1. FEC-2012, San Diego, CA, USA October 8-13, 2012
National Research Centre “Kurchatov Institute”
Kurchatov Centre of Nuclear Technology
Institute of Tokamak Physics
Development of magnetic fusion neutron sources and fusion-fission hybrid systems in Russia
E. Azizov, G. Gladush, B. Kuteev
FEC-2012, San Diego, CA, USA October 8-13, 2012

2. NRC “Kurchatov Institute”
Motivation
The strategic goal of developing nuclear power industry in Russia is the production of GW electric power until 2030
This goal is to be achieved using existing technologies of thermonuclear reactor
Fast reactors are considered in Russia as the basis of industrial nuclear power for a period later than 30-th, however those still need R&D for reaching the reasonable capacity, safety and economy

3. Problems of nuclear power
NRC “Kurchatov Institute”
Problems of nuclear power
Lack of fuel for thermal reactors
Poor development of economic and safe fast reactor
Development of closed fuel cycle
Utilization of spent nuclear fuel
Acceptance of nuclear power safety by public
Nonproliferation

4. Fission Energy needs Fusion neutrons
NRC “Kurchatov Institute”
Fission Energy needs Fusion neutrons
Further to nuclear fuel breeding, the problem of waste handling exists,
supporting the high growth rate scenario of Nuclear Industry development
IAEA Nuclear Energy Series No NP-T-1.8
Nuclear Energy Development in 21-st Century:
Global scenarios and regional trends.
2010,Vienna, Austria.
These issues are considered in:

5. The existing intense Neutron Sources
NRC “Kurchatov Institute”
The existing intense Neutron Sources
Spallation
Fission
Future Neutron Sources
Tokamaks
Microexplosion

6. location, used nuclides Neutron Power Output, MW
NRC “Kurchatov Institute”
Most powerful neutron sources in the world (* - projects)
Neutron Source Type
Facility,
location, used nuclides
Deposited Power, MW
Rate, 1017 n/s
Neutron Power Output, MW
Max. Neutron Flux
SS/Peak
n/cm2s
Fission reactor
ILL (Grenoble, France), U235 56 10
1,5
1015
Accelerator
SNS (ORNL, USA), p, Hg
1/30000)
1/30000
0.3/10000
1016
Tokamak
*JT-60SA (Naka, Japan), D
0.01/0.5
0.01/2
0/0.4
1011
*ITER (Cadarache, France), D, T
500
1800
400
~4x1013
Laser system
*LIFE (LLNL, USA),
D, T
1000
2100
800
1017

7. Challenges for Fusion Neutron Sources
NRC “Kurchatov Institute”
Challenges for Fusion Neutron Sources
Useful neutrons thermal n-flux > 1015 n/cm2s
Transmutation n-source rate > 1018 n/s
Fuel breeding n-source rate > 1020 n/s
MW fusion power may compete in neutron production with contemporary neutron sources - fission reactors and spallation neutron sources
Steady State Operations in neutron environment is the basic requirement for FNS and Hybrids
Pulsed Operation mode is acceptable for research

8. Interest to Hybrid systems in Russia rised again because:
NRC “Kurchatov Institute”
Interest to Hybrid systems in Russia rised again because:
Necessity to have resources for Nuclear Power involving U238 and Th232 fuel cycles.
Luck of fundamental decision on utilization of the spent nuclear fuel.
Hybrids can be real alternative to fast breeders and transmutation reactors

9. NRC “Kurchatov Institute”
Hybrid systems based on tokamak are attractive because main technologies are properly developed
Economically acceptable value of neutron flux should be about ~ MW/m2
Technical requirements to steady-state tokamak device as fusion neutron source for Hybrids are reduced compared with pure fusion case therefore they seem like quite achievable

10. Schematic diagram of a Fusion-Fission Hybrid
D,T
Heating and NBI
Neutron customers
Nuclide customers
Blanket Active core
Tokamak
Neutrons
Neutrons E=14.1 MeV
Transmutation service
High Temp Heat
Irradiated Fuel
~100 MW
Radio-Chemical Technologies

11. Concept of compact tokamak FNS
NRC “Kurchatov Institute”
Concept of compact tokamak FNS
aspect ratio from spherical tokamak to classical
moderate sizes and elongation
Q ≤ 1
Pfus = MW
enhance factor H of ITER confinement time ITB98(2,y) 
neutral beams with energy ( keV) for heating, current drive and beam-plasma fusion.
combined inductive and non-inductive plasma formation, current ramp up and proper control of steady-state mode.

