The GDT-based fusion neutron source as a driver of subcritical nuclear fuel systems

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1 The GDT-based fusion neutron source as a driver of subcritical nuclear fuel systems Presented by A.A.Ivanov Budker Institute, FZD Rossendorf, Joint Institute for Nuclear,, VNIITF, Snejinsk

2 Layout of the talk Physics of GDT based neutron source Application as a driver for sub-critical fission reactor Application as a MA burner Possible re-optimization GDT-NS for application as a driver Conclusions

3 Gas Dynamic Trap 3

4 Basic principles of GDT operation The Gas-Dynamic Trap is a version of a standard simple mirror whose characteristic features are a very high mirror ratio, R, in the range of a few tens; a relatively large length, L,exceeding an effective mean free path, λ ii lnr /R, with respect to scattering into the loss cone. The warm target plasma is almost Maxwellian behaves like an ideal gas in a container with a pinhole leak MHD-stable even though system is fully axially symmetric non-negligible amount of plasma in the regions beyond the mirror throats, where magnetic field has favorable curvature MHD ballooning/interchange modes limit stability at β 40-60% The electron neat flux to the end walls is suppressed by strong reduction of magnetic field in expanders 4

5 Requirements to VNS for fusion materials testing Fusion neutron spectrum About 2MW/m 2 neutron flux or higher for accelerated tests Small enough gradient of neutron flux density Continuous operation Availability more than 70% Reasonable tritium consumption

6 Schematic view of the GDT-NS for the material tests

7 Basic set of parameters for two and three component version of GDT-NS Parameter Two component version Three component version Tritium beam energy (kev) Deuterium beam energy (kev) - 80 Tritium beam power (MW) Deuterium beam power (MW) Electron temperature (kev) Plasma density (m -3 ) 2 x x10 20 Plasma radius at the center (m) Mirror ratio Central field (T) Injection angle (deg.) Max. neutron flux (MW/m 2 ) Power consumption (MW) 50 60

8 Neutron spectrum in GDT-NS

9 GDT-NS: reference set of parameters POWER CONSUMPTION - 47 MW MAGNETIC FIELD IN MIRRORS, B m = 13 T; MIRROR RATIO R = 10 INJECTION ANGLE, θ =30 0 INJECTION ENERGY - 65 kev PLASMA DIAMETER AT MIDPLANE, 2a = 16 cm RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY T e /E INJ =10-2 MIRROR-TO-MIRROR, 11.4 m NEUTRON SOURCE INTENSITY s -1

10 Neutron flux density vs injection energy

11 Neutron flux density vs electron temperature Injection energy 65keV Power consumption 60MW

12 Cutaway view of the GDT-NS

13 Elevation view of GDT-NS

14 Neutron yield profile in GDT-NS

15 Neutron field characteristics

16 GDT device general view 16

17 Physics issues addressed in the experiments Factors controlling electron temperature Microstability of fast ions Steady state operation Ballooning instability threshold Effect of ambipolar fields on confinement Effect of plasma rotation/vortex barrier formation Non-paraxial effects due to high β

18 GDT device - important results MHD stable confinement of plasma with β exceeding 0.4 is achieved in axially symmetric magnetic field Stability of high-β plasma is demonstrated with external anchor cells (expander and cusp) Plasma stabilization by vortex barrier is demonstrated Plasma energy balance is determined by energy transfer from fast ions and losses through end mirrors Electron heat conduction to the end walls is suppressed by strong reduction of magnetic field in expander Relaxation rates of anisotropic fast ions are classical no microinstabilities Skew injection of neutral beams at midplane provides formation of fast ion density peaks near turning points Plasma is sustained during several characteristic times with extended neutral beams 18

19 Measured axial profile of DD-reaction intensity

20 Neutron flux vs plasma temperature NB energy 65keV 65keV injection energy 20

21 Electron temperature vs time 21

22 Plasma β in steady stay with D 0 beams βmax 40% n f 5x10 19 m -3 22

23 Formation of vortex barrier

24 End loss reduction by fast ion density peaking near the ends Peak density in local mirror cell vs trapped NB power Reduction of end loss current density with beam injection into local mirror cell

25 Experiment with max Te Standard experimental scenario Te 230eV Mean ion energy 8.0keV Confinement time Transient regime 160eV 10keV 0.001s Injected power Electron density 3.5MW 1.5x10 19 m MW Fusion triple product (nτei=2.0x10 17 kevm -3 s) Maximum stored energy Maximum β Plasma parameters in GDT 1.2 KJ <beta> 50% at B=0.5T Maximum density >10 20 m -3 Values in bold are maximum attained ones. 5.0x10 19 m -3 25

26 Existing GDT-NS version as a driver for sub-critical reactor

27 Results of simulations Neutron production in driver s -1 Overall multiplication factor 0.95 Thermal power generated ~0.5GW Neutron shield for SS coils Pb+water 60cm Filter material Pb 10cm

28 Energy amplifier proposed by C. Rubbia (1995): Principles of an ADS: Accelerator particle beam Target neutrons Sub-critical system (protons) (heavy metal) (spallation) (arrangement of nuclear fuel) Strong neutron field inside the whole volume of the fuel system by means of fissions! Important features: 1. Sub-criticality: k eff 0.98! 2. No control rods! Power control by proton beam! Release of nuclear energy Transmutation of nuclear waste!

29 Introduction Nuclear systems Driven sub-critical system, ADS, FDS? Accelerator z Effective multiplication factor: k eff Driven systems: k eff determines the self-multiplicity of the system: p E p 1 GeV Sub-critical Driven Reactor: system: k eff = < 1 I p = =const. 10 = ~ 0S 200 > ma 0 k eff < 1: M eff =k eff /(1-k eff ): f eff =M eff /ν : Core n Spallation n s/p=10-30 r Reflector

30 Energy spectra of ADS and GDT neutron source:

31 total n,2n n,γ n,3n 10 MeV

32 Consideration of GDT-NS for fission fuel systems Re-arrangement of neutron production zone (elongation (keff<0.97) to L 5 m on each side gives: Sn= n/s, Pfus=7.1 MW, Pfis 1400 MW, Pinp 200 MW) Re-optimization of operational parameters Increase of electron temperature (Te higher than 1.5keV would provide higher efficiency than ADS) Reduction of axial losses by ambipolar potential peaks (demonstrated) On-site tritium breeding K. Noack,et al, Annals of Nuclear Energy, 35(7), pp , (2008) P.Bagryansky, et al, Fusion eng. and design, 70, pp , (2004)

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