KIT – University of the State of Baden-Württemberg andNational Large-scale Research Center of the Helmholtz Association www.kit.edu
Numerical model of the fusion-fission hybrid system based on gas dynamic trap for transmutation of radioactive wastes
Andrey Anikeev
Budker Institute of Nuclear Physics, Novosibirsk, Russia (original affilation)
Institut für Sicherheitsforschung, Forschungszentrum Dresden-Rossendorf.
Budker INPNovosibirsk
In collaboration with:In collaboration with:
Institute for Neutron Physics and Reactor Technology, KIT, Karlsruhe, Germany
2 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
MotivationMotivation
Transmutation of long-lived radioactive nuclear waste, including
plutonium, minor actinides and fission products, represents a highly
important problem of fission reactor technology and is presently studied
worldwide in large-scale.
Fusion-fission devices might be useful such as the production of fuel for
fission reactors, direct electricity production, and closing the nuclear fuel
cycle by transmuting spent nuclear fuel from fission reactors.
GDT based neutron source shows great promise in future fusion-fission
applications.
3 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
ObjectivesObjectives
Numerical modelling and choice of parameters of the GDT NS as a driver in ADS-like subcritical burners.
Neutron flux > 1018 n/s
Test a GDT-DS burner capability
Requirements to MA burner systems:
energy efficiency Q=Poutel/Pinp
el > 1 (self-sufficiency) !
servicing of min 5 LWRs
4 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
GDT plasma neutron source as irradiation facility
BackgroundBackground
Test zone
Kotelnikov I.A., Mirnov V.V., Nagorny V.P., Ryutov D.D., Plasma Physics and Controlled Fusion Research, 2, IAEA, Vienna, p.309, 1985
~ 15 m
Magnetic field : B0 1 T Neutral beams injection: D0+T0
B 15 T energy , ED/T 65 keV Target warm plasma : total power, Pinj 36 MW temperature Те 0.75 keV Energy consumption: 60 MW (50 MW) density ne 2-5 x 1020 m-3 Total fusion neutron power: 1.25 MW
5 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
GDT plasma neutron source as irradiation facility
BackgroundBackground
Test zone
Kotelnikov I.A., Mirnov V.V., Nagorny V.P., Ryutov D.D., Plasma Physics and Controlled Fusion Research, 2, IAEA, Vienna, p.309, 1985
6 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
Positive features of the GDT NS:• Continuous source.
• 2 drivers with variable intensities.
• n-zones can be longitudinally extended.
• n-emission intensity can be axially profiled.
• Neutron energy = 14 MeV
Is a compact machine relatively low investment costs!
The technical idea would be to put up the GDT vertically and to surround both neutron production zones by a sub-critical system.
GDT neutron source driven systemTechnical idea
7 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
* for both side of GDT (2 n-zones)
Source: ADS [1] GDT basic [2]
GDT basic [2,3] Te~ 3.5 keV
GDT long [2] 2x1.5 m
GDT long [3]
2x4 m
Psuppl; MW 20 50 50 100 150
Pnusefull, MW 0.25 * 0.44 * 1.4 * 1.5 * 4
Sn , neutron/s 1.25х1018 * 2 х 1017 * 6.4x1017 * 6.8х1017 * 1.8х1018
Pfis , MW (total) 263 87 288 378 1044
Pelout , МW (η=40%) 105 35 115 151 418
Q= Pelout / Psuppl; 5.3 0.7 2.3 1.5 2.8
MA burning rate, kg/year( 1 LWRs = 29 kg / year)
36 (1.2) 23 (0.8) 75 (2.6) 52 (1.8) 144 (5)
Preceding Preceding results results Comparison of the driven sub-critical MA burners
[1] G. Aliberti et al.. Nuclear Science and Eng. 146 (2004) 13.
[2] K. Noack et al. Annals of Nuclear Energy 35 (2008) 1216–1222.
[3] A. Anikeev et al. in Proc. of Cairo 11th International Conference on Energy & Environment (2009).
