power density, and space occupied. The radial dimensions of the beam arecontrolled for injection into the SRF Linac by one quadrupole triplet and one quadrupole
doublet. The transverse position of the beam is corrected by the magnetic steerers integrated
into the quadrupoles. In order to cut the beam edges and to determine beam losses, theunmatched particles coming from the RFQ are collected by two 4-axis movable metallic
plates, called scrapers, inserted between the magnets of the triplet. To achieve the vacuum
conditions required by the proximity of the RFQ and Superconducting Radiofrequency Linac,
a pumping system in the range of 103 l/s for H2 will be installed at the vacuum ports of thebunchers.

10

Figure 11. Layout of the MEBT line

The detailed design activities of the main components have been accomplished:- the magnets have been designed and the first unit was validated on a magnetic test
bench in July 2012 ,- the beam halo and out-of-energy particles coming from the RFQ are stopped in two
movable scrapers, designed for a maximum 500 W beam power deposition. It has been
designed for easier maintenance and the manufacturing has started for a test which
will be done by the end of 2012,- the bunchers, currently in the detailed design phase, are under study with particularattention to the cooling system, the objective being to comply with the main
requirements with an accelerating voltage of 350 kV and a total power of 6.6 kW to bedissipated. A first prototype with aluminum stems for low-power tests is expected
before the end of 2012 and the first complete buncher for high-power tests is expectedby the beginning of 2013.
In mid-2013 the MEBT will be available for a performance and integration test.
2.1.4 The Superconducting Radio Frequency LINAC (SRF Linac)
The high-energy section of LIPAc accelerates the beam to 9 MeV and consists of the first of
the four cryomodules of the IFMIF SRF Linac, housing eight superconducting 175 MHz halfwave resonators (HWR) and eight superconducting solenoid packages [28]. The main cavity
and magnet parameters are listed in Table II.
TABLE II: MAIN PARAMETERS OF CAVITY AND SOLENOID

Frequency
Cavity 
Accelerating field Eacc
Quality factor Qo
Max. forward Power / coupler
Max. Tuning range
Beam aperture cavity/solenoid
Magnetic field Bz on axis
Field at cavity flange

175
0.094
4.5
1.4 109
200
±50
40/50
6
≤20

MHz
MV/m
kW
kHz
Mm
T
mT

11

Two prototypical resonant cavities have been fabricated. The original design of the tuner
relied on a capacitive plunger with a large membrane to allow an elastic deformation of±1 mm. Tests at cryogenic temperature showed a low Qo, as well as a quench at low field,
pointing to a suspect NbTi plunger [29]. New tests performed removing the plunger haveconfirmed the validity of the cavity design (see figure 12).

Figure 12. P02 Half way resonator qualified

As a result, a new design based on a conventional compression tuner principle is underdevelopment which leads to a lengthening of the cryomodule to ease the integration of themechanical tuning mechanism between the HWR tank and the solenoid package.
The RF coupler [30] is composed of a water-cooled Cu antenna, a disk ceramic window, an
external conductor made of helium cooled double wall tube and a tee transition between the
input coaxial line and the coupler. Two prototype couplers have been fabricated and will betested on a specific test bench when the 200 kW RF source will be available, planned at the
beginning of 2013. The beam focussing and orbit corrections are performed by 8 sets ofsuperconducting solenoids/steerers and beam position monitors, located before each HWR.
During the cold tests at 4.2K performed in a vertical cryostat, the theoretical critical current of
the magnet was reached (at about 260 A, well above the nominal current of 210 A) with avery short training [31]. The design of the cryomodule, including the magnetic shielding toprotect the HWR from the earth magnetic field, two independent 4.5K helium circuits to cool
down the cavities and the magnets, a helium phase separator and a thermal shield cooled at
60K by gaseous He, is now almost completed.
2.1.5 The High Energy Beam Transport lines (HEBT) and the Beam Dump
The HEBT line transports the beam from the Linac to the beam dump includes a Diagnostics
Plate for beam characterization, a bending magnet to reduce the neutron radiation from beam
dump towards upstream components, a magnetic beam expander to limit the power density on
the beam dump (< 200 kW/cm2), a lead shutter, closed during beam shutdown to act as a
gamma shield from the activated beam dump and a beam scraper to protect the last portion of
the vacuum pipe in front of the beam dump (see figure 13) [32].

