1. Physics under CoA

1
Composition of EURATOM/IPP.CR

• 1. Physics under CoA EFDA
• Inst. of Plasma Physics, Academy of Sciences of
  the Czech Republic
• Tokamak COMPASS moderate involvement in
  practically all TFs,TGs
• incl. TG Materials - WW alloys JET KIT on
  Inertial Fusion (PALS)
• Faculty of Mathematics and Physics, Charles
  University
• probes education
• Faculty of Nuclear Science and Physical
  Engineering, Czech Technical Uni.
• plasma simulations education (MC Physics and
  Technology of Nuclear Fusion)
• Institute of Physics of Materials, Acad. Sci. CR,
  Brno
• ODS Ferritic Steel properties
• J. Heyrovsky Inst. of Physical Chemistry, Acad.
  Sci. CR
• PWI TF - characteristics of small molecules
  and atoms at low energies

2
Composition of EURATOM/IPP.CR

• 2. Technology (old EFDA ? F4E)
• Nuclear Research Institute, plc., Rež
• -gt Research Center Rež, Ltd.
• ITER TBM and much more
• Institute of Applied Mechanics Ltd., Brno
• numerical simulations - welding of large
  structures
• Nuclear Physics Institute, Acad. Sci. CR, Rež
• Nuclear Data for IFMIF
• -------
• Not formally members of association industrial
  suppliers (ATEKO, CKD Energo, Skoda

3
Compass Tokamak
MAIN FEATURES Small size tokamak with ITER
relevant geometry - single-null-divertor Equippe
d with a set of saddle coils for the resonant
magnetic perturbation (n2). Two Neutral Beams
for either co-injection or balanced injection New
comprehensive set of diagnostics focused on the
edge plasma
STATUS Project started 2006, first political
plasma December 2008 Successful welding of new
ports for NBI systems Cleaning of all graphite
tiles and the vacuum vessel performed Final
commissioning of NBI systems, Fast Feedback,
Hydraulic Preload, Commissioning of advanced
diagnostic systems (HRTS, Li beam, etc.). Full
operation is planned to start in June 2011
ITER-like geometry (110)
4
Compass Status

• Vacuum chamber as good as new

Lithium Beam
NBI SYSTEM
5
Compass Diagnostics

• Magnetic diagnostics (illustrated-gt)
• Multi-channel tools for tomography in different
  spectral ranges (visible, soft-X and bolometric
  measurements)
• Hard X-ray Monitoring
• Fast Visible Camera System (450-116000 fps)
• High Resolution Thomson Scattering (2x NdYAG
  30Hz 1.5J)
• Neutral Particle Analyser
• Divertor probes (39x)
• Reciprocating Probes (2x)
• Beam Emission Spectroscopy
• Atomic Beam Probe
• Microwave reflectometry system

High Resolution Thomson Scattering
6
Compass Work Plan

• Scientific programme
• H-mode studies
• Pedestal physics studies, data for scalings
• ELM mitigation using RMP
• Long-range correlations studies
• Advanced probe development
• E.g. probes for measurement of important
  quantities in edge plasma and SOL (ion
  temperature, plasma potential, etc.)
• Advanced training
• Traditional international school in tokamak
  operation and experimental plasma physics (SUMmer
  TRAIning Course)
• Two runs of SUMTRAIC per year planned as of
  2012
• Recognized by FUSENET as optimum advanced
  training facility
• Erasmus Mundus, Workplace for preparation of
  PhD theses,

7
F4E, PPPT, ITER IO

• 2. Technology

8
Research Center Rež, Ltd.

• - Member of TBM Consortium
• - Operates LVR-15 research reactor
• Subject to EC notification, RCR will launch
  SUSEN project (SUStainable ENergy) for
  development of new materials and technologies
  primarily for GEN III, GEN IV but also Fusion
  (100 M of EU structural funds)
• RCR tests both in-pile and out-of-pile VV
  components for long-run cyclic thermal fatigue
  loads

Beryllium coated Primary First Wall qualification
mock-ups were tested up to 0.625 MW/m2 and 0.6
dpa Plan to respond to F4E call for tender
for HIGH HEAT FLUX TESTING OF BERYLLIUM COATED
FIRST WALL PANELS
9
Research Center Rež, Ltd.
RCR Future Programme PFW In-pile and
out-of-pile high heat flux testing, life-time
testing of PFW mock-ups Radiolysis, corrosion,
and chemistry in-pile investigation of coolant
medium Investigation of HIP joint under
irradiation conditions TBM PbLi in-pile tritium
transportation modeling, Tritium permeation
model Development and testing of anticorrosion
and tritium antipermeation layers Development of
Auxiliary Equipment Unit and Tritium Extraction
Unit detailed design Cooling medium corrosion
investigation Tritium retention devices Design,
development and investigation of Cold Trap
performance. Possibly supply of some of these
components . Facilities LVR-15 fission
reactor for research with various loops and
rigs RVS3 Reactor Water Loop, SCWL
Supercritical Water Loop, HTHL High Temperature
Helium Loop, TW3 Irradiation rig for small PFW
mock-ups, MELILO Metal Liquid Loop, etc.
10
Institute of Applied Mechanics, Ltd.
EU Fusion Roadmap Garching 13-14 Apr 2011

• IAM develops and improves methodologies for
  prediction of big welded construction
  deformations
• All methods are verified by real experimental
  measurements
• more than 8 years of experience lead to solution
  of
• numerical welding analyses of whole VV
  fabrication

PS1
VMO
Small initial experiments
LMVMO
PS2
VVPSM
40sector of VV
11
Institute of Applied Mechanics, Ltd.
EU Fusion Roadmap Garching 13-14 Apr 2011
12
Nuclear Physics Institute
EU Fusion Roadmap Garching 13-14 Apr 2011
NPI Cyclotron-based Irradiation Facility for
obtaining and benchmarking nuclear data relevant
to the fusion technologies
the high-power neutron source with the
heavy-water target simulates the neutron spectrum
of IFMIF
13
Nuclear Physics Institute
EU Fusion Roadmap Garching 13-14 Apr 2011
NPI Cyclotron-based irradiation facility Future
program
? measurement of neutron activation cross
sections in particular for the
validation of the neutron activation properties
of EUROFER steel components for
fusion technologies (ITER, IFMIF)
and the development and tests of neutron flux
monitors for IFMIF ? activation measurement of
IFMIF accelerator components ? the fast-neutron
response tests of various mock-up modules ?
neutron hardness tests of integrated electronic
circuits
14
ATEKO Ltd. Turbo Circulators
EU Fusion Roadmap Garching 13-14 Apr 2011
ATEKO a.s. Hradec Kralove (never a member of
Association IPP.CR)
developed and delivered (in 2010) 2 1 pcs. of
Helium TurboCirculators (TC) for cooling
testing of the TBM / TDM modules. Basic
parameters of the helium TC Inlet/Outlet pressure
MPa 8 / 10.14 Flow-rate kg/s 1
/ 1.4 Impeller diameter mm 185 Speed
rpm 40 000 Power kW
232 Active magnetic bearings
TC No.02 HELOKA
TC No.01 HeFUS
TC CEA