- Email: [email protected]
HT tests of liquid metal breeder blanket
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Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket A.Yu. Hon a , I.R. Kirillov a , K.A. Komov a , O.A. Kovalchuk a , A.A. Lancetov a , D.M. Obukhov a,∗ , D.A. Pertsev a , A.V. Pugachev b , I.Yu. Rodin a , E.R. Zapretilina a a b
JSC “NIIEFA” (D.V. Efremov Institute), 196641, Doroga na Metallostroy, 3, St. Peterburg, Russian Federation Forss Consulting Ltd, 195027, Magnitogorskaya Street, 51, lit. E, St. Petersburg, Russian Federation
h i g h l i g h t s • • • •
Overview of the new facility (LIMITEF5) is presented. The facility is aimed for MHD/HT tests of liquid metal breeder blanket mock-ups. The facility includes lead-lithium loop and superconducting magnet. Overview of the lead-lithium loop and superconducting magnet is given.
a r t i c l e
i n f o
Article history: Received 26 September 2016 Received in revised form 10 March 2017 Accepted 14 March 2017 Available online xxx Keywords: Liquid metal breeding blanket Superconducting magnet Lead-lithium loop MHD/HT test facility
a b s t r a c t This paper gives an overview of the new facility for MHD and heat transfer (HT) tests of liquid metal breeder blanket mock-ups in high magnetic field. The facility named LIMITEF5 is under construction now in JSC “NIIEFA” (D.V. Efremov Institute). The facility includes the lead-lithium (LL) loop passing through the warm aperture of the superconducting magnet. Superconducting magnet is planned to be put in operation in 2018 with the following characteristics: - magnetic field induction is up to 5.5 T; - dimensions of the magnet “warm” zone: diameter – 900 mm, length – 1600 mm; - winding design: low temperature superconducting split solenoid. LL loop consists of melting and feeding tanks; main loop with electromagnetic pump (EMP), electromagnetic flow meter, calibration nozzle, heat exchanger and blanket mock-up; LL impurities control and purification system containing oxygen sensor, plug indicator, cold trap, LL sampler. The details of the lead-lithium ceramic breeder test blanket module (LLCB TBM) mock-up for MHD/HT tests in magnetic field of ∼5 T which is under conceptual design are also given. © 2017 Elsevier B.V. All rights reserved.
1. Introduction Six Test Blanket Modules (TBMs) will be installed in ITER equatorial port to test DEMO relevant blanket options [1]. Lead-Lithium Ceramic Breeder (LLCB) TBM proposed by India [2] will be tested in port #2 of the ITER machine. India is a “leader” of LLCB TBM concept and responsible for delivery and subsequent tests of the IN LLCB TBM in ITER. Special-
∗ Corresponding author. E-mail address: [email protected] (D.M. Obukhov).
ists from Russian Federation are participating in design and R&D activity on IN LLCB TBM according to the technical program of cooperation between the leading research institutes of India (“leader”) and RF (“partner”). RF also has been developing the LLCB TBM design, with the aim to explore alternative design variants different from IN one in order to propose it for further application [3]. RF LLCB TBM design, similar in general to Indian LLCB TBM design for ITER, comprises the helium cooled load-bearing casing and tritium breeding zone with ceramic blocks (CB) and leadlithium (LL) ducts located inside the casing (Figs. 1,2). Tritium breeding zone (BZ) is arranged inside the TBM casing and surrounded by the internal surfaces of the first wall (FW), the casing
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Fig. 3. LL flow scheme in the TBM. (numbers of LL ducts and CB are designated by digits).
Fig. 1. General view of RF LLCB TBM. 1-Be armor; 2-FW cramp; 3-electrical insulating pad; 4-purge-gas outlet branchpipe; 5-covers of load-bearing casing; 6-shear key; 7-helium coolant outlet branchpipe; 8-flexible support; 9-electrical connector; 10- helium coolant inlet branchpipe; 11-LL outlet branch-pipe; 12-LL inlet branch-pipe; 13- purge-gas inlet branchpipe.
