The ITER Neutral Beam Test Facility. Design Overview. European Tasks ref. TW3-THHN-IITF1 ( ) TW4-THHN-IITF2 ( ) Jean-Jacques Cordier

Transcription

1 The ITER Neutral Beam Test Facility Design Overview European Tasks ref. TW3-THHN-IITF1 ( ) TW4-THHN-IITF2 ( ) Jean-Jacques Cordier on behalf of EU Associations involved in the study 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 1

2 The ITER Neutral Beam Test Facility Outline Main objectives and context of the study Design of the Test Facility Description of the General Infrastructure Auxiliaries : Cryosystem and Cooling plant Summary 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 2

3 The ITER Neutral Beam Test Facility - Introduction NBTF : Context and Objectives There is a general appreciation within the NB community, that an ITER-scale NB test facility will be required to demonstrate high voltage acceleration at ITER-relevant currents. The facility would permit all elements of the ITER NB system to be tested at essentially full scale and at pulse lengths commensurate with those required for ITER (~ 1 hour). The test facility would be constructed on the territory of the host Party. The first injector would be transferred to ITER site (when qualification is achieved on the NBTF). [EFDA] Operation plan phase 1 : qualification of the ITER source, then accelerator, then Beam Line Components up to full 40 MW power (short pulses mainly). phase 2 : qualification of the ITER NB injector during long pulses (3,600 s) at full power (84 pulses in H mode, then 84 pulses in D mode) 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 3

4 The ITER Neutral Beam Test Facility - Schedule Phase 1 Phase 2 [ ENEA-RFX input ] 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 4

5 nuclear and tritium analysis EU Task Organisation UKAEA SINGAP integration test bed general infrastructure cryogenic & cooling systems remote in-vessel inspection CEA EFDA CSU ITER IT nuclear analysis preliminary safety report ENEA Frascati RFX Design integration, Operation plan IPP RF source diagnostics design first injector design revision SINGAP source design power supply buildings ENEA RFX FZK CIEMAT cryopump design forepumping system correction coils 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 5

6 The ITER Neutral Beam Test Facility - Specifications Design specifications : The ITER reference beam source, BSV, HV bushing and beam line components, have to be integrated in the Test Facility MAMuG or Singap Bushing calorimeter RID neutraliser Beam Source Vessel (BSV) MAMuG or Singap Source 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 6

7 The ITER Neutral Beam Test Facility - Design correction coils NBTF Global Design top port flange and diagnostics openings ITER bushing beam line vessel (47t) 5m width, 4.5m height BLCs Hydraulic connections BLV support ITER reference beam source vessel (30t) 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 7

8 The ITER Neutral Beam Test Facility - Design Test facility cross section Top port Beam source neutraliser 4th IAEA technical meeting cryopump 9-11 may 05 RID - J.J. Cordier - calorimeter NBTF Design Overview Man access for inspection 8

9 Test bed phase I et phase II configuration Phase I ( 3 years) set of diagnostics qualification at low then high power, H - then D - (limited at full power) low level activation Phase II : ITER full configuration (6 months) long pulses (3600s), high power (40 MW) H - then D - 2 split halves cryopump ITER reference cryopump 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 9

10 The ITER Neutral Beam Test Facility - Design Hydraulic Connections of Beam Line Components flanges bolting and tightness reliability, have to be demonstrated (proof of principle, through representative mock-up) External bolted connection of BLCs : neither welding nor cutting [RFX input] metallic seal and single bolted flange (water tightness) easy maintenance, limited in-situ operations 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 10

11 The ITER Neutral Beam Test Facility - maintenance Mixed Vertical Horizontal Access (MVH) ITER relevant maintenance of the source from rear side vertical maintenance during Phase I horizontal maintenance during phase II 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 11

12 The ITER Neutral Beam Test Facility - inspection In-vessel viewing system : Articulated Inspection Arm Axe 4 Axe 3 Axe 2 Axe 1 Axe 6 Axe segments robot, payload : 10 kg Inspection is performed under vacuum (BLCs at 350K and cryopump at 80K) Source and Cryopump Conditioning is preserved Visual inspection : Ground Electrode, Neutraliser, RID Calorimeter (open configuration) and Cryopump 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 12

13 ITER Neutral Beam Test Facility - infrastructure Experimental Hall concrete structure 1.8m thick walls 15 m HV deck TL1 TL2 50 t 20 m 2m Pit 8 m 37 m [ ENEA-RFX & CEA input ] 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 13

14 ITER Neutral Beam Test Facility - infrastructure Experimental Hall : man access platforms Upper access to BLV, BLCs, Bushing Diagnostics maintenance area 4th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 14

15 ITER Neutral Beam Test Facility - Infrastructure HV deck TL1 Power supply (not shown) TL2 facility Forepumping and gas Helium tank Cryosystem primary heat transfer system Heat rejection system 60 MW cooling tower [ ENEA-RFX & CEA input ] Basin(s) 430 m 3 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 15

