The design of the prototype fast breeder reactor SC Chetal, V Balasubramaniyan, P Chellapandi, P Mohanakrishnan, ... Nuclear engineering and design 236 (7-8), 852-860, 2006 | 302 | 2006 |
Finite element analysis of fluid–structure interaction in pipeline systems B Sreejith, K Jayaraj, N Ganesan, C Padmanabhan, P Chellapandi, ... Nuclear Engineering and Design 227 (3), 313-322, 2004 | 141 | 2004 |
Dynamic stability of rectangular laminated composite plates RS Srinivasan, P Chellapandi Computers & structures 24 (2), 233-238, 1986 | 136 | 1986 |
CFD investigation of helical wire-wrapped 7-pin fuel bundle and the challenges in modeling full scale 217 pin bundle R Gajapathy, K Velusamy, P Selvaraj, P Chellapandi, SC Chetal Nuclear Engineering and Design 237 (24), 2332-2342, 2007 | 117 | 2007 |
A comparative CFD investigation of helical wire-wrapped 7, 19 and 37 fuel pin bundles and its extendibility to 217 pin bundle R Gajapathy, K Velusamy, P Selvaraj, P Chellapandi, SC Chetal Nuclear Engineering and Design 239 (11), 2279-2292, 2009 | 94 | 2009 |
Dynamic strain ageing, deformation, and fracture behavior of modified 9Cr–1Mo steel P Verma, GS Rao, P Chellapandi, GS Mahobia, K Chattopadhyay, ... Materials Science and Engineering: A 621, 39-51, 2015 | 75 | 2015 |
Thermal striping limits for components of sodium cooled fast spectrum reactors P Chellapandi, SC Chetal, B Raj Nuclear Engineering and Design 239 (12), 2754-2765, 2009 | 66 | 2009 |
Overview of pool hydraulic design of Indian prototype fast breeder reactor K Velusamy, P Chellapandi, SC Chetal, B Raj Sadhana 35, 97-128, 2010 | 61 | 2010 |
Sodium fast reactors with closed fuel cycle B Raj, P Chellapandi, PRV Rao CRC press, 2015 | 60 | 2015 |
CFD investigation of effect of helical wire-wrap parameters on the thermal hydraulic performance of 217 fuel pin bundle R Gajapathy, K Velusamy, P Selvaraj, P Chellapandi Annals of Nuclear Energy 77, 498-513, 2015 | 48 | 2015 |
Current status of fast reactors and future plans in India SC Chetal, P Chellapandi, P Puthiyavinayagam, S Raghupathy, ... Energy Procedia 7, 64-73, 2011 | 47 | 2011 |
Simultaneous development of flow and temperature fields in wire-wrapped fuel pin bundles of sodium cooled fast reactor NG Rasu, K Velusamy, T Sundararajan, P Chellapandi Nuclear Engineering and Design 267, 44-60, 2014 | 45 | 2014 |
A multi layer core catcher concept for future sodium cooled fast reactors AJ Sudha, K Velusamy, P Chellapandi Annals of Nuclear Energy 65, 253-261, 2014 | 42 | 2014 |
Testing and qualification of Control & Safety Rod and its drive mechanism of Fast Breeder Reactor VR Babu, R Veerasamy, S Patri, SIS Raj, SK Krovvidi, SK Dash, ... Nuclear Engineering and Design 240 (7), 1728-1738, 2010 | 42 | 2010 |
Study on JWL equation of state for the numerical simulation of near-field and far-field effects in underwater explosion scenario S Koli, P Chellapandi, LB Rao, A Sawant Engineering Science and Technology, an International Journal 23 (4), 758-768, 2020 | 41 | 2020 |
Development of stainless steels in nuclear industry: with emphasis on sodium cooled fast spectrum reactors history, technology and foresight R Baldev, U Kamachi Mudali, M Vijayalakshmi, MD Mathew, AK Bhaduri, ... Advanced Materials Research 794, 3-25, 2013 | 40 | 2013 |
Thermal hydraulic investigations of intermediate heat exchanger in a pool-type fast breeder reactor R Gajapathy, K Velusamy, P Selvaraj, P Chellapandi, SC Chetal, ... Nuclear Engineering and Design 238 (7), 1577-1591, 2008 | 40 | 2008 |
Decay heat removal in pool type fast reactor using passive systems U Parthasarathy, T Sundararajan, C Balaji, K Velusamy, P Chellapandi, ... Nuclear engineering and design 250, 480-499, 2012 | 39 | 2012 |
Progress in reliability of fast reactor operation and new trends to increased inherent safety B Merk, A Stanculescu, P Chellapandi, R Hill Applied Energy 147, 104-116, 2015 | 37 | 2015 |
Effect of dilution on micro hardness of Ni–Cr–B–Si alloy hardfaced on austenitic stainless steel plate for sodium-cooled fast reactor applications S Balaguru, V Murali, P Chellapandi, M Gupta Nuclear Engineering and Technology 52 (3), 589-596, 2020 | 36 | 2020 |