Fig. 4. LL loop hydraulic scheme. 1- EMP, 2–EFM, 3–normal nozzle, 4–supply tank, 5–mechanical filter, 6–TBM mockup, 7–LL sampler, 8–cold trap with water cooling, 9–plug indicator, 10–air cooler, 11–valve, 12 – oxygen sensor.
covers and gas manifolds unit. LL is intended to cool the BZ, to moderate the thermonuclear neutrons and to breed tritium. LL flow scheme inside TBM is shown in Fig. 3. R&D activity on LLCB TBM includes MHD and heat transfer tests of the TBM mock-ups and LL technology aspects (eutectic preparation, impurities control and LL purification). At the initial stage mock-ups tests were performed on the NaK and mercury in magnetic field (MF) 1 T (see some details in [4,5]). To test TBM mock-ups on LL in close to ITER MF values new facility for MHD and heat transfer (HT) tests named LIMITEF5 (LIquid Metal TEst Facility, 5 T) is under construction now in JSC “NIIEFA”. 2. Lead-lithium loop Fig. 2. Poloidal cross-section of RF LLCB TBM. 1-partition between upward and downward LL flows; 2-LL upward flow zone; 3-LL downward flow zone; 4-bimetallic adapter; 5- CB; 6- FW; 7-upper LL header; 8covers of load-bearing casing; 9-purge-gas outlet branch-pipe; 10-helium coolant outlet branch-pipe; 11-flexible support; 12-stiffness ribs of helium manifold; 13-electrical connector; 14-helium coolant inlet branch-pipe; 15-LL outlet branchpipe; 16-LL inlet branch-pipe; 17-purge-gas inlet branch-pipe; 18-lower LL header.
LL loop for LIMITEF5 facility (Figs. 4 and 5) consists of melting and feeding tanks; main loop with electromagnetic pump (EMP), electromagnetic flow meters (EFM), normal nozzle for flow meter calibration, heat exchanger and blanket mock-up; bypasses for LL impurities control and purification system containing oxygen sensor, plug indicator, cold trap, LL sampler; gas-vacuum and data acquisition systems. Loop main parameters are the following: overall dimensions – 5.7(length) × 2.5(width) × 3.6(height) m; pipes
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071
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Table 1 LL chemical composition.
mass%
Li
Fe
Cu
Ag
As, Sb, Sn, Zn
Bi
Pb
0.64 ± 0.03
0.001
<0.0005
0.0008
<0.0005
0.005
the rest
Fig. 5. Overall view of LL loop (test section and magnet are on the rear right side).
material – analog of AISI 304 steel; main loop pipes diameter 48 × 4 mm, LL inventory ∼80 l, LL temperature – 250–350 ◦ C, LL flow rate – up to 4 m3 /h, pressure developed by EMP – up to 0.5 MPa. EMP is Annular Linear Induction Pump (ALIP) with power supply parameters 380 V, 180 A, 200 Hz. The EMP can output parameters of the ITER TBM (pressure developed, flow rate). Loop main components (except EMP made in NIIEFA) and LL for the facility were delivered by IPPE, Obninsk. LL chemical composition is shown in Table 1, eutectic melting temperature is 232 ± 1◦ . LL loop purification system consists of mechanical filters in the filling up branch and cold trap combined with magnetic trap in the by-pass branch. Plug indicator and LL sampler are placed in the by-pass branch as well. Obtaining dependencies of plug indicator plugging from LL temperature at its entrance and flow rate for different positions of plug throttle one can judge on impurities concentration in LL alloy. LL sampler provides for solid samples removal from the loop for chemical analysis. Electrochemical oxygen sensor is based on zirconium dioxide solid electrolyte. For MHD/HT tests of LLCB TBM a number of mock-ups are under design/manufacturing from simple to around natural size ones. Simple mock-ups consisting of one or several rectangular ducts are planned for preliminary tests of MHD and HT phenomena including buoyancy effects in vertical ducts placed in coplanar magnetic field of high intensity. One of such mock-ups (see Fig. 6) includes two parallel upward flow ducts divided in a number of sub-ducts in toroidal direction and one downward flow duct. Large size mockup will get all details of breeding zone (Fig. 2) with real toroidal and radial dimensions (462 × 580 mm) and around 1/3 of poloidal dimension. In this mock-up it is important to retain all peculiarities of TBM BZ and casing, since MHD characteristics are determined by induced electric currents closing through BZ casing (first and side walls). The tests will be performed at constant values of LL temperature, flow rate, magnetic field controlled with information system based on National Instruments equipment, isolating amplifiers, network router Ethernet and industrial computer. Loop temperature is regulated with heaters and heat exchanger. Parameters to be measured during the tests are the following: temperature distribution in different locations with thermocouples and inside the flow with micro thermocouples at swivel type probe, pressure/pressure difference with strain gauge transducers placed in the gas system of measuring tanks, LL flow rate with EFM and normal nozzle, electric potential distribution on mock-ups side walls.
