Publications
2025
Does Partitioning & Transmutation have a future as a nuclear waste management strategy?
Merk, B., Jain, L., Noorikalkhoran, O., Derrer-Merk, E., Cartland-Glover, G., Powell, L., . . . Patel, M. (n.d.). Does Partitioning & Transmutation have a future as a nuclear waste management strategy?. In T. Wetzel, W. Tromm, & J. Knebel (Eds.), Everlasting Energy - In Memoriam Prof. Dr.-Ing. Robert Stieglitz. KIT Scientific Publishing.
2024
From fishing village to atomic town and present: A grounded theory study.
Derrer-Merk, E., Jain, L., Noori-Kalkhoran, O., Taylor, R., Mike, D., Stain, T., & Merk, B. (2024). From fishing village to atomic town and present: A grounded theory study.. PloS one, 19(11), e0310144. doi:10.1371/journal.pone.0310144
Neutronics design of shutdown and control systems for a Zero Power Experiments of chloride-based molten salt fast reactor.
Jain, L., Noori-Kalkhoran, O., Powell, L., Jones, A., Aflyatunova, D., & Merk, B. (2024). Neutronics design of shutdown and control systems for a Zero Power Experiments of chloride-based molten salt fast reactor.. PloS one, 19(10), e0309928. doi:10.1371/journal.pone.0309928
On the Use of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 3; Radiation Damage
Noori-kalkhoran, O., Jain, L., & Merk, B. (n.d.). On the Use of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 3; Radiation Damage. Energies, 17(19), 4772. doi:10.3390/en17194772
A Draft Design of a Zero-Power Experiment for Molten Salt Fast Reactor Studies
Merk, B., Noori-kalkhoran, O., Jain, L., Aflyatunova, D., Jones, A., Powell, L., . . . Lange, C. (n.d.). A Draft Design of a Zero-Power Experiment for Molten Salt Fast Reactor Studies. Energies, 17(11), 2678. doi:10.3390/en17112678
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
Noori-kalkhoran, O., Jain, L., Powell, L., Jones, A., Aflyatunova, D., & Merk, B. (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. Energies, 17(6), 1475. doi:10.3390/en17061475
2023
New Waste Management Options Created by iMAGINE through Direct Operation on Spent Nuclear Fuel Feed
Merk, B., Detkina, A., Noori-kalkhoran, O., Jain, L., Litskevich, D., & Cartland-Glover, G. (n.d.). New Waste Management Options Created by iMAGINE through Direct Operation on Spent Nuclear Fuel Feed. Energies, 16(21), 7420. doi:10.3390/en16217420
iMAGINE - 7,500 Years of Sustainable Energy from Nuclear Waste
Jain, L., Merk, B., & Derrer-Merk, E. (2023). iMAGINE - 7,500 Years of Sustainable Energy from Nuclear Waste. (Vol. 79 (3), Autumn 2023 ed., pp. 10-12). [Science in Parliament, UK Parliamentary and Scientific Committee]. UK Parliamentary and Scientific Committee. Retrieved from https://www.scienceinparliament.org.uk/
iMAGINE-Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century
Merk, B., Litskevich, D., Detkina, A., Noori-kalkhoran, O., Jain, L., Derrer-Merk, E., . . . Cartland-Glover, G. (2023). iMAGINE-Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century. ENERGIES, 16(7). doi:10.3390/en16073120
2022
A HELIOS-Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium-Based Initial Core for iMAGINE
Merk, B., Detkina, A., Litskevich, D., Noori-kalkhoran, O., Jain, L., & Cartland-Glover, G. (2022). A HELIOS-Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium-Based Initial Core for iMAGINE. Energies, 15(24), 9638. doi:10.3390/en15249638
On the Employment of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 1: Thermophysical Properties and Core Criticality
Noori-kalkhoran, O., Litskevich, D., Detkina, A., Jain, L., Cartland-Glover, G., & Merk, B. (2022). On the Employment of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 1: Thermophysical Properties and Core Criticality. ENERGIES, 15(23). doi:10.3390/en15238865
2021
Convergence study of CMFD based acceleration schemes for multi-group transport calculations with fission source using fourier analysis
Jain, L., Mohanakrishnan, P., Karthikeyan, R., & Kannan, U. (2021). Convergence study of CMFD based acceleration schemes for multi-group transport calculations with fission source using fourier analysis. ANNALS OF NUCLEAR ENERGY, 160. doi:10.1016/j.anucene.2021.108314
Comparative studies of iterative methods for solving the "optimally diffusive" coarse mesh finite difference accelerated transport equation
Jain, L., Karthikeyan, R., & Kannan, U. (2021). Comparative studies of iterative methods for solving the "optimally diffusive" coarse mesh finite difference accelerated transport equation. ANNALS OF NUCLEAR ENERGY, 157. doi:10.1016/j.anucene.2021.108211
Convergence analysis of the non-linear CMFD schemes for acceleration of multi-group fixed source neutron transport calculations
Jain, L., Prabhakaran, M., Karthikeyan, R., & Kannan, U. (2021). Convergence analysis of the non-linear CMFD schemes for acceleration of multi-group fixed source neutron transport calculations. ANNALS OF NUCLEAR ENERGY, 153. doi:10.1016/j.anucene.2020.108041
2020
Theoretical investigation for optimizing the production of <SUP>223</SUP>Ra in research reactors for treatment of bone metastases
Jain, L., Thakare, S. V., & Gundra, K. (2020). Theoretical investigation for optimizing the production of <SUP>223</SUP>Ra in research reactors for treatment of bone metastases. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 325(3), 905-911. doi:10.1007/s10967-020-07159-9
DIAMOND - A Method of Characteristics neutron transport code using unstructured meshing
Jain, L., Karthikeyan, R., & Kannan, U. (2020). DIAMOND - A Method of Characteristics neutron transport code using unstructured meshing. ANNALS OF NUCLEAR ENERGY, 137. doi:10.1016/j.anucene.2019.107086