[1] Hemsworth R, Feist J, Hanada M, et al. Neutral beams
for ITER (invited) [J]. Rev. Sci. Instrum., 1996, 67(3):
1120-1125.
[2] Hemsworth R, Decamps H, Graaceffa J, et al. Status of
the ITER heating neutral beam system [J]. Nucl. Fusion,
2009, 49(4): 045006.
[3] Toigo V, Piovan R, Dal Bello S, et al. The PRIMA test
facility: SPIDER and MITICA test-beds for ITER neutral
beam injectors [J]. New J. Phys., 2019, 19: 085004.
[4] Zhuang G, Li G, Li J, et al. Progress of the CFETR design
[J]. Nucl. Fusion, 2019, 59: 112010.
[5] Li J, Wan Y. Present state of Chinese magnetic fusion
development and future plans [J]. J. Fusion Energy, 2019,
38(1): 113-124.
[6] Wan B, Ding S Y, Qian J P, et al. Physics design of
CFETR: determination of the device engineering
parameters [J]. IEEE Transactions on Plasma Science,2014, 43(3): 495-502.
[7] Song Y, Wu S, Li J, et al. Concept design of CFETR
tokamak machine [J]. IEEE Transactions on Plasma
Science, 2014, 43(3): 503-509.
[8] Heinemann B, Wunderlich D, Kraus W, et al.
Achievements of the ELISE test facility in view of the
ITER NBI [J]. Fusion Engineering and Design, 2019, 146:
455-459.
[9] Wunderlich D, Fantz U, Heinemann B, et al. Progress of
the ELISE test facility: towards one hour pulses in
hydrogen [J]. Nucl. Fusion, 2016, 56(10): 106004.
[10] Antoni V, Agostinetti P, Aprile D, et al. Physics design of
the injector source for ITER neutral beam injector
(invited) [J]. Rev. Sci. Instrum., 2014, 85(2): 02B128.
[11] Singh M, Boilson D, Hemsworth R, et al. Powerloads on
the front end components and the duct of the heating and
diagnostic neutral beam lines at ITER [C]. Fourth
International Symposium on Negative Ions, Beams and
Sources, NIBS, 2014.
[12] Dalla M, Sartori E, Blatchford P, et al. Design and R&D
for manufacturing the beamline components of MITICA
and ITER HNBs [J]. Fusion Engineering and Design,
2015, 96-97: 557-562.
[13] Pavei M, Dal Bello S, Groeneveld H, et al. R&D
activities for the design of the MITICA plasma driver
plate manufacturing process via explosion bonding
technique [J]. Fusion Engineering and Design, 2013,
88(9-10): 1664-1667.
[14] Dremel M, Day C, Hemsworth R, et al. Cryopump design
for the ITER heating neutral beam injector [J]. Nucl.
Fusion, 2009, 49(7): 075035.
[15] Liang L, Hu C, Xie Y, et al. Calculation of beam intensity
distribution for the neutral beam injection in EAST [J].
Plasma Science & Technology, 2011, 13(4): 502-505.
[16] Serianni G, Agostinetti P, Agostini M, et al, Neutralisation
and transport of negative ion beams: physics and
diagnostics [J]. New J. Phys., 2017, 19: 045003.
[17] Sonato P, Agostinetti P, Fantz U, et al. Conceptual design
of the beam source for the DEMO neutral beam injectors
[J]. New J. Phys., 2016, 18: 125002.
[18] Hemsworth R S, Boilson D, Blatchford P, et al. Overview
of the design of the ITER heating neutral beam injectors
[J]. New J. Phys., 2017, 19: 025005.
|