Fig. 6. LLCB TBM mock-up design and general view.
LL loop together with mock-ups is placed on a moving platform to be inserted into the magnet. LIMITEF5 facility with superconducting magnet put into operation will be unique facility differing from MaPLE loop in UCLA [6] and PbLi loop in IPUL, Latvia [7] by allowing MHD/HT tests of large size TBM mock-ups in high magnetic fields (up to 5.5 T) with ITER like orientation of LL flow (poloidal) and magnetic field (toroidal). 3. Superconducting magnet According to the technical specification the LIMITEF5 magnetic system should produce uniform MF over a working zone with maximum height 800 mm (ITER poloidal coordinate). For that case uniform MF width should be 500 mm (radial coordinate) and length 250 mm (toroidal coordinate). In addition the following conditions should be satisfied: - MF with magnitude of 3–5.5 T should be normal to the poloidal/radial plane; - MF non-uniformity within working zone should not exceed 10%; - the system should give a possibility to insert TBM mock-ups in direction normal to poloidal/radial plane. Uniform MF zone has complex geometry and for smaller height allowed radial and toroidal dimensions could be higher. Calculations show that the mock-up with radial (580 mm) and toroidal (462 mm) dimensions equal to that of ITER TBM and poloidal dimension 550 mm will have main (axial) magnetic field component variation not exceeding 6.6% and ratio of radial to axial component not more than 6.3%. Our calculations for TBM in ITER location give 8% variation of toroidal component over TBM radial dimension and radial to toroidal components ratio around 8%. The version of split sectioned solenoid has been selected. The configuration of the windings along with the position of the working zone is shown in Fig. 7. Each winding consists of two sections – inner and outer made from NbTi. Two inner as well as two outer sections are connected in series forming two coils – inner and outer. Each coil has its own pair of current leads and could be supplied with current independently. The maximum MF in the working zone (up to 5.5 T) can be reached when coils work together (as a system).
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071
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Fig. 7. Schematic view of the LIMITEF5 magnetic system and position of the working zone (black – uniform MF zone with maximum height, red – uniform MF zone for TBM-like radial and toroidal dimensions). (For interpretation of the references to colour in this figure legend, the reader is referred to the web version of this article.)
low thermal conductive fiberglass supports and cooled by gaseous helium and liquid nitrogen respectively. Magnet power supply system consists of: - three-phase step-down transformer which has on the primary winding 380 V, 50 Hz and on the secondary winding – highcurrent three-phase low voltage 12 V, nominal current – 6200 A; - power rectifier to transform three-phase low voltage into direct voltage; - three independent constant-current sources with regulators; - bank of capacitors for short time supply in the regime of pulsewidth modulation; - supply line. Main parameters of the power supply system are: - two independent supply channels; - nominal current for each supply channel – 2500 A; - nominal output voltage – 12 V. 4. Summary
Fig. 8. General view of the SC magnet.
