Development of magnetic fusion neutron sources and fusion-fission hybrid systems in Russia

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

2. The strategic goal of developing nuclear power industry in Russia is the production of 30-40 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 NRC “Kurchatov Institute” Motivation

3. 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 NRC “Kurchatov Institute”

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

6. NRC “Kurchatov Institute” Most powerful neutron sources in the world (* - projects)

7. 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. 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 ~0.2-0.5 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. Neutron customers Nuclide customers Heating and NBI D,T Neutrons Neutrons E=14.1 MeV Irradiated Fuel Tokamak Blanket Active core Radio-Chemical Technologies ~100 MW Transmutation service High Temp Heat Schematic diagram of a Fusion-Fission Hybrid

11. Concept of compact tokamak FNS aspect ratio from spherical tokamak to classical moderate sizes and elongation Q ≤ 1 Pfus = 1 - 100 MW enhance factor H of ITER confinement time ITB98(2,y)  1.2-1.4 neutral beams with energy (100-140 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. NRC “Kurchatov Institute”

12. Plan for hybrid reactors developmentinRussia 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 NRC “Kurchatov Institute”

13. Storage Secondary loop 140ºС 10 bar water 20ºС Cooler Heat transfer Primary loop Drain vessel Hear exchanger, secondary loop Molten salt 92% NaBF4+8% NaF 539ºС 480ºС 1.7 kg/s NRC “Kurchatov Institute” Hear exchanger, primary loop Molten salt 85% FLiNaK+15% ThF4580ºС5.86 кг/с 550ºС 1 bar Molten salt blanket module Thermal power 175 kW Two nuclear fuel cycles are considered 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 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) 2015 TIN-1 (demonstration tokamak-FNS) 2018 Pilot plant 2022 Industrial hybrid reactor 2030 NRC “Kurchatov Institute”

15. Tokamak T-15 Upgraded is Under Construction Now Main parameters of T-15 after modernisation

16. Plasma current, Ip (MA) 3.2 Current Drive, INBI (МА) 2.3 Safety Factor at 95 % flux, q95 4.1 Average electron density, <n20> (m-3) 0.5 Average ion temperature, <Ti> (keV) 4.7 Confinement time, Е (s) 0.19 Normalized beta, N 2.7 Total DT fusion neutron power, Pn(MW) 16.1 Fusion gain, Q=Pfus/PNBI 0.64 14 MeV neutron flux, n (MW/m2) 0.21 RSC “Kurchatov Institute” FNS with SC EMS (R=1.9 m) 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 0.25:0.75 • Pulse length, s 60

17. 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. R, m 0.5 R/a 1.67 k 2.75 δ 0.5 Ip, MA 1.5 BT, T 1.5 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 5 fnon-ind 1.0 Pdiss, TF, MW 14 Pdiss, PF, MW 6.0 Swall, m2 13 Vpl, m3 2.5 FNS-ST:basic parameters and cut-view Strongly shape device B. V. Kuteev et al. Nuclear Fusion 51 (2011) 073013

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 Btor0.4 T1 T Ipl0.2 MA0.5 MA Tpulse 0.1 s0.3 s Collis., ν* 0.2-0.7 0.01-0.05 R 0.36 munchanged a 0.24 m unchanged R/a 1.5unchanged 2.0 unchanged δ0.5unchanged <n> [max] ~11020m-3unchanged Auxiliary heating @ CD NBI 30 keV/1 MW 40keV/1.5MW ICRH 7 MHz/0.3 MW 18MHz/1MW LH 900MHz/0.06MW 2.45GHz/0.5MW Globus-M Globus-M2 Close fitting wall; RGT tiles; Plasma gun;

20. Ignitor project Ignition may be possible in highly shaped ST with Bt=5T and Ip=11 MA Ignitor Coppi

21. Assessment of the options Construction cost of SC option, including nuclear part, is about 0.8-0.9 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 NRC “Kurchatov Institute”

22. ~ 15 m 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 Magnetic field: B0 1 T Neutral beam injection: D0+T0 Bm 15 T energy, ED/T65 keV Warm (target) plasma: power, Pinj 36 MW temperature Те 0.75 keV Fast ion mean energy: 30 keV density ne 2-5 x 1020 m-3 Fusion power (in neutrons): 1.25 MW

23. 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 NRC “Kurchatov Institute”

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