12Figure 13. 3D mock-up of the HEBT line

A conical dump [33] made of copper has been designed to stop the 1.125 MW deuteron beam(see figure 14). It is cooled by a high velocity water flow that circulates through an annularchannel along the outer surface of the cone. Thermo-mechanical studies showed a highrobustness to beam errors, CW and pulsed mode operation, buckling and high velocity
coolant flow effects. A local shielding made of water tanks and polyethylene against neutrons
and iron blocks against gamma rays associated with an extra frontal shielding made of a 70
cm thick concrete wall to fulfil the radiological protection requirements: low dose rates
outside the accelerator vault during accelerator operation and manual maintenance inside
the accelerator vault possible during beam-off phases.

Figure 14. 3D view of the Beam Dump; inner cone installation and cooling tests

The HEBT and the Beam Dump are in the final stage of detailed design, and prototypes of thebeam dump cartridge have been built. Hydraulic tests of a 1:1 scale cartridge prototype areon-going. The manufacturing phase will start in autumn 2012 with the integration and test in
Europe in mid-2013. The delivery on site will be completed by mid-2014.
2.1.6 Beam instrumentation
Beam instrumentation consists of diagnostics aiming at monitoring and controlling all thenecessary beam characteristics along the accelerator (see figure 15), and thus are the basis for
its successful operation, right from the early beam commissioning phases up to routine
operation. Except for some specific devices, most of the beam diagnostics must therefore be13able to provide information for pulsed and continuous beams equally, withstanding minimum
to maximum beam current (power).

Figure 15. Beam Instrumentation along the LIPAc

A full set of non-intrusive diagnostics to monitor and to characterize the beam all along theaccelerator has been developed: current monitors of various types (AC and DC current
transformers, fast current transformer), 20 beam position monitors (8 of them at cryogenic
temperature), beam profile monitors (based on ionization and fluorescence of the residualgas), around 40 beam loss monitors (ion chamber Large Hadron Collider type), micro-loss
monitors (based on chemical vapour deposition) diamond operating at cryogenic
temperature), bunch length monitor (residual gas). For short chopped beams, interceptive
devices as secondary emission monitor grids and slits will be used for emittance and energy
spread measurement [34].
In addition, a Diagnostic plate (D-Plate) combines specific diagnostics to characterize thebeam during commissioning with beam, and will be located first at the exit of the RFQ and
MEBT during RFQ commissioning, and second at the exit of the SRF Linac during LIPAc
normal operation.
2.1.7 RF Power system
The RF Power System [35] is composed of 18 RF power generators to feed the 8 RFQ
couplers (200 kW), the 8 superconducting half wave resonators of the SRF Linac (105 kW)
and the 2 buncher cavities (16 kW). Except for the buncher cavities, which are fed by fullsolid-state amplifiers, the same topology has been chosen for all the power chains forstandardization and scale economy reasons: they use the same main components (solid-state
pre-driver and tetrodes for driver and final amplifier) which can be individually tuned toprovide different RF output powers up to 200 kW (see figure 16).

14

Figure 16. 3D view of the RF Chain 200 kW and 100 kW and Prototype RF module at Madrid
Integration facility