8 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
* for both side of GDT (2 n-zones)
Source: ADS [1] GDT basic [2]
GDT basic [2,3] Te~ 3.5 keV
GDT long [2] 2x1.5 m
GDT long [3]
2x4 m
Psuppl; MW 20 50 50 100 150
Pnusefull, MW 0.25 * 0.44 * 1.4 * 1.5 * 4
Sn , neutron/s 1.25х1018 * 2 х 1017 * 6.4x1017 * 6.8х1017 * 1.8х1018
Pfis , MW (total) 263 87 288 378 1044
Pelout , МW (η=40%) 105 35 115 151 418
Q= Pelout / Psuppl; 5.3 0.7 2.3 1.5 2.8
MA burning rate, kg/year( 1 LWRs = 29 kg / year)
36 (1.2) 23 (0.8) 75 (2.6) 52 (1.8) 144 (5)
Preceding Preceding results results Comparison of the driven sub-critical MA burners
[1] G. Aliberti et al.. Nuclear Science and Eng. 146 (2004) 13.
[2] K. Noack et al. Annals of Nuclear Energy 35 (2008) 1216–1222.
[3] A. Anikeev et al. in Proc. of Cairo 11th International Conference on Energy & Environment (2009).
9 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
I. Improvement of the GDT basicGDT basic: Electron temperature
Study:Study: Optimisation of the GDT neutron source
: Te should be increased up to the self-consistent value.
– Radial confinement !
– Reduction of the electron heat losses !
0
1
2
3
0 1 2 3 4
Te (keV)
Q
x
0.75
GDT „Basic version“: Pinp = 50 MWel, Einj = 65 keV
GDT-DS
Te < 10-2 Einj !
~3 !
3.5
: Pfis = 144 МW therm (one side) Pfis
total = 288 MW therm (both side)Pout
total = 115 MWel
Q = 2.3 ~3
10 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
I. Improvement of the GDT basicGDT basic: Electron temperature
Study:Study: Optimisation of the GDT neutron source
: Te should be increased up to the self-consistent value.
– Radial confinement !
– Reduction of the electron heat losses !
0
20
40
60
80
100
120
140
160
180
200
0,00 0,50 1,00 1,50 2,00
Ph (MW)
Te
(eV
)
■ GDT experiment
♦ Estimation
Te~Ph2/3
▲ Estimation
Te~Ph2/7
(electron heat conductivity).
11 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
II. Improved GDT neutron source for driven system (KIT version):
Study:Study: Optimisation of the GDT neutron source
Requirements: Continuous source.
Neutron emission Sn > 1018 n/s (for each n-zones).
Neutron power flux densyty qn < 2 MW/m2 → Geometry of the n-zone.
Fusion energy efficiency Qfus ~ 1 → low energy “cost” of a neutron.
Assumptions:
Improved axial confinement → low axial loses → Te ~ 3 keV.
Vortex radial confinement → low transverse tranport.
High β ~ 60% (experimentally attained value).
Maximal magnetic field in the mirror with approriate mirror ratio.
Pilet injection → steady state plasma density.
Extended neutron emission region → 2 x 2m n-zones.
12 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
II. Improved GDT neutron source for driven system:
Study:Study: Optimisation of the GDT neutron source
Instruments and methods of modeling:
A full 3D calculations by Integrated Transport Code System (ITCS).
ITCS includes modules:
MCFIT – Monte-Carlo Fast Ions Transport code – fast ions, fusion reactions.
NeuFIT – Neutral particles and gas simulations.
FITMag – Magnetic field perturbation by high pressure plasmas (β reduction).
PlasmaX – Target plasma simulations (heating, losses → temperature).
NeutronS – Neutron flux calculation.
+ Input/Output subroutines.
13 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
II. Improved GDT neutron source for driven system:
Study:Study: Optimisation of the GDT neutron source
Results: Main parameters of the GDTNS_KA:
Magnetic field (SC coils):in midplane, B0 1 T
im mirror, Bm 15 T
lenght, L 16 m
Target warm plasma : temperature, Те 3 keV
density, ne 5x1020 m-3
radius, a 10 cm
Neutral beams injection: D0+T0energy, Einj 65 keV
total power, Pinj 75 MW
trapped power, Ptr 50 MW
Fussion power:total, Pfus 15 MW
neutron, Pn 12 MW
neutron yield 1.6 MW/mIs a compact machine → low investment costs.