In this case coil currents should be adjusted. Some measures are taken to minimize heat generation and flux from magnetic system: NbTi busbars are used to connect the coil sections; a long (∼1 m) busbars made form G2 high temperature super conducting (HTSC) tapes connect low part of current leads and coil windings. Water cooled shield is placed on the inner cryostat surface to take the heat flux from the mock-up. General view of the magnet cryostat is given in Fig. 8. The overall “warm” zone of the cryostat has the following dimensions: diameter – 900 mm and length – 1600 mm. Cryostat vacuum vessel made of stainless steel analog of AISI 304 contains the vessel for liquid helium (helium bath) and superconducting coils. The cooling method chosen for the superconducting coils is based on the natural convection of liquid helium. To reduce the heat inflow to the cold mass cryostat has two thermal shields at 20 K and 80 K, which are located around the cold mass, fixated by
New facility for MHD and HT tests of liquid metal breeder blanket mock-ups in high MF is under construction now in RF as a part of R&D activity on LLCB TBM. The facility named LIMITEF5 includes: – lead-lithium loop with LL inventory ∼80 l, LL temperature – up to 350 ◦ C, LL flow rate – up to 4 m3 /h, pressure developed by EMP – up to 0.5 MPa; – superconducting magnet with MF induction up to 5.5 T and “warm” zone diameter – 900 mm and length – 1600 mm. MHD/HT tests of large size TBM mock-ups in high magnetic fields (∼5 T) with ITER like orientation of LL flow (poloidal) and magnetic field (toroidal) are planned. Status of the facility at the moment is the following: lead-lithium loop is commissioned and put into operation with d.c. magnet of ∼1 T, SC magnet cryostat and windings are manufactured, its assembling and commissioning are planned for 2018. References [1] L.M. Giancarli, M. Abdou, D.J. Campbell, V.A. Chuyanov, M.Y. Ahn, M. Enoeda, C. Pan, Y. Poitevin, E. Rajendra Kumar, I. Ricapito, Y. Strebkov, S. Suzuki, P.C. Wong, M. Zmitko, Overview of the ITER TBM program, Fusion Eng. Des. 87 (2012) 395–402. [2] S. Ranjithkumar, Deepak Sharma, Paritosh Chaudhuri, Chandan Danani, E. Rajendra Kumar, Istiyak Khan, Sujay Bhattacharya, K.N. Vyas, Engineering
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design and analysis of Indian LLCB TBM set, Fusion Eng. Des. 109–111 (Part B) (2015) 1581–1586, http://dx.doi.org/10.1016/j.fusengdes.2015.11.018. [3] A.Yu. Leshukov, Yu.S. Strebkov, I.R. Kirillov, I.V. Vitkovskiy, et al., Design development and analytical assessment of LLCB TBM in Russian Federation during 2012–2013, Fusion Eng. Des. 89 (2014) 1232–1240. [4] V.G. Kovalenko, A.Yu. Leshukov, S.N. Tomilov, A.V. Razmerov, Yu.S. Strebkov, M.N. Sviridenko, I.R. Kirillov, D.M. Obukhov, D.A. Pertsev, I.V. Vitkovsky, Progress in design development and research activity on LLCB TBM in Russian Federation, Fusion Eng. Des. 109–111 (Part A) (2016) 521–531, http://dx.doi. org/10.1016/j.fusengdes.2016.02.062.
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[5] I.R. Kirillov, D.M. Obukhov, L.G. Genin, V.G. Sviridov, N.G. Razuvanov, V.M. Batenin, I.A. Belyaev, I.I. Poddubnyi, IN.Yu. Pyatnitskaya, Buoyancy effects in vertical rectangular duct with coplanar magnetic field and single sided heat load, Fusion Eng. Des. 104 (2016) 1–8. [6] C. Courtessole, S. Smolentsev, T. Sketchley, M. Abdou, MHD PbLi experiments in MaPLE loop at UCLA, Fusion Eng. Des. 10 (2016) 9–111, 1016–1021. [7] S. Ivanov, A. Shishko, A. Flerov, E. Platacis, A. Romanchuks, A. Zik, MHD PbLi loop at IPUL, in: 9th PAMIR International Conference on Fundamental and Applied MHD, Riga, Latvia, 2014, pp. 76–80.