The first prototype 200 kW RF source will be ready by the end of 2012 and will be used forthe testing and conditioning of the HWR couplers while the first 2 x 100 kW RF module isexpected at the beginning of 2013. The 16 kW solid-state amplifier will be ready for the highpower tests of the buncher cavities at mid-2013.
2.1.8 Cryoplant
The production of liquid and gaseous helium needed for the SRF Linac cooling is performed
with industrial equipment using the well-known Claude refrigeration cycle.
The technical specifications have been completed in 2011 and manufacturing has started in2013.
2.1.9 Control System
The Control System [36] consists of six subsystems; Central Control System (CCS), Local
Area Network (LAN), Personnel Protection System (PPS), Machine Protection System(MPS), Timing System (TS) and Local Control System (LCS).
PPS aims at protecting the personnel against the radiation, the high beam power and other risk
factors. In particular, it manages the controlled areas access for radiation safety aspects, while
it provides permission/restriction orders for accelerator subsystem actions. After installationof the hardware (PLCs, central console, personnel key box, emergency stops, monitoring
cameras) in the building, the programming of the sequence is on going. The Timing System
has to include both operation modes (pulsed and cw modes). A TS test bench was developed
and was successfully tested on the Injector at CEA-Saclay. MPS controls the beam rapid stop
to minimize the beam loss and has to react to an interlock signal in less than 10 s. The MPS
modules have been completed and a test with the interlock circuit of the Injector is planned in
November 2012. The MPS logical functions with all subsystems of the accelartor are underprogress.
All accelerator subsystems include a LCS connected to the CCS which can work stand-alone
under Experimental Physics and Industrial Control System (EPICS) for monitoring andcontrolling the different subsystem equipment. The LCS development is well advanced for15most of the accelerator subsystems and the development of the Data Acquisition System(DAC), one of the important functions of CCS, is under progress.
All the designs and the definitions of the different structures are under review have been
finalized in 2013.
2.1.10 Building, Conventional Facilities and Integration on site
The building, erected in Rokkasho in 2009, consists of an accelerator vault, a nuclear heating,ventilation and air conditioning (HVAC) area, a heat exchange and cooling water area forboth radiation-controlled and non-controlled areas, an access room, a control room, and alarge hall for power racks, RF systems (HVPS and RF power chains) and the 4K refrigerator(see a photo in figure 17). The accelerator vault is surrounded by 1.5 m thick concrete walls
and ceiling.
The installation of the main auxiliaries has been completed, and the remaining components
will be provided at the same time as the installation of each sub-system.
All the accelerator system components will be fully or partially tested in Europe before theinstallation in Rokkasho. To handle the installation on site with all the stakeholders and theirrespective responsibilities, an integration activity has been set up at the Integrated Project
Team level to ensure coherence, and that all the requirements are fulfilled.

Figure 17. Accelerator building in Rokkasho

To ease this process different tools have been implemented such as a Plant Integration
Document (LIPAc PID), a baseline document of the project, an Interface Management System(IMS), defining and detailing all the interfaces between each sub-system, and a 3-dimensional
integration review process to insure the coherency of the integration on site.
2.2 Lithium Target Facility Validation Activities
The EVEDA tasks related to the Li target facility validation consist of 4 activities which
cover the construction and operation of a Li test loop including purification systems,
diagnostics for the Li target, erosion/corrosion tests of loop structure materials and remote16
handling aspects of the target assembly. The activities are jointly carried out by JAEA and
ENEA.
2.2.1 ELTL flow validation and purification systems
The EVEDA Lithium Test Loop (ELTL), physically almost equivalent to the loop in the
IFMIF Plant [12], has been built at Oarai and successfully commissioned in February 2011
with an “integral concept” target assembly manufactured in stainless steel (figure 18). The
design was carried out from March to December 2009 and the construction was completed by
November 2010. The loop consists of three floors with a total height of approximately 20 mfrom the ground level and a pit in which the dump tank is placed. A simplified piping andinstrumentations diagram (P&ID) is shown in figure 19. The ELTL is composed of two major
branches which are the main loop with 6”/8” piping and the purification control loop with a1” piping. All piping is made of AISI 304 steel. The main loop contains the target assembly,
a quench tank, an electro-magnetic pump (EMP), an electro-magnetic flow meter (EMF), a Li
cooler and the dump tank. The tanks connect to Ar gas cylinders and turbo-molecular vacuum
pump units to control pressure and vacuum.

Figure 18. ELTL just commissioned in the JAEA premises in Oarai

17
The ELTL is able to generate a flow rate of 3000 l/min which will produces a flow velocity of
20 m/s in the target assembly. It can operate at Ar pressure and in a vacuum condition of 10-3
Pa [13].
The target assembly is installed at the 3rd floor inside of an air-tight vessel, which is filledwith Ar during operation. The target assembly is equipped with a double reducer nozzle and aconcavely curved open channel of 100 mm width (2.6 times reduced compared to IFMIF) togenerate a free surface Li jet of nominal 25 mm thickness like in IFMIF [37].
A Li flow at IFMIF nominal velocity of 15 m/s was achieved in the target assembly with an
Ar gas pressure of 0.12 MPa. In September 2012, the loop was back in operation after thedamage suffered at the time of Great East Japan earthquake. During this restoration work, thefirst test operation was conducted to gain critical information about the geometrical stabilityof the lithium flow and the performance of the flow guiding structure up to 20 m/s flow speed.

