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2014 IGORR 2014 / IAEA Technical Meeting
Enhanced utilization of Zero Power Reactors
and Subcritical Assemblies
Bariloche, Argentina
17 - 21 November 2014
Centrum výzkumu Řež s.r.o.
Radek Řezáč
Research Centre Rez in brief
Established 2002, daughter company of ÚJV, R&D organization
Member of ÚJV Group
Particularly focused at nuclear power generation
7
LR-0 research reactor
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REACTOR
Reactor type Light-water, zero-power,
pool-type
Maximal thermal output (kW) Up to 1
Fuel type VVER-1000, VVER-440
Moderator Light water
Core
Assembly grid triangular
Diameter of the fuel pellet UO2 (mm) 7,15
Height of fuel column in pins (mm) 1250
Pitch of the fuel cells (mm) 12,7
Cladding material Zr + 1% Nb
Dimension of pin cladding (mm) diameter 9,15x0,72
Number of fuel assemblies 7 – 55
Number of fuel pins in VVER-1000 assembly 312
Assembly pitch for VVER-1000 236 mm
Number of fuel pins in VVER-440 assembly 126
Assembly pitch for VVER- 440 147 mm
Moderator
Chemical composition Demineralized water
with H3BO3
Concentration of H3BO3 (g/kg) 0 – 12
Change of concentration during operation n/a
Safety and experimental clusters
Number of absorbing elements in cluster up to 18
Layout in fuel assembly Standard circle
Regular triangular
Absorbing material B4C
Dimension of absorbing tube (mm) diameter 8,2x0,6
LR-0 reactor variability
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Concrete biological
shielding
Reactor Pressure
Vessel Model
LR-0 Al tank
Displacer
Barrel
Baffle
Measurement
dry channels
Fuel Assemblies
with different 235U
enrichment
Moderator
(demi-water, H3BO3)
MCNP model in scale 1:1 to study
of VVER-1000 physical parameters
Driving core with 7 Fuel Assemblies
Activity on LR-0 reactor
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Activity Description
Research Space-time kinetic for assembly of benchmarks
Measurement of neutron flux distribution
Experiments with new fuel assembly
Capacity for ideas Offering access to reactor LR-0
Providing 6 weeks of operating time in year (free of charge)
Aassessment of the applicant’s project
Student’s thesis Offering diploma and PhD thesis
Cooperation with Czech Universities
Providing facility for bachelor’s and master’s theses
Education &
Training
Technical visits
Courses and summer schools
Long term fellowships
Generation IV Forum: 6 systems
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Sodium cooled Fast Reactor
Molten Salt Reactor
Gas cooled Fast Reactor Lead cooled Fast Reactor
Supercritical Water cooled Reactor Very High Temperature Reactor
Parameters and use
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Reactor Neutrons Fuel cycle Dimension Application R&D
GFR fast closed middle
electricity,
actinide
recycling, H2
fuel, materials,
safety
LFR fast closed
small
middle
large
electricity,
actinide
recycling, H2
fuel, structural
materials
compatibility
MSR thermal closed large actinide
recycling, H2
fuel, materials,
safety, reliability
SFR fast closed middle
large
electricity,
actinide
recycling
Improvement of
recycling,
passive safety,
limit states
SCWR thermal
fast
open
closed large electricity
High-
temperature
materials,
composites,
ceramics
VHTR thermal open middle
electricity,
H2, waste
heat
fuel, materials,
hydrogen
production
Main parameters of GIV reactors
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Parameter SFR GFR LFR VHTR SCWR MSR
Coolant
liquid Na He, 7 MPa Pb alloys He, 7 MPa
water
24 MPa Molten salts
Core structure
F/M steels
Cladding
AFMA
F/M ODS
SiCf-SiC
composite
F/M steels
Austenitics
316, 15-15Ti
ODS
core
Graphite
Control rods
C/C SiC/SiC
Ni based
Alloys &
F/M steels
Graphite
Hastelloy
Temperature
(°C) 390-700 600-1,200 350-480 600-1,600 350-620 700-800
Dose Cladding
200 dpa 60/90 dpa
Cladding
~100 dpa 7/25 dpa
Other
components
IHX, turbine
Ni alloys
IHX, turbine
Ni alloys
Driving reactor cores assembled at LR-0
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A) Core arrangement for well-defined reactor neutron spectra.
B) Core arrangement for thermal neutron spectra modified by
graphite.