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071
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Contents lists available at ScienceDirect
Fusion Engineering and Design journal homepage: www.elsevier.com/locate/fusengdes
Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket A.Yu. Hon a , I.R. Kirillov a , K.A. Komov a , O.A. Kovalchuk a , A.A. Lancetov a , D.M. Obukhov a,∗ , D.A. Pertsev a , A.V. Pugachev b , I.Yu. Rodin a , E.R. Zapretilina a a b
JSC “NIIEFA” (D.V. Efremov Institute), 196641, Doroga na Metallostroy, 3, St. Peterburg, Russian Federation Forss Consulting Ltd, 195027, Magnitogorskaya Street, 51, lit. E, St. Petersburg, Russian Federation
h i g h l i g h t s • • • •
Overview of the new facility (LIMITEF5) is presented. The facility is aimed for MHD/HT tests of liquid metal breeder blanket mock-ups. The facility includes lead-lithium loop and superconducting magnet. Overview of the lead-lithium loop and superconducting magnet is given.
a r t i c l e
i n f o
Article history: Received 26 September 2016 Received in revised form 10 March 2017 Accepted 14 March 2017 Available online xxx Keywords: Liquid metal breeding blanket Superconducting magnet Lead-lithium loop MHD/HT test facility
a b s t r a c t This paper gives an overview of the new facility for MHD and heat transfer (HT) tests of liquid metal breeder blanket mock-ups in high magnetic field. The facility named LIMITEF5 is under construction now in JSC “NIIEFA” (D.V. Efremov Institute). The facility includes the lead-lithium (LL) loop passing through the warm aperture of the superconducting magnet. Superconducting magnet is planned to be put in operation in 2018 with the following characteristics: - magnetic field induction is up to 5.5 T; - dimensions of the magnet “warm” zone: diameter – 900 mm, length – 1600 mm; - winding design: low temperature superconducting split solenoid. LL loop consists of melting and feeding tanks; main loop with electromagnetic pump (EMP), electromagnetic flow meter, calibration nozzle, heat exchanger and blanket mock-up; LL impurities control and purification system containing oxygen sensor, plug indicator, cold trap, LL sampler. The details of the lead-lithium ceramic breeder test blanket module (LLCB TBM) mock-up for MHD/HT tests in magnetic field of ∼5 T which is under conceptual design are also given. © 2017 Elsevier B.V. All rights reserved.
1. Introduction Six Test Blanket Modules (TBMs) will be installed in ITER equatorial port to test DEMO relevant blanket options [1]. Lead-Lithium Ceramic Breeder (LLCB) TBM proposed by India [2] will be tested in port #2 of the ITER machine. India is a “leader” of LLCB TBM concept and responsible for delivery and subsequent tests of the IN LLCB TBM in ITER. Special-
∗ Corresponding author. E-mail address: [email protected] (D.M. Obukhov).
ists from Russian Federation are participating in design and R&D activity on IN LLCB TBM according to the technical program of cooperation between the leading research institutes of India (“leader”) and RF (“partner”). RF also has been developing the LLCB TBM design, with the aim to explore alternative design variants different from IN one in order to propose it for further application [3]. RF LLCB TBM design, similar in general to Indian LLCB TBM design for ITER, comprises the helium cooled load-bearing casing and tritium breeding zone with ceramic blocks (CB) and leadlithium (LL) ducts located inside the casing (Figs. 1,2). Tritium breeding zone (BZ) is arranged inside the TBM casing and surrounded by the internal surfaces of the first wall (FW), the casing
http://dx.doi.org/10.1016/j.fusengdes.2017.03.071 0920-3796/© 2017 Elsevier B.V. All rights reserved.
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071
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Fig. 3. LL flow scheme in the TBM. (numbers of LL ducts and CB are designated by digits).
Fig. 1. General view of RF LLCB TBM. 1-Be armor; 2-FW cramp; 3-electrical insulating pad; 4-purge-gas outlet branchpipe; 5-covers of load-bearing casing; 6-shear key; 7-helium coolant outlet branchpipe; 8-flexible support; 9-electrical connector; 10- helium coolant inlet branchpipe; 11-LL outlet branch-pipe; 12-LL inlet branch-pipe; 13- purge-gas inlet branchpipe.