12. Plan for hybrid reactors development in Russia
NRC “Kurchatov Institute”
Plan for hybrid reactors development in Russia
First step
Design and reconstruction of tokamak T-15 and ST Globus MU as a physical prototypes of FNS.
Second step
Development of FNS and design of hybrid pilot plants for nuclear breeding and transmutation
Third step
Design, construction and transfer to nuclear power industry a hybrid reactors for nuclear fuel breeding and transmutation as well as intense neutron source for research and innovative technologies

13. Two nuclear fuel cycles are considered
NRC “Kurchatov Institute”
Two nuclear fuel cycles are considered
Hear exchanger, primary loop
Hear exchanger, secondary loop
Heat transfer
Molten salt
85% FLiNaK+15% ThF4580ºС 5.86 кг/с
550ºС
1 bar
92% NaBF4+8% NaF 539ºС
480ºС
1.7 kg/s
140ºС
10 bar
water
20ºС
Molten salt blanket module Thermal power 175 kW
Primary loop
Secondary loop
Cooler
Drain vessel
Storage
Solid blanket module
pump
U-Pu
1Pu+1T per 1n(DT)
Th-U
0.6U+1T per 1n(DT)

14. Time scale of hybrids development
NRC “Kurchatov Institute”
Time scale of hybrids development
Current activity:
Development the physical prototype T-15 and demonstration FNS for hybrid systems
Several options for demonstration tokamak- FNS with warm and superconducting electromagnetic system have been considered to ensure the maintenance of steady-state mode at conceptual level since 2009
Plans:
Facilities to be constructed and put into operation:
Physical prototype of FNS (T-15, Globus MU)
TIN-1 (demonstration tokamak-FNS)
Pilot plant
Industrial hybrid reactor

15. Tokamak T-15 Upgraded is Under Construction Now
Main parameters of T-15 after modernisation
Aspect ratio
2.2
Plasma current IP, МА
2.0
Major radius R,м
1,48
Elongation
1.9
Triangularity, δ
Plasma configuration SN
Discharge duration tразр, sec
5-10
Toroidal magnetic field Bt, Тл
NBI power, MW 9
NBI Energy, keV
120
ECRH power, MW 6

16. The tokamak FNS with warm EMS, R0=1.5 m
RSC “Kurchatov Institute”
FNS with SC EMS (R=1.9 m)
Plasma current, Ip (MA) 3.2
Current Drive, INBI (МА) 2.3
Safety Factor at 95 % flux, q
Average electron density, <n20> (m-3) 0.5
Average ion temperature, <Ti> (keV) 4.7
Confinement time, Е (s)
Normalized beta, N
Total DT fusion neutron power, Pn(MW)
Fusion gain, Q=Pfus/PNBI
14 MeV neutron flux, n (MW/m2) 0.21
The tokamak FNS with warm EMS, R0=1.5 m
Major radius, R0(m) 1.5
Minor radius, a (m) 0.68
Plasma Elongation,  1.75
Toroidal magnetic field, Bt0(T) 3.0
NBI power, PNBI (MW) 15
Neutral particle energy, ENBI (keV) 140
Fuel composition D:T :0.75
Pulse length, s 60

17. FNS-ST project Main design constraints:
NRC “Kurchatov Institute”
FNS-ST project
The mission of the FNS-ST is to be a prototype of a fusion-fission hybrid system with the fusion power below 10 MW and fission power below 100 MW, being capable to produce neutrons with fast/thermal spectra with the plant life time of several decades.
Main design constraints:
- Minimization of the device size is desirable to reach highest neutron flux density
- Reducing the total electric power consumption below 50 MW follows from the desire to keep the capital cost <200 M$ and operation cost <30 M$ with the duty factor of 0.3
- Tritium consumption to be less than 100 grams per year
B.V. Kuteev et. Al. “Plasma Physics Reports, 2010, vol.36, pp.281

