| Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code SP Saraswat, P Munsh, A Khanna, C Allison Journal of Nuclear Engineering and Radiation Science 4 (2), 021001, 2018 | 19 | 2018 |
| Linear stability analysis of RELAP5 two-fluid model in nuclear reactor safety results SP Saraswat, P Munshi, C Allison Annals of nuclear energy 149, 107720, 2020 | 17 | 2020 |
| Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4. 0 Code SP Saraswat, P Munshi, A Khanna, C Allison Journal of Nuclear Engineering and Radiation Science 3 (1), 014503, 2017 | 15 | 2017 |
| Characteristics and linear stability analysis of RELAP5 two-fluid model for two-component, two-phase flow SP Saraswat, P Munshi, C Allison Annals of Nuclear Energy 151, 107948, 2021 | 13 | 2021 |
| Ex-vessel loss of coolant accident analysis of ITER divertor cooling system using modified RELAP/SCADAPSIM/Mod 4.0 SP Saraswat, P Munshi, A Khanna, C Allison Journal of Nuclear Engineering and Radiation Science 3 (4), 041009, 2017 | 13 | 2017 |
| Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium D Ray, SP Saraswat, M Kumar, OP Singh, P Munshi Journal of Nuclear Engineering and Radiation Science 8 (2), 021501, 2022 | 11 | 2022 |
| Analysis of loss of heat sink for ITER divertor cooling system using modified RELAP/SCDAPSIM/MOD 4.0 SP Saraswat, D Ray, P Munshi, C Allison Journal of Nuclear Engineering and Radiation Science 5 (4), 042202, 2019 | 9 | 2019 |
| Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis) SP Saraswat, P Munshi, C Allison Journal of Nuclear Engineering and Radiation Science 7 (1), 011402, 2021 | 8 | 2021 |
| Progress towards the validation of SIMMER-III code model for lead-lithium water chemical interaction SP Saraswat, V Cossu, F Galleni, M Eboli, A Del Nevo, N Forgione Fusion Engineering and Design 193, 113819, 2023 | 7 | 2023 |
| Thermal-hydraulic safety assessment of full-scale ESBWR nuclear reactor design SP Saraswat, D Ray, G Mishra, D Yadav, VS Bhadouria, P Munshi, ... Journal of Nuclear Engineering and Radiation Science 8 (3), 031403, 2022 | 6 | 2022 |
| A Study of Transverse Buckling Effect on the Characteristics of Burnup Wave in a Diffusive Media D Ray, M Kumar, VS Bhadouria, SP Saraswat, P Munshi International Youth Nuclear Congress, 84-87, 2020 | 6 | 2020 |
| Thermal Hydraulic Analysis of in-Vessel Loss of Coolant Accident and Loss of Flow Accident of First Wall Helium Cooling System of Generalized LLCB TBS in ITER Using Modified … SP Saraswat, P Munshi, A Khanna, C Allison EasyChair, Kanpur, India, Paper, 14, 2020 | 4 | 2020 |
| Numerical Investigation of LIFUS5/Mod3 Series E Experiment Test 5.1 Towards Thermal-Hydraulic System Code" SIMMER-III" Validation SP Saraswat, F Galleni, M Eboli, N Forgione, A Del Nevo EasyChair, 2023 | 3 | 2023 |
| In-Vessel Loss of coolant accident assessment of a generalized LLCB TBS in ITER using RELAP/SCDAPSIM Code SP Saraswat, P Munshi, A Khanna, C Allison EasyChair, Kanpur, India, Paper, 2020 | 3 | 2020 |
| Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique SP Saraswat, N Forgione, ME Angiolini Journal of Nuclear Engineering and Radiation Science 10 (2), 021302, 2024 | 2 | 2024 |
| Thermal-hydraulics of loss of heat sink accident of Indian test blanket system in ITER SP Saraswat, P Munshi, A Khanna, C Allison International Youth Nuclear Congress (IYNC), 10-12, 2020 | 2 | 2020 |
| Investigation of non-hyperbolicity of conservation equations of RELAP/SCADAPSIM in nuclear reactor safety results by method of characteristics SP Saraswat, P Munshi, C Allison | 2 | 2018 |
| Validation and Verification of ASYST Code for Predicting Condensation Phenomena in Nuclear Reactor Safety Systems SP Saraswat, M Hassan, SM Osman, C Allison, Y Addad International Conference on Nuclear Engineering 88308, V010T13A005, 2024 | 1 | 2024 |
| A comprehensive examination of the linear and numerical stability aspects of the bubble collision model in the TRACE-1D two-fluid model applied to vertical disperse flow in a … SP Saraswat, Y Addad Nuclear Engineering and Technology, 2024 | 1 | 2024 |
| Micorwave nondestructive testing of reinforcement in concrete structures VS Bhadouria, SP Saraswat, G Mishra, P Munshi, MJ Akhter Proc. NDE Virtual Conf. Exhib., 10-12, 2020 | 1 | 2020 |
Prabhat MunshiIndian Institute of Technology KanpurEmail yang diverifikasi di iitk.ac.in