Figure 19. Layout of the ELTL (some traps and monitors are not yet installed)

The purification loop is connected to the main loop at the upstream and downstream of the
EMP. An impurity monitoring loop is branched at the downstream of the impurity traps in the
purification loop. The purification loop includes a cold trap that removes oxygen, and two
mechanical interfaces to install two hot traps to remove nitrogen and hydrogen respectively.
These two hot traps are designed and fabricated in collaboration with Japanese universities,
who qualify the getters in a separate task. These traps will be installed in the future. The N
content is considered particularly critical, since it has a strong impact on corrosion anderosion through the formation of Li ternary nitrides Li3CrN2. The trap must therefore reduce
the N content to values < 10 ppm, but the methodology followed; i.e. a getter made of pellets
of Fe doped with Ti, has currently still shown limitations.
The impurity monitoring loop includes a Li sampler to analyze impurity concentration in the
Li off-line, and interfaces to two on-line monitors, which will be installed in the future.
The dump tank is capable to store the 2.5 tons of Li that were melted from 1608 ingots. The
installation was particularly laborious in a purposed design glass-box to limit thecontamination by air and humidity (values below 25 ppm was ensured). Figure 20 shows theinterior of the glove box with some Li ingots sealed in plastic.

18

Figure 20. Glove box with Li ingots

2.2.2 Target diagnostics
The diagnostics for the free surface cross-flowing Li jet in the target assembly exposed tovacuum that will absorb the 10 MW beam power is of utmost relevance. The thickness andthe waviness of the jet must be controlled to ensure sufficient Li screen to absorb the beamenergy, which presents its peak for deuterons at 40 MeV at 19 mm. A contact probe has beendeveloped with a minute needle that does not generate visible turbulences that drops voltage
at contact with flowing Li. It has been successfully applied to measure jet thickness and wave
heights at the Li loop of the University of Osaka (figure 21) [37]. Its adaptation to the ELTL
is still to be proven and to the high radiation environment of IFMIF is still to be done.
A new optical method by means of time-of-flight of a laser beam has been developed andtested by Osaka University with a precision of 1 µm. Applicability at the ELTL has been
proven in preliminary tests.

19

Figure 21. Set up of the contact probe measurement in the Osaka Li loop

A thorough analytical assessment of the wave height distribution combined with CFD
modelling has managed to predict the pattern with Görtler vortices under Rayleigh-Taylor
instabilities. Wave amplitudes are inversely proportional to liquid Li speed and with 90% of
probability the nozzle will guarantee surface amplitudes within the 1 mm specified. Speed
influence in wave pattern can be observed in figure 22 from Osaka Li loop.

Figure 22. Flow pattern close to the nozzle at two velocities (Osaka Li loop). Amplitude is observed as
to be inversely proportional to Li liquid speed

2.2.3 Erosion/corrosion testing in LIFUS6
Dedicated corrosion/erosion tests for austenitic and RAFM steels were planned with theexisting LIFUS3 loop at ENEA-Brasimone but certain limitations to accomplish the expectedvalidation activities led to the construction of a new liquid Lithium test facility in 2010. The
new loop LIFUS6 (see plant layout in figure 23) is built with a simplified configuration fromthe hydraulic point of view and contains a cold trap operated continuously in a bypass stream
and a hot (nitrogen) trap based on Ti-sponge operated in batch [14]. The Li will flow underisothermal conditions at 350°C. The maximum velocity in the test section will be about 16

20
m/s. The impurities will be measured on-line by a resistivity meter developed by ENEA andUniversity of Nottingham; it relies on the linear variation of the metal resistivity at a given T
with the concentration of N anions, and by the chemical analysis of Li samples. A resistivity
meter will be sent to Oarai to be integrated in the ELTL.
The experimental program foresees up to 8000 hours of corrosion/erosion tests, which will
start in spring 2013.

Figure 23. Layout of the LIFUS6 loop in Brasimone (ENEA)

2.2.4 Remote handling validation
A dedicated orbital Laser welding machine has been developed by JAEA to remotely weld
and cut a lipseal flange. The process has been validated using a mock-up of the IFMIF inlet
pipe in collaboration with Osaka University. Figure 24 shows a welding trial. The flanges are
made of AISI 316L steel and the peripheral lips are 2+2 mm thick. A 16 kW fibre laser isused. Welding and cutting is done with a power of 5 kW beam power and a speed is 3m/min.
Welding quality is acceptable, but cutting still needs to be improved to avoid sticking of theflanges and proper weld geometry for re-welding the same lips. In addition, quality
procedures to be applied remotely need to be developed.
At ENEA, a target assembly mockup is under construction to simulate remote replacement ofa removable backplate based on the bayonet concept and detachment and reconnection offlanges fastened with a dedicated connection system developed at the institute. The tests will
simulate the geometrical constraints of the test cell using a manipulator system similar to thatplanned for IFMIF.