Electricity consumption ~ 120 MW.
2 x 2m neutron emission zones with intencivity of 1.5x1018 neutron/s
14 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
On axis magnetic field profileOn axis magnetic field profile
— vacuum magnetic field
– – beta reduced MF
n-zone n-zone
Results: Improved GDT neutron source for driven system
15 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
Axial profile of neutron yieldAxial profile of neutron yield
2 x 2 m neutron emission zones with intencivity of 1.5x1018 neutron/s
Results: Improved GDT neutron source for driven system
16 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
Study: Subcritical GDT driven MA burner
First analysis of proposed GDT driven subcritical reactor we made on a base of EFIT (European Facility for Industrial Transmutation) reactor design [1]. The EFIT reactor is designed to be a demonstration ADS facility for industrial scale transmutation of minor actinides, with a power of about 400 MWth. The EFIT reactor is cooled by lead. Its fuel is uranium free CERCER fuel 50% MgO +50% (Pu,MAO2) in volume, containing a large quantity of americium. The plutonium content is ~ 37% leading to Keff ~ 0.97.
In [2] several variations of EFIT design parameters were studied by using ENDF/B-6.5 based 69 group cross sections in the deterministic Sn code TWODANT. We used original (A) and extended (G) version of the EFIT reactor design for application with the GDT neutron source instead of the ADS lead target.
[1] J.U. Knebel et.al., 9th Information Exchange Meeting P&T, Nîmes, 2006
[2] M. Badea, R. Dagan, C.H.M. Broeders, Jahrestagung Kerntechnik 2007, Karlsruhe, 22.-24.Mai 2007
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for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
Applied EFIT-like cylindrical geometry with Applied EFIT-like cylindrical geometry with GDT neutron sourceGDT neutron source
Fuel
Pb
B
uff
er
Plenum
Pb_Ext
R=115.72 cm
R 48 cmR 30 cm
14 M
eV n
-sou
rce
40
0 c
m
25
0 c
m
Fuel
Pb
B
uff
er
Plenum
Pb_Ext
R=156.72 cm
R 48 cmR 30 cm
14 M
eV n
-so
urce
24
0 c
m
90
cm
A
G
The fuel composition CERCER fuel 50% MgO +50% (Pu,MAO2) : a) plutonium with weight fractions: Pu238 0.04, Pu239 0.46, Pu240 0.34, Pu241 0.04, Pu242 0.12b) MA with weight fractions: U234 0.04, Np237 0.04, Am241 0.73, Am243 0.15, Cm244 0.03, Cm245 0.01.
Study: Subcritical GDT driven MA burner
18 08.07.2010 88thth International Conference on Open Magnetic Systems International Conference on Open Magnetic Systems
for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
Source ADS GDT NS
Geometry A G A G
Radius (cm) 156.72 115.72 156.72 115.72
Height (cm) 240 400 240 400
Fuel height (cm) 90 250 90 250
Keff 0.9718 0.9724 0.9733 0.9741
Ks 0.9329 0.9573 0.9411 0.9577
Results of calculationsResults of calculations
Study: Subcritical GDT driven MA burner
Pfis = 550 MW therm (one side)
Pouttotal = 440 MWel (both side)
Pinp = 120 МВтel
Q = 3.7
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Conclusions.Conclusions.
A new improved numerical model of the GDT neutron source based on last experimental results with a scaling to high Te ~ 3 keV and Qfus~ 0.3 was proposed and numerical simulated. The two 2 m n-zones with 1.6 MW/m neutron yield can produce 1.5x1018n/s each. It can be used for application to FDS burner of MA.
Analysis of proposed GDT driven subcritical reactor for MA burning was made on the base of the EFIT reactor design. The elongated version of EFIT with GDT-NS instead a spallation target show considerable promise for future development of this model. Detailed 3D simulation and thermohydraulic study should be made in the nex step of the project.
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for Plasma Confinement, July 2010, Novosibirsk, Russiafor Plasma Confinement, July 2010, Novosibirsk, Russia
Thank you for attention!!!