1. 3D space-time analysis of ATWS in compact high temperature reactor with integrated thermal-hydraulic model in code ARCH-TH. (December 2017) Authors: Dwivedi, D.K.; Gupta, Anurag; Kannan, Umasankari Journal: Annals of nuclear energy Issue: Volume 110(2017:Dec.) Page Start: 306 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
2. A Diffusion Monte Carlo–Based Algorithm for Estimation of Higher Modes of a Reactor. (2nd September 2019) Authors: Srivastava, Argala; Singh, K. P.; Mallick, Amod Kishore; Kannan, Umasankari; Degweker, S. B. Journal: Nuclear science and engineering Issue: Volume 193:Number 9(2019) Page Start: 1044 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
3. A hybrid method for reactor core simulations employing finite difference and polynomial expansion with improved treatment of transverse leakage. (September 2019) Authors: Ray, Sherly; Degweker, S.B.; Kannan, Umasankari Journal: Annals of nuclear energy Issue: Volume 131(2019) Page Start: 102 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
4. Analysis for the use of thorium based fuel in LWRs. (1st September 2022) Authors: Raj, Devesh; Kannan, Umasankari Journal: Annals of nuclear energy Issue: Volume 174(2022) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
5. Analysis of Integral Experiment of the AHWR Critical Facility with Diffusion-Based Monte Carlo Method. (3rd April 2023) Authors: Srivastava, Argala; Bhandari, Deep; Singh, K. P.; Kannan, Umasankari Journal: Nuclear science and engineering Issue: Volume 197:Number 4(2023) Page Start: 703 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
6. Comparative studies of iterative methods for solving the "optimally diffusive" coarse mesh finite difference accelerated transport equation. (July 2021) Authors: Jain, Lakshay; Karthikeyan, Ramamoorthy; Kannan, Umasankari Journal: Annals of nuclear energy Issue: Volume 157(2021) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
7. Convergence analysis of the non-linear CMFD schemes for acceleration of multi-group fixed source neutron transport calculations. (April 2021) Authors: Jain, Lakshay; Prabhakaran, Mohanakrishnan; Karthikeyan, Ramamoorthy; Kannan, Umasankari Journal: Annals of nuclear energy Issue: Volume 153(2021) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
8. Convergence study of CMFD based acceleration schemes for multi-group transport calculations with fission source using fourier analysis. (15th September 2021) Authors: Jain, Lakshay; Mohanakrishnan, Prabhakaran; Karthikeyan, Ramamoorthy; Kannan, Umasankari Journal: Annals of nuclear energy Issue: Volume 160(2021) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
9. Determination of spectrum shaping factor in nuclear reactor AHWR-CF by Monte Carlo method for material characterization using neutrons. (2021) Authors: Bhandari, Deep; Kishore Mallick, Amod; Samanta, Sudipta; Sarkar, Anindita; Kumar, Rajeev; Kannan, Umasankari Journal: Materials today Issue: Volume 38:Part 5(2021) Page Start: 3041 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
10. Development of computer code ADWITA and data library for the solution of transmutation chain equations and application to the analysis of nuclear fuel cycles. (15th December 2021) Authors: Raj, Devesh; Kannan, Umasankari Journal: Annals of nuclear energy Issue: Volume 164(2021) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