New Developments in Fast Reactor Related Technologies at HZDR · New Developments in Fast Reactor...
Transcript of New Developments in Fast Reactor Related Technologies at HZDR · New Developments in Fast Reactor...
Text optional: Institutsname Prof. Dr. Hans Mustermann www.fzd.de Mitglied der Leibniz-Gemeinschaft
New Developments in Fast Reactor
Related Technologies at HZDR
B. Merk
Department Reactor Safety at
Institute of Resource Ecology
Helmholtz-Zentrum Dresden-Rossendorf
IAEA TWG-FR, Vienna, May 19-23, 2014
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Content
DYN3D developments
Cross section measurements
Liquid metal technologies
Enhanced feedback effects
Contribution to P&T Study
Molten salt reactor for P&T
Text optional: Institutsname Prof. Dr. Hans Mustermann www.fzd.de Mitglied der Leibniz-Gemeinschaft
DYN3D Develoments
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DYN3D distribution at national and international institutions
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Verification of XS generation and Steady State
Calculations
• 3D full core calculations (Example: 3600 MW Pu-MOX SFR)
– At beginning of life
• DYN3D and PARCS
– Diffusion solution
• Serpent:
– Reference solution
– Few-group XS for DYN3D and PARCS
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k-eff, Radial Power, and Safety Parameters • Δρ
– DYN3D vs. Serpent: 128 pcm
– PARCS vs. Serpent: 84 pcm
• Max. diff. in radial power
– DYN3D vs. Serpent: 0.56%
– PARCS vs. Serpent: 0.34%
Parameter Serpent,
pcm
DYN3D vs.
Serpent, pcm
PARCS vs.
Serpent, pcm
Doppler constant -852 -15 -15 Na void reactivity 1864 87 81 Total CR worth -6046 -127 -180
Acknowledements:
Eugene Shwageraus, Univ. of Cambridge
Konstantin Mikityuk, PSI
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Thermal hydraulics
Sodium thermal hydraulics is tested
Fuel rod model
coupling of DYN3D with TRANSURANUS in testing
Strategy for handling of axial fuel rod expansion in a nodal code is
developed, implementation has started
Validation on experiments
~ 24 pm in FREYA for validation for LFR, work is started
STC with IPPE for validation on BFS experiments has started
Developments for Transient Calculatons
Text optional: Institutsname Prof. Dr. Hans Mustermann www.fzd.de Mitglied der Leibniz-Gemeinschaft
Nuclear Data Measurements at the
Photoneutron Source nELBE
Liquid-Pb loop as neutron producing target
electron
beam
neutron
beam
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nELBE double time-of-flight experiment HZDR Dresden
incoming neutron time-of-flight: BaF2 and LaBr3 scintillators
scattered neutron time-of-flight: plastic scintillators
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nELBE neutron spectrum
Photoneutron spectrum (measured with a 235U fission chamber)
Photofission from bremsstrahlung and neutron induced fission can be measured.
similar to the neutron spectrum from fission
Neutron time of flight 100 ns – 2,5 µs
Neutron energy range from 100 keV – 7 MeV
235U fission chamber
Measurement time : 49.4 h Ie- = 15 μA, Ee- = 31 MeV
Flight path 618 cm
Absorption dips : 78,117, 355, 528, 722, 820 keV 208Pb scatttering resonances
Emission peaks: 40,89,179, 254, 314, 605 keV near threshold photoneutron emission
In 208Pb (strong capture resonances of 207Pb)
R. Beyer et al., NIM A723 (2013) 151
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Double time-of-flight measurement natFe(n,n‘)
-Fe-56 (1.,2.,3. Level)
(847, 2085, 2658 keV)
-Fe-54 (1. Level)
(1408 keV)
-Fe-56 (2 x 1. Level)
(1694 keV)
excited levels in Fe resolved by double time-of-flight method
Publications:
Neutron total cross section measurements of gold and tantalum at the nELBE photoneutron source⋆
Roland Hannaske, et al. Eur. Phys. J. A 49 (2013) 137
Characterization of the neutron beam at nELBE
Roland Beyer, et al., Nuclear Instruments and Methods in Physics Research A 723 (2013) 151–162
Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data
P. Schillebeeckx et al., Nuclear Data Sheets 113 (2012) 3054–3100
Inelastic neutron scattering from excited states in 56Fe
R. Beyer et al., Nuclear Physics A 927 (2014) 41
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Liquid Metal Technologies
DRESDYN – 3D design and curreent comnstruction status
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Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
Institute of Fluid Dynamics
Measurement techniques for liquid metal flows
applicable to flows of Na, Pb, PbBi, etc.