Fig. 4. LL loop hydraulic scheme. 1- EMP, 2–EFM, 3–normal nozzle, 4–supply tank, 5–mechanical filter, 6–TBM mockup, 7–LL sampler, 8–cold trap with water cooling, 9–plug indicator, 10–air cooler, 11–valve, 12 – oxygen sensor.
covers and gas manifolds unit. LL is intended to cool the BZ, to moderate the thermonuclear neutrons and to breed tritium. LL flow scheme inside TBM is shown in Fig. 3. R&D activity on LLCB TBM includes MHD and heat transfer tests of the TBM mock-ups and LL technology aspects (eutectic preparation, impurities control and LL purification). At the initial stage mock-ups tests were performed on the NaK and mercury in magnetic field (MF) 1 T (see some details in [4,5]). To test TBM mock-ups on LL in close to ITER MF values new facility for MHD and heat transfer (HT) tests named LIMITEF5 (LIquid Metal TEst Facility, 5 T) is under construction now in JSC “NIIEFA”. 2. Lead-lithium loop Fig. 2. Poloidal cross-section of RF LLCB TBM. 1-partition between upward and downward LL flows; 2-LL upward flow zone; 3-LL downward flow zone; 4-bimetallic adapter; 5- CB; 6- FW; 7-upper LL header; 8covers of load-bearing casing; 9-purge-gas outlet branch-pipe; 10-helium coolant outlet branch-pipe; 11-flexible support; 12-stiffness ribs of helium manifold; 13-electrical connector; 14-helium coolant inlet branch-pipe; 15-LL outlet branchpipe; 16-LL inlet branch-pipe; 17-purge-gas inlet branch-pipe; 18-lower LL header.
LL loop for LIMITEF5 facility (Figs. 4 and 5) consists of melting and feeding tanks; main loop with electromagnetic pump (EMP), electromagnetic flow meters (EFM), normal nozzle for flow meter calibration, heat exchanger and blanket mock-up; bypasses for LL impurities control and purification system containing oxygen sensor, plug indicator, cold trap, LL sampler; gas-vacuum and data acquisition systems. Loop main parameters are the following: overall dimensions – 5.7(length) × 2.5(width) × 3.6(height) m; pipes
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071
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3
Table 1 LL chemical composition.
mass%
Li
Fe
Cu
Ag
As, Sb, Sn, Zn
Bi
Pb
0.64 ± 0.03
0.001
<0.0005
0.0008
<0.0005
0.005
the rest
Fig. 5. Overall view of LL loop (test section and magnet are on the rear right side).
material – analog of AISI 304 steel; main loop pipes diameter 48 × 4 mm, LL inventory ∼80 l, LL temperature – 250–350 ◦ C, LL flow rate – up to 4 m3 /h, pressure developed by EMP – up to 0.5 MPa. EMP is Annular Linear Induction Pump (ALIP) with power supply parameters 380 V, 180 A, 200 Hz. The EMP can output parameters of the ITER TBM (pressure developed, flow rate). Loop main components (except EMP made in NIIEFA) and LL for the facility were delivered by IPPE, Obninsk. LL chemical composition is shown in Table 1, eutectic melting temperature is 232 ± 1◦ . LL loop purification system consists of mechanical filters in the filling up branch and cold trap combined with magnetic trap in the by-pass branch. Plug indicator and LL sampler are placed in the by-pass branch as well. Obtaining dependencies of plug indicator plugging from LL temperature at its entrance and flow rate for different positions of plug throttle one can judge on impurities concentration in LL alloy. LL sampler provides for solid samples removal from the loop for chemical analysis. Electrochemical oxygen sensor is based on zirconium dioxide solid electrolyte. For MHD/HT tests of LLCB TBM a number of mock-ups are under design/manufacturing from simple to around natural size ones. Simple mock-ups consisting of one or several rectangular ducts are planned for preliminary tests of MHD and HT phenomena including buoyancy effects in vertical ducts placed in coplanar magnetic field of high intensity. One of such mock-ups (see Fig. 6) includes two parallel upward flow ducts divided in a number of sub-ducts in toroidal direction and one downward flow duct. Large size mockup will get all details of breeding zone (Fig. 2) with real toroidal and radial dimensions (462 × 580 mm) and around 1/3 of poloidal dimension. In this mock-up it is important to retain all peculiarities of TBM BZ and casing, since MHD characteristics are determined by induced electric currents closing through BZ casing (first and side walls). The tests will be performed at constant values of LL temperature, flow rate, magnetic field controlled with information system based on National Instruments equipment, isolating amplifiers, network router Ethernet and industrial computer. Loop temperature is regulated with heaters and heat exchanger. Parameters to be measured during the tests are the following: temperature distribution in different locations with thermocouples and inside the flow with micro thermocouples at swivel type probe, pressure/pressure difference with strain gauge transducers placed in the gas system of measuring tanks, LL flow rate with EFM and normal nozzle, electric potential distribution on mock-ups side walls.