21

Figure 24. Weld trial with the orbital fiber laser system in Osaka University

2.3 Test Facility Validation Activities
The design and validation of the test facilities are predominantly conducted in the European
Home Team with the exception of the Small Specimens Test technique development carriedout under the coordination of Japanese Home Team. Design work of the test facilities isaccompanied by prototyping of the High Flux Test Module (HFTM) and internal rigs forpost-irradiation examination of miniature-size specimens of fusion reactor materials and online creep testing in the Medium Flux Test Module (CFTM). It is also making progress on thedesign and R&D of an alternative proposal of HFTM, potentially enabling irradiation undervery high temperatures, adequate for irradiation testing of SiC [16].
2.3.1 High Flux Test module
The irradiation of small specimens is planned at several blanket-relevant irradiation
temperatures and shall accumulate structural damage of up to 150 NRT dpa. The HFTM willallow the irradiation and the temperature control of the specimens by an active coolingsystem of He gas. The HFTM is mainly dedicated to the research on RAFM steels, to betested in the temperature range 250-550°C, with an option to provide irradiation up to 650°C.
The uncertainty of temperature for 80% of the specimen is demanded to be below +/-3%
related to the absolute nominal temperature. Further, it is an aim to cool the specimen fromtheir temperature to below 200°C to freeze the irradiation defects after the irradiation within
15 minutes. The arrangement of the specimens in the HFTM is adapted to the beam footprintof the neutron source, which is 20 cm x 5 cm. The specimen alignment, and the dimensioningof reflectors, must limit the neutron flux gradient to less than 10% of the individual sample
gage volume. In order to transmit the neutron flux with as little as possible losses to thespecimens, the HFTM structures need to be thin, and avoid materials with a high neutron
absorption cross section. A minimum of 26, but possibly up to 40 specimens per alloy, shouldbe accommodated for a single irradiation position. The structures of the HFTM might be
exposed to damage rates of up to 50-55dpa/fpy but are submitted to stresses [15].
The HFTM is built from a thin walled container divided into eight compartments, into which
three rigs can be placed in each (for a total of 24 rigs). The central four compartments (360cm³ for specimens) are inside the beam footprint where neutron flux levels are suitable for22high quality irradiation experiments. The remaining four out-of-center compartments are also
filled with rigs. The function of these so called companion rigs is mainly to act as lateralneutron reflectors, but also to accommodate instrumentation, like fission chambers for online
flux monitoring. In the two compartments located at the lateral ends most distant from thesource, the neutron flux amounts to only about 10% of the central positions, but flux
gradients are low, and can thus be attractive as additional irradiation space.
The specimens are contained in rectangular irradiation capsules (external dimensions 120
mm x 46.7 mm x 13.4 mm) equipped with electrical heaters, which can partly compensate thespatial distribution as well as temporal fluctuations of the nuclear heat release. In order tohomogenize the temperature field, gaps between the specimens are to be filled up with liquid
NaK-78 eutectic alloy (see figure 25). The capsules are encased inside irradiation rigs, which
incorporate neutron reflectors on the upper and the lower end. In order to guarantee thesevere temperature gradient allowed, gaps between encapsuled specimens are filled up withliquid NaK-78 eutectic alloy. The capsules are encased inside irradiation rigs, which
incorporate neutron reflectors on the upper and the lower end. A helium gas flows between
the capsule surface and the rig functions as the main thermal resistance between the specimen
and the heat sink with a maximum gap of 1.35mm depending of the capsule target
temperature level (250-650°C). In turn, the irradiation temperature is measured and controlled
thanks to various (between 3 and 6) type-K thermocouples located inside the specimen stack.
The thermocouple readings will be the input to the control of the capsule’s electric heaters. In
the current design, the thermocouples are directly immersed in the NaK of the specimen
stack.