C) Core arrangement for modified – fast neutron spectra,
CC - Central Channel = hexagonal assembly
CVR activities in Gen-IV - SUSEN
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Technology Projects Status
SFR Possible
involvement Currently none
GFR
SUSEN
GoFastR
ALLEGRO
TEO, MAT,
SSD
LFR
SUSEN
MATTER,
MATISSE,
GAČR,
ARCADIA
TEO, MAT,
SSD
VHTR SUSEN
ARCHER TEO, MAT
SCWR SUSEN
CWR-FQT
Coordination
of EU – China
TEO, MAT,
SSD
MSR SUSEN TEO, NFC
TEO - Technological Experimental Loops
SSD - Structural and System Diagnostics
NFC - Nuclear Fuel Cycle
MAT - Material Research
SUSEN – SUStainable ENergy
To create a robust infrastructure for
sustainable R&D activities to support
Czech participation on European effort
for safe and efficient energy generation
in Europe in the 21st century,
particularly in terms of preparation of
Gen IV and fusion and
for safe operation of Gen III and Gen II
SUSEN – program list 1
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Program Description
Experimental SCWR
Loop
Experimental circuit with fluid – water at supercritical parameters (pressure 25 MPa, temperature
550 ° C), for testing of cladding materials and other components and materials subjected to very
high temperature steam.
Experimental Helium
Loop
Experimental circuit with high helium for material testing of reactor components exposed to
helium at temperatures up to 1000 °C. The experimental circuit will also exposure to radiation and
mechanical stress.
Experimental CO2
Loop
Experimental loop with supercritical carbon dioxide. The main aim of this facility is to verify the
conversion cycle and identify correlations for heat transfer and supercritical CO2.
ITER Facility Infrastructure for experimental verification and development of the new procedures for remote
handling for installation, repair and maintenance of systems.
14MeV Neutron
Source
Source will be used to study the interaction of neutrons (with energies of 14MeV) with materials
especially for fusion applications.
Laboratory of
Electron Microscopy
Modern fully equipped laboratory for transmission (TEM) and scanning (SEM) electron
microscopy. The microscopes will be equipped EDX, WDX and EBSD detectors.
NDE Laboratory
Comprehensively equipped laboratory for the development of new methods of non-destructive
testing of ferritic, austenitic and heterogeneous welded joints. The laboratory offers the possibility
to create a body with artificial discontinuities in order to study the degradation process.
SUSEN – program list 2
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Program Description
LOCA Chamber Device for simulation of an accident LOCA (loss of coolant accident). LOCA type device will be
mainly used for testing cables.
Hot Cells Complex
New complex of 10 hot cells. Cells will be equipped with a set of equipments for carrying out
mechanical tests (sample preparation area, stress testing machine, impact tester, etc.) as well as
to study material microstructure (optical microscope, SEM, etc.).
FERDA 2
Technological Line The experimental equipment for testing the fractional distillation of fluoride.
Cold Crucible Devices Equipment for thermal treatment of materials that are very difficult to treat be standard
procedures or non-standard radioactive materials.
SIMS Laboratory Laboratory equipped with high-end secondary ion mass spectrometer will be used primarily for
accurate detection of ultralow concentrations of substances.
Mechanical Testing
Laboratory
Comprehensively equipped laboratory for a wide range of material testing. The laboratory will be
equipped with a sample preparatory devices, testing machine for low and high-cycle fatigue,
stress testing machines, spectrometers, SEM etc.
Welding Laboratory
(in Pilsen)
Laboratory for studying of procedures for welding of advanced materials for use in the energy
industry. The laboratory infrastructure will be part of the SUSE project partner – University of
West Bohemia in Pilsen.
Education & training concept
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Gamma
Spectroscopy
Reactor
Physics
Neutron
Spectroscopy
Nuclear
Safety
Nuclear
Physics
Basic
Courses
Advanced
Courses
Tailor-made
Courses
Educational modules
Local
Training
e-learning
Distance
Teaching
Training types
Training forms
Th
eo
ry
Pra
cti
ce
Experiments related to education on LR-0
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A. Reactor Basic critical experiment
The determination of the exact critical moderator level
Calibration of the cluster by water level of the moderator
Measurement of the influence of dynamic cluster changes to
reactivity
B. Gamma spectrometry Energy and efficiency calibration of spectrometric equipment for
activation foils measurements
Measurement of the residual activity of radionuclides in several
axial positions of the fuel pin by means of gamma-scanning device
C. Reactor power monitors Measurement of neutron flux
Measurement of differential and counting characteristics of
neutron detectors
Training’s topics of advanced courses
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Reactor Physics on LR-0
Nuclear Reactor and safety operation
The Pin Power Distribution Measurement on the LR-0 Research Reactor
The Neutron Fluence Determination in LR-0 Reactor by Activation Detectors
Semiconductor Gamma-Ray Spectrometry and Its Experimental Reactor Physics Application
Environmental Radioactivity
Experimental Verification of Nuclear Safety During NPP Temelín Commissioning
Course schedule in 2014
26
January
Reactor Physics Reactor Physics Reactor Physics Summer school
in Reactor Physics
Gamma
Spectrometry
Gamma
Spectrometry
Environmental
Radioactivity
Environmental
Radioactivity
NPP Commissioning Nuclear reactor
safety
December 2014