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Chandan Danani

Observed names: C DANANI, C Danani, C. Danani, Chandan DANANI, Danani C., Danani, Chandan
ORCID: 0009-0007-8994-7135
Observed ORCID: 0009-0007-8994-7135
OpenAlex ID: A5028611598
Preliminary design of Indian Test Blanket Module for ITER
2008 · E. Rajendra Kumar, C. Danani, et al. · Fusion Engineering and Design · 87
Status and progress of Indian LLCB test blanket systems for ITER
2012 · Paritosh Chaudhuri, E. Rajendra Kumar, et al. · Fusion Engineering and Design · 55
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
Engineering design and analysis of Indian LLCB TBM set
2015 · S. Ranjithkumar, Deepak Sharma, et al. · Fusion Engineering and Design · 26
Overview of design and thermal–hydraulic analysis of Indian solid breeder blanket concept
2013 · Paritosh Chaudhuri, Chandan Danani, et al. · Fusion Engineering and Design · 23
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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Thermal–hydraulic and thermo-structural analysis of first wall for Indian DEMO blanket module
2009 · Paritosh Chaudhuri, Chandan Danani, et al. · Fusion Engineering and Design · 21
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
Current status of design and engineering analysis of Indian LLCB TBM
2010 · Paritosh Chaudhuri, Chandan Danani, et al. · Fusion Engineering and Design · 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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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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Thermal-hydraulics of LLCB TBM under different ITER operational conditions
2016 · Paritosh Chaudhuri, S. Ranjithkumar, et al. · Fusion Engineering and Design · 11
Analysis of the reference accidental sequence for safety assessment of LLCB TBM system
2012 · Vilas Chaudhari, Ram Kumar Singh, et al. · Fusion Engineering and Design · 11
Novel mixed-oxide ceramic for neutron multiplication and tritium generation
2010 · Dakshinamoorthy Sathiyamoorthy, S.J. Ghanwat, et al. · Journal of Nuclear Materials · 11
Radioactivation analysis of 14 MeV neutron generator facility
2021 · H.L. Swami, S. Vala, 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
Preliminary Design of Central Solenoid of SST-2 and Demo
2016 · U. Prasad, R. Srinivasan, et al. · IEEE Transactions on Applied Superconductivity · 7
Thermal Conductivity of Composites of Beryllia and Lithium Titanate
2013 · B. N. Rath, S. J. Ghanwat, et al. · Journal of Materials Engineering and Performance · 7
Neutronic analysis of Indian helium-cooled solid breeder tritium breeding module for testing in ITER
2022 · H L SWAMI, Deepak SHARMA, et al. · Plasma Science and Technology · 5
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
Neutronic design optimization of ITER TBM port#2 bio-shield plug
2018 · H.L. Swami, Sanchit Sharma, et al. · Fusion Engineering and Design · 3
Works count: 42
Citation count: 473
H-index: 13
I10-index: 16
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