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KIT – University of the State of Baden-Württemberg and National 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 af Institut für Sicherheitsforschung, Forschungszentrum Dresden-Rossendo Budker INP Novosibirsk n collaboration with: n collaboration with: tute for Neutron Physics and Reactor Technology, KIT, Karlsruhe, Ge

Andrey Anikeev

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Budker INP Novosibirsk. Numerical model of the fusion-fission hybrid system based on gas dynamic trap for transmutation of radioactive wastes. Andrey Anikeev. Institute for Neutron Physics and Reactor Technology, KIT, Karlsruhe, Germany. In collaboration with:. - PowerPoint PPT Presentation

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Page 1: Andrey Anikeev

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

Page 2: Andrey Anikeev

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.

Page 3: Andrey Anikeev

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

Page 4: Andrey Anikeev

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

Page 5: Andrey Anikeev

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

Page 6: Andrey Anikeev

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

Page 7: Andrey Anikeev

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).

Page 8: Andrey Anikeev

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).

Page 9: Andrey Anikeev

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

Page 10: Andrey Anikeev

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).

Page 11: Andrey Anikeev

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.

Page 12: Andrey Anikeev

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.

Page 13: Andrey Anikeev

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

Page 14: Andrey Anikeev

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

Page 15: Andrey Anikeev

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

Page 16: Andrey Anikeev

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

Page 17: Andrey Anikeev

17 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

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

Page 18: Andrey Anikeev

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

Page 19: Andrey Anikeev

19 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

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.

Page 20: Andrey Anikeev

20 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

Thank you for attention!!!