Local flow fields (3D) can be measured by:
- Ultrasonic Doppler velocimetry (UDV)
- Contactless inductive flow tomography (CIFT)
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-2000
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-1200
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0
ve
locity [m
m/s
]
depth [mm]
Essential development over past 1-2 decades:
Liquid metal flows can (almost) completely
be measured and monitored
Velocity profiles
in the Na duct flow
at HZDR
measured by UDV
(4 MHz, 5 mm)
A flow field modifies an externally applied magnetic field:
the magnetic field measured outside the melt
contains full information about the flow field
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Integral flowrate: Eddy-current flowrate measurements (ECFM)
Sketch of the flowrate sensor
y
x
z
flow receiver coil1
receiver coil2
channelwall
emitter
coil
magnetic field
induced currents
J. Priede, D. Buchenau, G. Gerbeth: Contactless electromagnetic phase-shift
flowmeter for liquid metals. Meas. Sci. Technol. 22, 055402, 2011.
Phase-shift sensor of HZDR:
phase-shift between receiver coils proportional to flowrate
Coils around the flow
Commercially available via company SAAS Ltd. Dresden
Tested at: THESYS (KIT), WebExpir (SCK Mol), NACIE (ENEA), etc.
planned model exp.
using GaInSn
Transient application:
Flow around the sensor
for detection of flow
blockages
Text optional: Institutsname Prof. Dr. Hans Mustermann www.fzd.de Mitglied der Leibniz-Gemeinschaft
Enhanced Feedback Effects
Assembly burnup distribution wit and without modrating material
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Enhanced Feedback Effects
Merk, Weiß, Annals of Nuclear Energy 38,5, (2011), 921-929
Merk, Weiß, Annals of Nuclear Energy 38,11 (2011) 2374–2385
Merk, Fridman, Kliem, Weiß, Nuclear Sc. and Eng. 171 (2012) 136-149
Insertion of fine distributed moderating material:
Hydrogen bearing metal compound
Significant low energy tail formed in the spectrum
Ideally located in the spacer wire
ZrH or better YH for increased thermal stability
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x p
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eth
arg
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(1/c
m²/
s)
neutron energy (eV)
rad
iati
ve
cap
ture
co
rss s
ecti
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(barn
)
reference
YH
U-238
Pu-239
Pu-240
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Optimization of Fast Reactor Safety for P&T
feedback effects are an inherent safety
mechanism in all nuclear reactors
Insertion of fine distributed
moderating material
enhances the negative Doppler effect
reduces the positive sodium void effect
reduces the positive coolant effect
insertion of transmutation materials
damps the feedback effects
compensation of effects caused by insertion of
transmutation materials (Americium)
improved transmutation efficiency due to higher possible loading
refere
nce
with m
od. materia
l
with A
m
with A
m + mod.
