Table 3 - Nucleus

TABLE 2.
Country
Research
reactor
Scheduled
and planned
life- time
Operation
cycle
Argentina
RA-10
(planned)
Argentinean
multipurpose
reactor
PLANNED RESEARCH REACTORS. OVERVIEW OF FUTURE CAPACITIES FOR MATERIAL TESTING RESEARCH
Power
Type
Fuel
Coolant
Moderator
Reflector
30 MW
Open-pool
Square array
with 19
MTR LEU
fuel
assemblies
Light water
as coolant
and
moderator
Heavy water
reflector
Irradiation
positions:
– number
– height
– diameter
Flux, (ncm-2s-1):
– total flux
– fast flux (≥0.1
MeV)
Estimated dpa/year
in steel
6 in-core
irradiation channels
Ø 5–8 cm
12–65 cm long
Total flux: ≤ 6  1014
ncm-2s-1
fast flux (max):
≤5×1014 ncm-2s-1
8 dpa/year
Test configuration
Test environment
temperature and pressure
range
Loop facility for testing
PHWR and PWR fuels,
linear power 500 W/cm
and a maximum heat flux
of 130 W/cm2 in steady
state conditions (3 rods)
and 600 W/cm and 150
W/cm2 in ramp
conditions (1 rod)
Temperature 320ºC (max.)
Pressure 15bar (max.)
Instrumentation
and control
(in-pile temperature,
pressure,
fission gas monitoring,
stress strain, etc.)
Auxiliary
facilities
(beams,
neutron
activation
analysis,
gamma-ray,
etc.)
On-site PIE
capabilities
(hot cells,
glove boxes,
tools for
stress analysis,
etc.)
In pile temp, pressure,
stress, strain
Pneumatic
system for
NAA and long
irradiation
capsules, cold
source and
beams guides
(cold and
thermal),
Isotope
production,
neutron
transmutation
doping (NTD)
Hot cell for fresh
and irradiated
experimental
material in-pool
neutron radiography
facility for
irradiated devices
inspection
Design,
manufacturing,
disposition,
shipping,
waste handling
and other
capabilities
Method
of access
and
degree of
utilization
Miscellaneous
and readiness
for material
testing
research
(MTR)
MYRRHA
Planned to
be
operational
by 2024
65–100 MW
ADS system
capable of
operating in
critical mode
Max 35 wt%
enriched
MOX fuel
Pb-Bi
eutectic
(LBE)
coolant
2 layers
dummy FA
(LBE and
YZrO)
6+1 instrumented
In-pile-sections
(IPS) positions,
21 additional
Test configuration is IPS
positions for inserts
design dependent
from top available
Sample surface
Core height 600 mm,
temperature range
irradiation space:
100–650°C
hexagonal, ID
ΔT
over
sample < 30°C
101.5 mm
IPS
coolant
possibilities:
Total flux
inert
gas
(He, Ar,
15
-2
1
10 ncm sCO2…), water, liquid
Fast flux (>0.75
metal (LBE, Pb, Na)
MeV) 4.2  1014
Possibilities
for material
ncm-2s-1
testing, fuel tests,
dpa/year: 23 in IPS,
instrumentation tests, etc.
up to 30dpa/year
below target zone
in ADS mode
Instrumentation &
control is IPS dependent
On-site hot cells
available
On site PIE facilities
IPS design
group and IPS
manufacturing/
assembly inhouse
Waste handling
& shipping
possible
Via
MYRRHA
consortium
Commercial
access
Scientific
merit (via
PAC)
Primary
mission:
demonstration
No paper
TABLE 2 (cont).
