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H.L. Swami

Observed names: H L SWAMI, H L Swami, H. L. Swami
ORCID: 0000-0001-9942-2489
Observed ORCID: 0000-0001-9942-2489
OpenAlex ID: A5047072318
Progress in engineering design of Indian LLCB TBM set for testing in ITER
2014 · Paritosh Chaudhuri, S. Ranjithkumar, et al. · Fusion Engineering and Design · 47
Neutronic performance of Indian LLCB TBM set conceptual design in ITER
2016 · H.L. Swami, A.K. Shaw, et al. · Fusion Engineering and Design · 21
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Activation characteristics of candidate structural materials for a near-term Indian fusion reactor and the impact of their impurities on design considerations
2018 · H L SWAMI, C DANANI, et al. · Plasma Science and Technology · 20
Tritium breeding mock-up experiments containing lithium titanate ceramic pebbles and lead irradiated with DT neutrons
2015 · Shrichand Jakhar, M. Abhangi, et al. · Fusion Engineering and Design · 20
Development and performance of a 14-MeV neutron generator
2020 · S.J. Vala, M. Abhangi, et al. · Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment · 17
Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term Indian DEMO fusion reactor
2020 · H. L. Swami, Deepak Sharma, et al. · International Journal of Energy Research · 16
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Neutron emission characterization of IPR 14 MeV neutron generator
2024 · Mitul Abhangi, S. Vala, et al. · Fusion Engineering and Design · 15
A neutronic experiment to support the design of an Indian TBM shield module for ITER
2019 · H L SWAMI, M ABHANGI, et al. · Plasma Science and Technology · 14
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Occupational radiation exposure control analyses of 14 MeV neutron generator facility: A neutronic assessment for the biological and local shield design
2020 · H.L. Swami, S. Vala, et al. · Nuclear Engineering and Technology · 13
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Physics design of 14 MeV neutron generator facility at the Institute for Plasma Research
2023 · H L SWAMI, S VALA, et al. · Plasma Science and Technology · 10
Tritium-titanium target degradation due to deuterium irradiation for DT neutron production
2023 · M. Rajput, H.L. Swami, et al. · Nuclear Fusion · 8
Radioactivation analysis of 14 MeV neutron generator facility
2021 · H.L. Swami, S. Vala, et al. · Fusion Engineering and Design · 8
Progress in the integration of Test Blanket Systems in ITER equatorial port cells and in the interfaces definition
2012 · R. Pascal, S. Beloglazov, et al. · Fusion Engineering and Design · 8
Multi-model quantification of defects in irradiated lithium titanate
2019 · Chandan Danani, H.L. Swami, et al. · Fusion Engineering and Design · 7
Mechanical and electrical performance of glass fiber reinforced plastic insulation for cryogenic application in fusion magnet irradiated in fast breeder reactor
2024 · Rajiv Sharma, V.L. Tanna, et al. · Fusion Engineering and Design · 5
Deuterium ion irradiation impact on the current-carrying capacity of DI-BSCCO superconducting tape
2022 · M. Rajput, H.L. Swami, et al. · Nuclear Engineering and Technology · 5
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One-dimensional nuclear design analyses of the SST-2
2019 · Chandan Danani, Deepak Aggarwal, et al. · Pramana · 5
Neutronic design of Indian LLCB TBM
2012 · M.V. Gathibandhe, R.A. Agrawal, et al. · Fusion Engineering and Design · 5
A case for gross electricity producing compact fusion pilot plants
2024 · P.N. Maya, S.P. Deshpande, et al. · Nuclear Fusion · 4
Thermal Analysis of HCSB Blanket Concept for a Moderate Sized Tokamak Fusion Reactor
2024 · Piyush Prajapati, Shishir Deshpande, et al. · Fusion Science & Technology · 4
Neutronic simulation of medical radioisotope 99Mo and 177Lu production in IPR 14 MeV neutron generator facility
2023 · H.L. Swami, A. Saxena, et al. · Applied Radiation and Isotopes · 4
Simulation of silicon etching in NF3 plasma reactor
2023 · H L Swami, V Mehta, et al. · Pramana · 3
Neutronic design optimization of ITER TBM port#2 bio-shield plug
2018 · H.L. Swami, Sanchit Sharma, et al. · Fusion Engineering and Design · 3
Design and analysis of mixed bed solid breeder blanket with titanium berrylide as neutron multiplier
2024 · Deepak Sharma, Paritosh Chaudhuri, et al. · Applied Thermal Engineering · 2
Conceptual Design of Solid Breeder Blankets for Fusion Pilot Plants
2026 · Deepak Sharma, Paritosh Chaudhuri, et al. · IEEE Transactions on Plasma Science · 1
Works count: 34
Citation count: 269
H-index: 10
I10-index: 10
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