| Progress in engineering design of Indian LLCB TBM set for testing in ITER P Chaudhuri, S Ranjithkumar, D Sharma, C Danani, HL Swami, ... Fusion Engineering and Design 89 (7-8), 1362-1369, 2014 | 51 | 2014 |
| Tritium breeding mock-up experiments containing lithium titanate ceramic pebbles and lead irradiated with DT neutrons S Jakhar, M Abhangi, S Tiwari, R Makwana, V Chaudhari, HL Swami, ... Fusion Engineering and Design 95, 50-58, 2015 | 23 | 2015 |
| Neutronic performance of Indian LLCB TBM set conceptual design in ITER HL Swami, AK Shaw, AN Mistry, C Danani Fusion Engineering and Design 113, 71-81, 2016 | 21 | 2016 |
| Activation characteristics of candidate structural materials for a near-term Indian fusion reactor and the impact of their impurities on design considerations HL SWAMI, C DANANI, AK SHAW Plasma Science and Technology 20 (6), 065602, 2018 | 14 | 2018 |
| A neutronic experiment to support the design of an Indian TBM shield module for ITER HL SWAMI, M ABHANGI, S SHARMA, S TIWARI, AN MISTRY, V VASAVA, ... Plasma Science and Technology 21 (6), 065601, 2019 | 10 | 2019 |
| Development and performance of a 14-MeV neutron generator SJ Vala, M Abhangi, R Kumar, S Tiwari, R Kumar, HL Swami, ... Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2020 | 9 | 2020 |
| Occupational Radiation Exposure Control Analyses of 14 MeV Neutron Generator Facility: A neutronic assessment for the biological and local shield design HL Swami, S Vala, M Abhangi, R Kumar, C Danani, R Kumar, ... Nuclear Engineering and Technology, 2020 | 9 | 2020 |
| Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term Indian DEMO fusion reactor HL Swami, D Sharma, AN Mistry, C Danani, P Chaudhuri, R Srinivasan International Journal of Energy Research 2020, 1-10, 2020 | 8 | 2020 |
| Progress in the integration of Test Blanket Systems in ITER equatorial port cells and in the interfaces definition R Pascal, S Beloglazov, S Bonagiri, L Commin, P Cortes, LM Giancarli, ... Fusion Engineering and Design 87 (7-8), 1347-1351, 2012 | 7 | 2012 |
| Multi-model quantification of defects in irradiated lithium titanate C Danani, HL Swami, P Chaudhuri, A Mutzke, R Schneider, M Warrier Fusion Engineering and Design 140, 92-96, 2019 | 6 | 2019 |
| Neutronic design of Indian LLCB TBM MV Gathibandhe, RA Agrawal, KN Vyas, C Danani, HL Swami, ... Fusion Engineering and Design 87 (7-8), 1161-1165, 2012 | 6 | 2012 |
| Radioactivation analysis of 14 MeV neutron generator facility HL Swami, S Vala, M Abhangi, R Kumar, C Danani, R Kumar, ... Fusion Engineering and Design 165 (April 2021), 112229, 2021 | 4 | 2021 |
| One-dimensional nuclear design analyses of the SST-2 C Danani, D Aggarwal, HL Swami, V Menon, R Srivatsava, A Sharma, ... Pramana 92, 1-7, 2019 | 4 | 2019 |
| Experimental study of neutron irradiation effect on elementary semiconductor devices using Am-Be neutron source HL Swami, R Rathod, TS Rao, M Abhangi, S Vala, C Danani, ... Indian Journal of Pure & Applied Physics (IJPAP) 59 (1), 40-47, 2021 | 3 | 2021 |
| Neutronic design optimization of ITER TBM port# 2 bio-shield plug HL Swami, S Sharma, AK Shaw, C Danani Fusion Engineering and Design 137, 49-55, 2018 | 3 | 2018 |
| Physics design of 14 MeV neutron generator facility at the Institute for Plasma Research HL SWAMI, S VALA, M RAJPUT, M ABHANGI, R KUMAR, A SAXENA, ... Plasma Science and Technology 25 (12), 125602, 2023 | 2 | 2023 |
| Deuterium ion irradiation impact on the current-carrying capacity of DI-BSCCO superconducting tape M Rajput, HL Swami, R Kumar, A Bano, S Vala, M Abhangi, U Prasad, ... Nuclear Engineering and Technology 54 (7), 2586-2591, 2022 | 2 | 2022 |
| Nuclear Analyses of Indian LLCB Test Blanket System in ITER HL Swami, AK Shaw, C Danani, P Chaudhuri Journal of Physics: Conference Series 823 (1), 012066, 2017 | 2 | 2017 |
| Tritium-titanium target degradation due to deuterium irradiation for DT neutron production M Rajput, HL Swami, S Vala, M Abhangi, R Kumar, R Kumar Nuclear Fusion 63 (6), 066033, 2023 | 1 | 2023 |
| Neutronic analysis of Indian helium-cooled solid breeder tritium breeding module for testing in ITER HL Swami, D Sharma, C Danani, P Chaudhari, R Srinivasan, R Kumar Plasma Science and Technology 24 (6), 065601, 2022 | 1 | 2022 |
