Explanipedia

Vacuum Brazing Route for Large-Scale Grid Manufacturing in Negative Ion Beam Generation Open

R. M. Pandey, Mahendrajit Singh, Jaydeep Joshi, M. Bandyopadhyay, Arun Chakraborty · 2025

Visible camera-based diagnostic to study negative ion beam profiles in ROBIN ion source Open

Sidharth Dash, Mainak Bandyopadhyay, Kaushal Pandya, M. Bhuyan, Ratnakar Yadav , et al. · 2024

Ensuring ion beam quality is of prime importance concerning the design of large-size neutral beam injectors(NBIs). Homogeneity, divergence, and beam energy are three crucial parameters defining beam quality. ROBIN(RF-Operated Beam source i…

Source performance optimization in Cesiated mode in ROBIN Open

K. Pandya, Mahendrajit Singh, M. Bhuyan, M. Bandyopadhyay, Himanshu Tyagi , et al. · 2024

ITER reference design, an inductively coupled single driver RF (100 kW, 1 MHz)-source ROBIN is operational at IPR, Gandhinagar. The first phase of the operation yielded H - current density of 22–25 mA/cm 2 and with electron to ion ratios >…

Design Development of Nuclear Grade Vacuum Vessel for Diagnostic Neutral Beam of Iter Open

Ashish Yadav, J. H. Joshi, Mahendrajit Singh, C. Rotti, Arun Chakraborty , et al. · 2024

Characterization of Hydrogen Plasma in an ECR based Large Volume Plasma Chamber Open

Shweta Sharma, Debaprasad Sahu, R. Narayanan, Satyananda Kar, M. Bandyopadhyay , et al. · 2022

Hydrogen plasma characterization was carried out in a large volume (dia∼ 1.0 m, h∼ 1.0 m) plasma chamber to evaluate the efficacy of production of uniform, large-area H - beam for fusion applications. Up to seven Compact ECR Plasma Sources…

The PRIMA Test Facility: SPIDER and MITICA test-beds for ITER neutral beam injectors Open

V. Toigo, R. Piovan, S. Dal Bello, E. Gaio, A. Luchetta , et al. · 2017

The ITER Neutral Beam Test Facility (NBTF), called PRIMA (Padova Research on ITER Megavolt Accelerator), is hosted in Padova, Italy and includes two experiments: MITICA, the full-scale prototype of the ITER heating neutral beam injector, a…

The ITER Neutral Beam Test Facility towards SPIDER operation Open

V. Toigo, S. Dal Bello, E. Gaio, A. Luchetta, R. Pasqualotto , et al. · 2017

SPIDER is one of two projects of the ITER Neutral Beam Test Facility under construction in Padova, Italy, at the Consorzio RFX premises. It will have a 100 keV beam source with a full-size prototype of the radiofrequency ion source for the…

Heating neutral beams for ITER: negative ion sources to tune fusion plasmas Open

Mahendrajit Singh, D. Boilson, A.R. Polevoi, T Oikawa, R. Mitteau · 2017

Neutral beam injection (NBI) based on a negative ion source is one of the basic heating and current drive systems designed for ITER required to reach its goals of the operation with high fusion power, P _fus ∼ 500 MW with fusion gain, Q = …

Overview of the design of the ITER heating neutral beam injectors Open

R. Hemsworth, D. Boilson, Peter Blatchford, M. Dalla Palma, G. Chitarin , et al. · 2017

The heating neutral beam injectors (HNBs) of ITER are designed to deliver 16.7 MW of 1 MeV D ^0 or 0.87 MeV H ^0 to the ITER plasma for up to 3600 s. They will be the most powerful neutral beam (NB) injectors ever, delivering higher energy…

Heating Neutral Beams for ITER: Present Status Open

Mahendrajit Singh, D. Boilson, R. Hemsworth, J. Chareyre, Hans Decamps , et al. · 2016

—The heating neutral beam (HNB) systems at ITER are designed to inject a total of 33 MW of either 1 MeV D0 or 870 keV H0 beams into the ITER plasma using two injectors with a possible addition of a third injector later to increase the inje…

Final design of the beam source for the MITICA injector Open

D. Marcuzzi, P. Agostinetti, M. Dalla Palma, M. De Muri, G. Chitarin , et al. · 2015

The megavolt ITER injector and concept advancement experiment is the prototype and the test bed of the ITER heating and current drive neutral beam injectors, currently in the final design phase, in view of the installation in Padova Resear…

Powerloads on the front end components and the duct of the heating and diagnostic neutral beam lines at ITER Open

Mahendrajit Singh, D. Boilson, R. Hemsworth, F. Geli, J. Graceffa , et al. · 2015

The heating and current drive beam lines (HNB) at ITER are expected to deliver ∼16.7 MW power per beam line for H beams at 870 keV and D beams at 1 MeV during the H-He and the DD/DT phases of ITER operation respectively. On the other hand …

Benchmark of numerical tools simulating beam propagation and secondary particles in ITER NBI Open

E. Sartori, P. Veltri, E. D. Dlougach, R. Hemsworth, G. Serianni , et al. · 2015

Injection of high energy beams of neutral particles is a method for plasma heating in fusion devices. The ITER injector, and its prototype MITICA (Megavolt ITER Injector and Concept Advancement), are large extrapolations from existing devi…

Mahendrajit Singh YOU? Author Swipe