16 ITER Neutral Beam Test Facility - Cryosystem Cryopump Loading [ FZK input ] Operating modes Cryopanels Shields and Baffles Remarks Stand By T in = 4.5 K T out = 6.5 K Q 0 = 40 W 65 K< T in < 80 K T out = 90 K Q 0 = 18 kw Beam Line Components T = 350 K NBI operation Pulses T in = 4.5 K T out = 6.5 K Q 1 = 160 W 65 K< T in < 80 K T out = 90 K Q 1 = 22 kw short pulse (20 s) (100 pulses/shift) long pulse (3600 s) (2 pulses/shift) T = 350 K Outgasing (H 2, D2) Cryopanels Regeneration to 100 K T w = 100 K T w > 100 K Losses ~ 30 kw Gas conduction Gap between walls 100 mm < d < 200 mm Forepumping capacity (roots) Cryopanels Regeneration Up to 470 K T w = 470 K (T w ~ 470 K) are fed in series with Cryopanels outlet Shields & Baffles inlet 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 16

17 Process Flow Diagram of the NBTF Cryoplant 4.5K Industrial Refrigerator 500 W kg/s 0.4 MPa E 1 E 2 E 3 E 4 E 5 T 1 T 2 90 m 3 Warm GHe storage Compressor 280 kw Heat exchanger E 6 Cold Valve Box 1000 LHe tank cryopump heater Turbo-expander 25 kw 80K Refrigerator (Brayton cycle) kg/s, 1.8 MPa 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 17

18 Cryosystem K cryopanels behaviour Operating modes Refrigerator Duration Response K Cool down Turbo-expander 300 K to 80 K 80 K to 4.5 K Cool down after a 100 K regeneration 100 K to 4.5 K Warm up 80 K to 300 K Regeneration 300 K to 470 K Cooling after 470 K regeneration 470 K to 300 K 1 kw 1 kw SCHe masse flow 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview h 1.3 h K 550 s Heating power 10 kw 40 kw GHe masse flow 2.5 h ~ 1 h K 0.5 h hours 30 K 300 K hours sec K sec

19 Cooling Plant Primary Heat Transfer System NB Test Facility - Characteristics of the PHTS Component Inlet Temp. ( C) Average Outlet Temp. ( C) Max outlet Temp.( C) Saturation Pressure (MPa) Inlet Pressure (MPa) In Vessel Pressure drop (MPa) Outlet Pressure (MPa) Neutraliser leading edge Neutraliser Panels RID Calorimeter Ion Source, Filaments Acceleration grid, Extractor, Plasma grid NBTF: A global high pressure drop is preferred to a Calorimeter surpressor : Inlet pressure 2.65 MPa (higher flexibility, adjustment of required flow rates) 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 19

20 Cooling Plant Primary Heat Transfer System NB Test Facility - PHTS Flow diagram G N2 Pneumatic Pressurizer Main Pump Buffer Tank Filter Auxiliary Hall 1250 m 3 /h PHTS (Close to the ITER reference PFD) Back up Pump HRS m 3 /h Flowmeters CHWS 3 F F 58 m 3 /h 20 C 50 C F 80 C HRS 1 CVCS NB Test Facility Source BSV Accelerators, Extractor High Voltage Components Neutraliser RID Calorimeter Low Voltage Components BLV Flow control valves Drain Tank 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 20

21 Cooling Plant Heat Rejection System HRS Characteristics (NBTF secondary loop) Tinlet Toutlet P (kw) Q (m max ( C) max ( C) 3 /s) Q (m 3 /h) Power Supplies Acceleration Grid Power Supplies Inverters Ion Source Power Supply rectifiers inside the HVD Transformers inside the HVD Devices located outside the HVD Ground Related Power Supplies Cryo Compressors PHTS HE HE CHWS HE HRS Total th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 21

22 Cooling Plant Heat Rejection System Flow Diagram of the HRS HE1 50 MW 70 C 1217 m3/h DN m3/h DN C Cooling Tower 60 MW Basin 35 C HRS system is built for steady state operation HE2 4 MW 50 C 228 m3/h DN m3/h DN m3/h DN m3/h DN m3/h DN400 Filter Fore Pumping Power Supplies CCWS 1.9 MW 86 m3/h 17 C DN m3/h HE3 DN MW Cryo Building HVAC 600 kw 42 C 229 m3/h DN150 Compressors 280 kw Raw water 60 m3/h DN80 20 C 40 C 11.4 C Centrifugal Compressor 3.3 MW CHWS 511 m3/h DN250 6 C 640 m3/h DN250 Pressuriser 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 22

23 The ITER Neutral Beam Test Facility Summary A dedicated beam line vessel is designed for the NBTF, that allows easy man access, integration of diagnostics and in-vessel viewing inspection that would operate under vacuum Maintenance of NB injector components is optimised Conceptual design of the General Infrastructure is completed Designs of cryosystem and cryoplant fulfil the required NBTF specifications for both short (20s) and long (3600s) pulses at full 40 MW power 4 th IAEA technical meeting 9-11 may 05 - J.J. Cordier - NBTF Design Overview 23