Figure 25. HFTM 3D model and final constructed under tests. On the right, capsules filled withNaK

The capsules will be tested under irradiation conditions realized in the Belgian BR2
research reactor [17]. This irradiation will provide nuclear heating of approximately 3W/g asin the HFTM, but obviously considerably lower total doses than anticipated for IFMIF endof-life can be accumulated in this campaign. Main objectives are the test of the heaters andthe capsule temperature control, but also the recovery of the specimens after irradiation under23
hot cell conditions. Such experience will be most valuable for the planning of the IFMIF hot
cells and related logistics and workflow optimization.
The last step of validation will be the testing of a 1:1 prototype HFTM will be installed in
the HELOKA-LP helium loop facility at KIT (see figure 26), where it will be operated under
IFMIF design operation conditions, in what regards mass flow (up to 120 g/s), gas pressure(0.3 MPa) gas temperature and electrical heating of the capsules [18]. The test objectives
include the verification of the temperature control strategy, assessment of flow induced
dynamic loads on the rigs, the attachment structure and the helium pipes, and the definition ofoperational modes (startup/shutdown, emergency stops, cooldown transients etc.)

Figure 26. HELOKA-Li loop facility at KIT (Karlsruhe)

2.3.2 Medium Flux Test Module or Creep Fatigue Test Module
The purpose of the Creep Fatigue Test Module (CFTM) in IFMIF is to perform creep fatigue
experiments under intense neutron irradiation [19]. The CFTM consists of three parallel
testing machines, mounted on a frame, which is operated independently. It will be installed in
the medium flux area of the test cell and will be exposed to intense radiation fields, including
both neutron and gamma fields. The heat absorbed by the different parts of the module will be
extracted by means of a He gas passing through independent cooling channels. Measures tolearn the temperature and control it in the specimen under testing to ensure that the target
values are respected will be also included.
The testing machine load cells and extensometers have been designed to withstand the hard
operation conditions of irradiation and temperature.
The final CFTM will consist of three parallel load controlled single testing machines (STM),
mounted on a frame. The three testing machines will operate independently with +/-12.5 kN
load with controlled speed ranging between 1 µm/s and 80 µm/s (see figure 27). The results
obtained for a STM are conferrable to the second and third STMs. Finally, the complete
CFTM will be installed in the medium flux area of IFMIF test cell and will be exposed tointense radiation fields, including both neutron and gamma fields. The heat absorbed by thedifferent parts of the module will be extracted by means of a helium gas (coolant) passing
through independent cooling channels. Elements required to control the specimen
temperature at the targeted value will be included. The first tests have been performed
without radiation and heating effects.

24

actuator

specimen

frame

Load
cell

Figure 27. CFTM 3D model and final constructed equipment

2.3.3 Small Specimen Test Technique
Due to the limited irradiation volume available in the test modules, small specimen test
technique (SSTT) is being developed under IFMIF/EVEDA frame by various Japanese
universities (College of Hachinohe, Kyoto University and Tohoku University) and institutions(NIFS) under the coordination of JAEA [38]. The understanding fracture mechanics ofirradiated specimens as well as fatigue behavior in the irradiated materials of the first wall in
the fusion reactor vessel is essential.
Tests have been carried out with specimens fabricated with the RAFM F82H. The reduction
in size from standard size specimens has been demonstrated achievable for some types.

Figure 28. Small specimens devised for fusion materials testing25

Two types of fatigue specimens were tested with a perfect match for the round bar type in therange of interest as shown in figure 29. Further tests are needed to understand a slightdeviation from the expected hysteresis behaviour.

Figure 29. Fatigue testing comparison of standard specimen with two types of small specimens

Transition fracture toughness has been measured with ¼CT-specimens aiming at thedefinition of Master Curve (MC) following ASTM E1921 ‘Determination of Reference
Temperature, To, for Ferritic Steels in the Transition Range’. Results indicate that thecorrelation developed for ferritic steels cannot be exactly applied (see figure 30). A new
correlation has been proposed, but further tests are needed to statistically secure it. The
impact of cold work on toughness to simulate irradiation effects has been investigated for
F82H. Whereas standard Charpy specimens correlate well, it has been shown that CTspecimens do not follow that trend and it cannot replace the impact of irradiation at the
spectrum and flux to be expected in a fusion power plant. It is to be noted that Charpy tests
for minituarized specimens is already covered by ASTM E1253 ‘Reconstitution of IrradiatedCharpy-Sized Specimens’.

Figure 30. Fracture toughness measured following ASTM 1921 fitting with the Master Curve for standard
specimens

26
The crack growth rate through environmental assisted cracking and stress corrosion cracking,well known effects in austenitic steels for fission reactors, has been assessed for RAFM by
Hachinohe College with no significant difference observed with the data accumulated withaustenitic steels.
2.3.4 Fission chamber
Fission chambers (FC) will give information (on-line) on the Test Cell irradiation conditions.
Although these detectors are commonly used in power plants, the detector functioning in theharsh environment of the Test Cell must be proved. Therefore, validation experiments had tobe performed under conditions as close as possible to the IFMIF ones.