PLANNED RESEARCH REACTORS. OVERVIEW OF FUTURE CAPACITIES FOR MATERIAL TESTING RESEARCH
Irradiation
positions:
Power
– number
Type
– height
Test configuration
Fuel
– diameter
Test environment
Coolant
Flux, (ncm-2s-1):
temperature and pressure
Moderator
– total flux
range
Reflector
– fast flux (≥0.1
MeV)
Estimated dpa/year
in steel
Irradiation position,
thermal neutron
(<0.621 eV),
Epithermal
(0.625 eV–821 keV),
Fast neutron
30 MW (Th)
(>821keV)
Open pool
Materials irradiation
In-core water hole,
type
facility planned:
6.7 × 1014,
Plate type
temperatures up to
14
3.4 × 10 ,
U3Si2, 19.75
10000C
1.8 × 1014
India
%
Planned
In-core peripheral
enrichment
HFRR
200°C–450°C with inert
water
holes,
(LEU)
gas environment such as
4.4 × 1014,
Planned –
dispersed in
helium
14,
2.4
×
10
2022 start-up Al matrix
14
450°C–1000°C
with
1.3 × 10
12 cycles in with a clad of
molten
salt
environment
Irradiation holes in
a year, each Al-alloy
Fuel test loop facility:
D2O, 7 cm away
Coolant
and
25 days
temperatures up to 350C,
from
core
edge,
moderator
14
pressure 17.5 MPa
demineralised 3.7 × 1013,
6.0
×
10
,
Facility
for changing
water
1.2 × 1013
water chemistry
Heavy water
reflector tank Irradiation holes in
D2O, 20 cm away
from core edge,
2.9 × 1014,
5.0 × 1013,
1.7 × 1012
Country
Research
reactor
Scheduled
and planned
life- time
Operation
cycle
Instrumentation
and control
(in-pile temperature,
pressure,
fission gas monitoring,
stress strain, etc.)
Auxiliary
facilities
(beams,
neutron
activation
analysis,
gamma-ray,
etc.)
On-site PIE
capabilities
(hot cells,
glove boxes,
tools for
stress analysis,
etc.)
Design,
manufacturing,
disposition,
shipping,
waste handling
and other
capabilities
Temperature, pressure,
fluence
Six beam
tubes
NAA facility
NTD silicon
facility
Hot cells
Planned:
Necessary inhouse expertise
exists
Method
of access
and
degree of
utilization
Miscellaneous
and readiness
for material
testing
research
(MTR)
Material
irradiation
facility
planned
JULES
HOROWITZ
High
performances
material
testing reactor
100 MW
Light-water
reactor,
slightly
pressurized
core
U3Si2 Al
fuel (19.75%
or 27%)
10 cycle per
year
25 days cycle
20 irradiation
positions (about 10
for fuel experiments;
Experimental loops
10 for material
under developments
experiments)
allowing to represent
Fast flux
thermo hydraulic
(E > 0.1 MeV):
conditions of PWR,
5.5 E14 ncm-2s-1
BWR and WWER
(nominal, incidentalThermal flux
ramps and accidental
5.5 × 1014 ncm-2s-1
scenario – LOCA – are
Material ageing: up
considered)
to 16 dpa/year –
For
material
corrosion
max value in
loop to address
specific location
irradiated assisted stress
Diameter available
corrosion cracking
in the core: 30 mm
(IASCC)
(3 possibility to
Sodium loop under
80 mm)
feasibility for GENIV
Outside the core in
support
displacement
system (6 available)
flexibility
Many up to date
modern on-line
instrumentation to
measure: thermal and
fast neutron flux,
gamma heating,
elongation mono and biaxial, stress strain,
temperature,
pressure….
On-line fission gas
release analysis
Non-destructive
equipment to
perform X and
Gamma analysis
(tomography)
on fuel in the
reactor pool, in
the storage
pools and in hot
cells
No neutron
beam available
Non-destructive
analysis: X and
Gamma
measurement
(tomography) –
elongation via
LCDT…
4 hot cells to
perform first level
of PIE before
sending sample to
Cadarache Hot
Labs (or others)
Modern facility
with all support
activities such as:
design of new
experimental
device, transport,
waste
management
JHR is an
material
testing
research
steer and
Advanced
fund by an
Under
International
construction
Consortium
Plan to be in
(12 members
full operation
at the end of
by the end of
2013)
this decade
According to
Multi
purpose
the
with
primary
Consortium
mission –
agreement,
material
possibility for
testing
non-member
to have access
to JHR
experimental
capacity