Fig. 6. LLCB TBM mock-up design and general view.
LL loop together with mock-ups is placed on a moving platform to be inserted into the magnet. LIMITEF5 facility with superconducting magnet put into operation will be unique facility differing from MaPLE loop in UCLA [6] and PbLi loop in IPUL, Latvia [7] by allowing MHD/HT tests of large size TBM mock-ups in high magnetic fields (up to 5.5 T) with ITER like orientation of LL flow (poloidal) and magnetic field (toroidal). 3. Superconducting magnet According to the technical specification the LIMITEF5 magnetic system should produce uniform MF over a working zone with maximum height 800 mm (ITER poloidal coordinate). For that case uniform MF width should be 500 mm (radial coordinate) and length 250 mm (toroidal coordinate). In addition the following conditions should be satisfied: - MF with magnitude of 3–5.5 T should be normal to the poloidal/radial plane; - MF non-uniformity within working zone should not exceed 10%; - the system should give a possibility to insert TBM mock-ups in direction normal to poloidal/radial plane. Uniform MF zone has complex geometry and for smaller height allowed radial and toroidal dimensions could be higher. Calculations show that the mock-up with radial (580 mm) and toroidal (462 mm) dimensions equal to that of ITER TBM and poloidal dimension 550 mm will have main (axial) magnetic field component variation not exceeding 6.6% and ratio of radial to axial component not more than 6.3%. Our calculations for TBM in ITER location give 8% variation of toroidal component over TBM radial dimension and radial to toroidal components ratio around 8%. The version of split sectioned solenoid has been selected. The configuration of the windings along with the position of the working zone is shown in Fig. 7. Each winding consists of two sections – inner and outer made from NbTi. Two inner as well as two outer sections are connected in series forming two coils – inner and outer. Each coil has its own pair of current leads and could be supplied with current independently. The maximum MF in the working zone (up to 5.5 T) can be reached when coils work together (as a system).
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071
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Fig. 7. Schematic view of the LIMITEF5 magnetic system and position of the working zone (black – uniform MF zone with maximum height, red – uniform MF zone for TBM-like radial and toroidal dimensions). (For interpretation of the references to colour in this figure legend, the reader is referred to the web version of this article.)
low thermal conductive fiberglass supports and cooled by gaseous helium and liquid nitrogen respectively. Magnet power supply system consists of: - three-phase step-down transformer which has on the primary winding 380 V, 50 Hz and on the secondary winding – highcurrent three-phase low voltage 12 V, nominal current – 6200 A; - power rectifier to transform three-phase low voltage into direct voltage; - three independent constant-current sources with regulators; - bank of capacitors for short time supply in the regime of pulsewidth modulation; - supply line. Main parameters of the power supply system are: - two independent supply channels; - nominal current for each supply channel – 2500 A; - nominal output voltage – 12 V. 4. Summary
Fig. 8. General view of the SC magnet.
