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Lakshay Jain
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DIAMOND–A Method of Characteristics neutron transport code using unstructured meshing
L Jain, R Karthikeyan, U Kannan
Annals of Nuclear Energy 137, 107086, 2020
72020
Comparative studies of iterative methods for solving the “optimally diffusive” coarse mesh finite difference accelerated transport equation
L Jain, R Karthikeyan, U Kannan
Annals of Nuclear Energy 157, 108211, 2021
62021
Theoretical investigation for optimizing the production of 223Ra in research reactors for treatment of bone metastases
L Jain, SV Thakare, K Gundra
Journal of Radioanalytical and Nuclear Chemistry 325 (3), 905-911, 2020
52020
iMAGINE—Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century
B Merk, D Litskevich, A Detkina, O Noori-kalkhoran, L Jain, E Derrer-Merk, ...
Energies 16 (7), 3120, 2023
42023
Convergence study of CMFD based acceleration schemes for multi-group transport calculations with fission source using fourier analysis
L Jain, P Mohanakrishnan, R Karthikeyan, U Kannan
Annals of Nuclear Energy 160, 108314, 2021
42021
Convergence analysis of the non-linear CMFD schemes for acceleration of multi-group fixed source neutron transport calculations
L Jain, M Prabhakaran, R Karthikeyan, U Kannan
Annals of Nuclear Energy 153, 108041, 2021
32021
Acceleration of neutron transport calculations using Krylov subspace iterations and optimally diffusive coarse mesh finite difference method
L Jain, R Karthikeyan, U Kannan
The Proceedings of the International Conference on Nuclear Engineering …, 2019
32019
On the employment of a chloride or fluoride salt fuel system in advanced molten salt reactors, part 1: thermophysical properties and core criticality
O Noori-kalkhoran, D Litskevich, A Detkina, L Jain, G Cartland-Glover, ...
Energies 15 (23), 8865, 2022
22022
Multi-Grid Acceleration Scheme for Neutron Transport Calculations using Optimally Diffusive CMFD Method
L Jain, R Karthikeyan, U Kannan
22018
Negligible time-consuming RC5 remote decoding technique
TB Singha, L Jain, B Kant
2014 International Conference on Computer Communication and Informatics, 1-4, 2014
22014
New Waste Management Options Created by iMAGINE through Direct Operation on Spent Nuclear Fuel Feed
B Merk, A Detkina, O Noori-kalkhoran, L Jain, D Litskevich, ...
Energies 16 (21), 7420, 2023
12023
New Waste Management Options Created by iMAGINE through Direct Operation on SNF Feed
BR Merk, A Detkina, O Noori-kalkhoran, L Jain, D Litskevich, ...
Preprints, 2023
12023
A HELIOS-Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium-Based Initial Core for iMAGINE
B Merk, A Detkina, D Litskevich, O Noori-Kalkhoran, L Jain, ...
Energies 15 (24), 9638, 2022
12022
Interrupt based RC5 Remote-decoding using 8051 μc
L Jain, TB Singha, B Kant
Journal of Artificial Intelligence 6, 187-190, 2013
12013
A Draft Design of a Zero-Power Experiment for Molten Salt Fast Reactor Studies
B Merk, O Noori-kalkhoran, L Jain, D Aflyatunova, A Jones, L Powell, ...
Energies 17 (11), 2678, 2024
2024
On the employment of a chloride or floride salt fuel system in advanced molten salt reactors, Part 2; Core inventory, fuel burnup, and salt clean-up system
O Noori-kalkhoran, L Jain, L Powell, A Jones, D Aflyatunova, B Merk
Energies 17 (6), 1475, 2024
2024
Analysis of PWR Assemblies with Burnable Absorbers using the Code DIAMOND
L Jain, R Karthikeyan, U Kannan
Proceedings of the 22nd National Symposium on Radiation Physics, 2019
2019
Production possibility of 223Ra in Dhruva reactor for treatment of bone metastases
SV Thakare, L Jain, K Gundra
Proceedings of the fifteenth international conference on modern trends in …, 2019
2019
DEVELOPMENT AND VALIDATION OF METHOD OF CHARACTERISTICS BASED CODE FOR SOLVING NEUTRON TRANSPORT EQUATION FOR A TWO-DIMENSIONAL PIN CELL USING DELAUNAY TRIANGULATION
L Jain
2016
Study of Neutron Transport in Heterogeneous Assemblies using Method of Characteristics Coupled with Delaunay Triangulation
L JAIN
Mumbai, 0
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Articles 1–20