Figure 31. Prototype of the fission chamber, model CFUR43/C5B-U8.

During 2008 two prototypes (one FC and one ionization chamber) were acquired. For
studying the FC behavior in an environment free of neutrons, they were tested in an X-rays
and in a 60Co irradiation facilities at CIEMAT. After these preliminary tests the detectors
were sent to the BR2 reactor (SCK·CEN) for monitoring fast neutron fluxes. The integrated
gamma absorbed dose was about 4x1010 Gy and the fast neutron fluence (E > 0.1 MeV)
4x1020 n/cm2. Figure 32 shows the comparison between calculated values and experimental
data in three BR2 different channels [39]. Fission rates were calculated with ACAB code,
while the final FC current was calculated through a numerical code developed at CIEMAT.

27
Figure 32. Purely neutron-induced signal of the FC after gamma subtraction (points) and comparison withtheoretical calculation (solid line). The numbers above the data indicate different BR2 irradiation channels, fromref [39].

New prototypes have been acquired and will be included in the new BR2 irradiation [17],with the main objective of demonstrating the detectors robustness under an intense neutron
flux. Validation of theoretical calculations will be also possible.
3. Conclusions
The world fusion programme needs neutron sources adapted to its own physical requirements.
ITER and NIF will teach us how to control deuterium-tritium nuclear fusion reactions underelectromagnetic and inertial confinement, however the mechanical properties that essentialbuilding bricks will show after few years of operation of a fusion power plant remain
unknown. Licensing of a fusion reactor will not be possible without an understanding of thedegradation during operation of the materials of its vessel directly exposed to the nuclear
reactions. The successful development of nuclear fission power plants in the 50s demanded aparallel intense materials research over decades to understand the impact of fission neutronsin structural materials [40]. Present maturity of materials science and modern computation
techniques can guarantee a thorough understanding of the behaviour once relevant data isavailable; unfortunately the spectrum and flux of either existing or planned fission or
spallation neutron sources cannot disclose the unknowns. The transmutation energy thresholdfor p+ and α-particles generation goes beyond typical fission neutrons energy including fast
breeder reactors; in turn, spallation sources present wide neutron spectra with long tails
reaching one order of magnitude higher energy than fusion neutrons (with the generation of
typically one order of magnitude more appm/dpa of He leading to a significantly more severe
embrittlement). Furthermore, direct extrapolation of the mechanical degradation underirradiation from a FCC crystal structure of austenitic steels to the ferritic BCC is not possible.
Fusion relevant data at 30 dpa is needed to meet nuclear fusion roadmaps [41]. IFMIF will
generate neutrons with a broad peak at 14 MeV at a flux of 1018 /m·s2 that will allow
materials testing at equivalent conditions of those in a fusion power plant. The impact oftemperature while irradiation takes place in the detrimental lattice void swelling (observed for
ferritic-martensitic steels from 20 NRT dpa) is known; the High Flux Test Module (undervalidation in Karlsruhe) present 24 independently cooled capsules that will allow the tuningof the optimal operational conditions of a power plant. Furthermore, the small specimens
technique is mature; it will provide an understanding of macroscopical properties. Its
standardization would be of global benefit. The fusion materials programme demands joining
forces, unravelling the physics through suitable testing will validate and tune existingneutronics models and will allow the design of radiation harder low activating materials, withan enormous impact on fusion power plant operational life. Moving towards electricity
production demands materials science, in parallel with alternative facilities targeting to tamenuclear fusion reactions, to play a key role in the world fusion programme endeavours. Suitedmaterial testing experimental facilities are indispensable; IFMIF is.
Acknowledgement
The authors wished to thank all the members of the Integrated Project Team (Project Team in
Rokkasho, JA Home Team in Tokai and Rokkasho and the EU Home Team at Garching) andat the various Research Centers of the European Countries being Voluntary Contributors to
IFMIF/EVEDA and Japanese Universities and research centers.

28This paper has been prepared within the framework of the BA Agreement between Japan and
EURATOM.
The views and opinions expressed herein do not necessarily reflect those of CIEMAT, ENEA,
F4E, JAEA or KIT.

29

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