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Doppler effect
Coolant effect
Void effect
ch
an
ge
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ac
tiv
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eff
ec
t [%
]
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Effect of Plutonium Loading
Strong effect of Pu content on Doppler effect
Nearly no effect on reduction of sodium void
Effect of Pu content reduces during burnup
breeding in low content vs. burning in high content
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BOL
EOL
rel.
ch
an
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in
fu
el
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p.
eff
ec
t [%
]
Plutonium content [%]
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eff
ec
t [%
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Plutonium content [%]
BOL
EOL
Text optional: Institutsname Prof. Dr. Hans Mustermann www.fzd.de Mitglied der Leibniz-Gemeinschaft
Contribution to
P&T Study
Repository exploration site
Gorleben
Fast reactor Superphenix
Reprocessing plant La Hague
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Workpackage Status of Science and Technology
Reactor systems for P&T – with special view on the boundary
conditions given by the phase out
Overview on the status of science and technology in research and
application
Separation chemistry
Safety aspects in partitioning
accelerator technology and spallation targets
transmutation fuels
Basic physics and core design
Reactor physics and simulation tools
Safety approach for P&T systems
Material concepts and key technologies for liquid metal systems
Waste conditioning
Existing irradiation facilities with fast spectrum
Collection of open questions and technology gaps
Development of a strategy to close the technology gaps
Text optional: Institutsname Prof. Dr. Hans Mustermann www.fzd.de Mitglied der Leibniz-Gemeinschaft
Molten Salt Reactor for P&T
EVOL – Benachmark definition and layout sketch
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Transmutation Optimized Configuration in Phase Out Scenario
Idea born during P&T study
Bypass special problems in transmutation optimized systems
appearing in solid fuelled reactors
Multi recycling
Solid fuel production
Degradation of feedback effects
Avoiding of extensive transports
Adaption of EVOL design for P&T
Use of fertile free core composition
Use of MOSART salt composition
Application of deep burn phase
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Simulation of MSFR operation in transmuter mode followed by deep burn
mode using HELIOS 1.10 and a PHYTON script
Average criticality over cycle 𝒌 TRU and heavy metal content
TRU content is over the whole operation below solubility limit of 3 at% at
600°C for the MOSART salt
Scenario for Germany
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-0.010
-0.008
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-0.004
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end of operationdeep burn
k
cycles [-]
k
transmuter operation
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end of operationdeep burn
num
ber
density [n/b
arn
/cm
]
cycles [-]
heavy metal content
TRU content
transmuter operation
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Calculation Results for Germany
Operational results
Thermal power 3000 MW
available TRU 170 tons
real TRU inserted (per
reactor) 56.59 tons
operation time –
transmuter 44.9 years
TRU burning rate (calc.) 42.5 kg/TWh
theoretical burning rate 42.3 kg/TWh
operation time – deep burn 15.7 years
over all operation time –
transmuter + deep burn 60.6 years
TRU end of operation –
deep burn 0.115 tons
TRU burnt –
transmuter + deep burn 99.8 %
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Nuclear Data Measurements at the photoneutron source nELBE
Extending the scope of accurate nuclear data
New Isotopes:
Minor actinides, New coolants, structural materials
New energy range:
Fast neutrons
New reactions:
(in)elastic scattering, (n,tot), (n,fis)
New neutron facilities:
Helmholtz-Zentrum Dreden-Rossendorf operates
the world‘s only photoneutron source at a superconducting
electron accelerator:
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Measuring field: sitch-on – switch-off
eddy currents influenced by metal flow
3 measuring coils deliver flow velocity
around the sensor
calibration free!
ECFM: Flowrate measurements
TEC-FM: Transient eddy-current flow meter
planned model experiment
using GaInSn
recent activity:
Flow around the sensor
for detection of flow
blockages
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Calculation flow for the calculation of a molten salt reactor with online salt
cleanup using HELIOS 1.10
Intensive use of the power of the post processing tool ZENITH of the HELIOS
package
Calculation Flow using PYTHON Script
only printed
isotopes
re-distribution
of materials
isotopes
converged
re-feeding
material
user input output
expert
input
post-processor pre-processor
AURORA HELIOS ZENITH
SKRIPT