18. FNS-ST: basic parameters and cut-view
R, m
0.5
R/a
1.67 k
2.75 δ
Ip, MA
1.5
BT, T
n, 1020m-3 1
Pwall, MW/m2
0.2
Eb, keV
130
Pb, MW 10
Angle NBI, deg 30
PEC, MW 5
H-factor
1-2 βN
fnon-ind
1.0
Pdiss, TF, MW 14
Pdiss, PF, MW
6.0
Swall, m2 13
Vpl, m3
2.5
Strongly shape device
B. V. Kuteev et al. Nuclear Fusion 51 (2011)

19. Globus-M spherical tokamak demonstrated
all project objectives and will be upgraded by 2.5 fold increase of magnetic field and plasma current, retaining vacuum vessel (aspect ratio) and most of the systems for investigation of low collisionality regimes specific for compact FNS - machine name is Globus-M2
Globus-M Globus-M2
Btor T 1 T
Ipl MA 0.5 MA
Tpulse s 0.3 s
Collis., ν*
R m unchanged
a m unchanged
R/a unchanged
 unchanged
δ unchanged
<n> [max] ~11020 m-3 unchanged
Auxiliary CD
NBI keV/1 MW keV/1.5MW
ICRH 7 MHz/0.3 MW MHz/1MW
LH MHz/0.06MW GHz/0.5MW
Globus-M has basically achieved all project objectives, however some of results were achieved in separate.
Globus-M
Globus-M2
Close fitting wall; RGT tiles; Plasma gun; 19

20. Ignitor project
Ignition may be possible in highly shaped ST with Bt=5T and Ip=11 MA
Parameters
Symbol
Ignitor
Coppi
Unit
FNS-IGN
Plasma current  Ip
11 
MA  11
Toroidal magnetic field  Bt
13  T 
5,0
Central electron temperature /average
Te0
11.5 
keV  5
Central ion temperature /average
Ti0
10.5
Central electron density/average 
ne0
1.0 × 1021
m-3
Plasma stored energy  W 
11.9 
MJ  15
Ohmic power 
POH
11.2 
MW  10
Auxiliary power (ICRH) 
PICRH 0 
Alpha power  Pa
19.2  20
Energy replacement time  tE
0.62  s 
0,75
Poloidal beta  bp
0.20 
0,79
Toroidal beta  bT
1.2  % 
15,7
Central beta b0
5.0  % 25
Edge qy qa
3.6 
7,3
Bootstrap current 
Ibs
0.86 
5,1
Major radius R
1.32 m
0.6
Minor radius a
0.47
0.4
Aspect ratio A
2.8
1.5
Elongation k
1.83
3.3
Triangularity d
0.7
Central stack current
Ics
85.8 MA 18
Ignitor
Coppi

21. Assessment of the options
NRC “Kurchatov Institute”
Assessment of the options
Construction cost of SC option, including nuclear part, is about B$ that we consider as too expensive for the first step
The copper coil version with test blanket modules placed in ports costs about 200 M$.
This version seems preferable

22. Russia develops GDT based fusion neutron source
Kotelnikov I.A., Mirnov V.V., Nagorny V.P., Ryutov D.D., Plasma Physics and Controlled Fusion Research, 2, IAEA, Vienna, p.309, 1985
Test zones
~ 15 m
Magnetic field: B T Neutral beam injection: D0+T0
Bm 15 T energy, ED/T 65 keV
Warm (target) plasma: power, Pinj 36 MW
temperature Те 0.75 keV Fast ion mean energy: keV
density ne 2-5 x 1020 m-3 Fusion power (in neutrons): MW

23. Nuclear technology issues for FNS&Hybrids
NRC “Kurchatov Institute”
Nuclear technology issues for FNS&Hybrids
Radiation-resistant materials (first wall, vacuum vessel, blanket, divertor, manifolds, etc.)
Effective blanket (neutron economy, fuel and fuel cycle, сооlants, efficient design solutions)
Development of tritium breeding cycle
Effective radiation shielding of magnet and other systems
Safety issues

24. NRC “Kurchatov Institute”
Conclusions
The existing database, theoretical analysis, modeling and advanced technologies allow us:
to develop a compact fusion neutron source based on a tokamak with aspect ratio between ST and conventional one
to expect reasonable risks associated with physical and technological problems on the tokamak-way to a FNS for hybrid systems and research
to participate in ITER project and development of hybrid systems and research FNS as the key issues of Russian fusion program