In this case coil currents should be adjusted. Some measures are taken to minimize heat generation and flux from magnetic system: NbTi busbars are used to connect the coil sections; a long (∼1 m) busbars made form G2 high temperature super conducting (HTSC) tapes connect low part of current leads and coil windings. Water cooled shield is placed on the inner cryostat surface to take the heat flux from the mock-up. General view of the magnet cryostat is given in Fig. 8. The overall “warm” zone of the cryostat has the following dimensions: diameter – 900 mm and length – 1600 mm. Cryostat vacuum vessel made of stainless steel analog of AISI 304 contains the vessel for liquid helium (helium bath) and superconducting coils. The cooling method chosen for the superconducting coils is based on the natural convection of liquid helium. To reduce the heat inflow to the cold mass cryostat has two thermal shields at 20 K and 80 K, which are located around the cold mass, fixated by
New facility for MHD and HT tests of liquid metal breeder blanket mock-ups in high MF is under construction now in RF as a part of R&D activity on LLCB TBM. The facility named LIMITEF5 includes: – lead-lithium loop with LL inventory ∼80 l, LL temperature – up to 350 ◦ C, LL flow rate – up to 4 m3 /h, pressure developed by EMP – up to 0.5 MPa; – superconducting magnet with MF induction up to 5.5 T and “warm” zone diameter – 900 mm and length – 1600 mm. MHD/HT tests of large size TBM mock-ups in high magnetic fields (∼5 T) with ITER like orientation of LL flow (poloidal) and magnetic field (toroidal) are planned. Status of the facility at the moment is the following: lead-lithium loop is commissioned and put into operation with d.c. magnet of ∼1 T, SC magnet cryostat and windings are manufactured, its assembling and commissioning are planned for 2018. References [1] L.M. Giancarli, M. Abdou, D.J. Campbell, V.A. Chuyanov, M.Y. Ahn, M. Enoeda, C. Pan, Y. Poitevin, E. Rajendra Kumar, I. Ricapito, Y. Strebkov, S. Suzuki, P.C. Wong, M. Zmitko, Overview of the ITER TBM program, Fusion Eng. Des. 87 (2012) 395–402. [2] S. Ranjithkumar, Deepak Sharma, Paritosh Chaudhuri, Chandan Danani, E. Rajendra Kumar, Istiyak Khan, Sujay Bhattacharya, K.N. Vyas, Engineering
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071
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design and analysis of Indian LLCB TBM set, Fusion Eng. Des. 109–111 (Part B) (2015) 1581–1586, http://dx.doi.org/10.1016/j.fusengdes.2015.11.018. [3] A.Yu. Leshukov, Yu.S. Strebkov, I.R. Kirillov, I.V. Vitkovskiy, et al., Design development and analytical assessment of LLCB TBM in Russian Federation during 2012–2013, Fusion Eng. Des. 89 (2014) 1232–1240. [4] V.G. Kovalenko, A.Yu. Leshukov, S.N. Tomilov, A.V. Razmerov, Yu.S. Strebkov, M.N. Sviridenko, I.R. Kirillov, D.M. Obukhov, D.A. Pertsev, I.V. Vitkovsky, Progress in design development and research activity on LLCB TBM in Russian Federation, Fusion Eng. Des. 109–111 (Part A) (2016) 521–531, http://dx.doi. org/10.1016/j.fusengdes.2016.02.062.
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[5] I.R. Kirillov, D.M. Obukhov, L.G. Genin, V.G. Sviridov, N.G. Razuvanov, V.M. Batenin, I.A. Belyaev, I.I. Poddubnyi, IN.Yu. Pyatnitskaya, Buoyancy effects in vertical rectangular duct with coplanar magnetic field and single sided heat load, Fusion Eng. Des. 104 (2016) 1–8. [6] C. Courtessole, S. Smolentsev, T. Sketchley, M. Abdou, MHD PbLi experiments in MaPLE loop at UCLA, Fusion Eng. Des. 10 (2016) 9–111, 1016–1021. [7] S. Ivanov, A. Shishko, A. Flerov, E. Platacis, A. Romanchuks, A. Zik, MHD PbLi loop at IPUL, in: 9th PAMIR International Conference on Fundamental and Applied MHD, Riga, Latvia, 2014, pp. 76–80.
Please cite this article in press as: A.Yu. Hon, et al., Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.071