Umasankari Kannan

发表

Development of computer code IGDC for generation and depletion of fission products and actinides in pressure tube type heavy water reactors (PT-HWRs) using Klopfenstien-Shampine numerical differentiation formula (NDF)

G. C. Chauthwani, Umasankari Kannan, 2019, Nuclear Engineering and Design.

Sensitivity analysis of AHWR flux mapping system for unavailability of SPNDs

A. Tiwari, V. S. Yellapu, Umasankari Kannan, 2022, Nuclear Engineering and Design.

Development of the Assembly-Level Monte Carlo Neutron Transport Code M3C for Reactor Physics Calculations

S. Ganesan, Umasankari Kannan, Anek Kumar, 2019, Nuclear Science and Engineering.

New homogenised axial diffusion coefficients from lattice calculations

S. Degweker, Umasankari Kannan, Sherly Ray, 2020 .

Measurement and covariance analysis of $$ ^{232} {\text{Th}}\left( {{\text{n}},2{\text{n}}} \right)^{231} {\text{Th}} $$ reaction cross section

Manjunatha Prasad Karantha, Rajeev Kumar, T. Patel, 2019, Journal of Radioanalytical and Nuclear Chemistry.

Experimental and numerical investigation on suppression of thermal stratification in a water-pool: PIV measurements and CFD simulations

P. Vijayan, Sunil Kumar, A. Agrawal, 2018, Applied Thermal Engineering.

Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems

Geoffrey T. Parks, P. D. Krishnani, William J. Nuttall, 2014 .

Development of whole core pin-by-pin transport theory model in hexagonal geometry

V. Jagannathan, S. Khan, Umasankari Kannan, 2017 .

Study of VVER-1000 OECD LEU and MOX Computational Benchmark with VISWAM Code System

V. Jagannathan, Suhail Ahmad Khan, Umasankari Kannan, 2016 .

Development of computer code ADWITA and data library for the solution of transmutation chain equations and application to the analysis of nuclear fuel cycles

D. Raj, Umasankari Kannan, 2021 .

Experimental and computational simulation of thermal stratification in large pools with immersed condenser

Pallippattu Krishnan Vijayan, Manish Sharma, D. S. Pilkhwal, 2017 .

Numerical investigation on the effect of shrouds around an immersed isolation condenser on the thermal stratification in large pools

P. Vijayan, Sunil Kumar, R. Grover, 2017 .

DIAMOND – A Method of Characteristics neutron transport code using unstructured meshing

Umasankari Kannan, Lakshay Jain, R. Karthikeyan, 2020 .

Few-group diffusion theory parameters from lattice calculations using leakage corrected collision probabilities

S. Degweker, Umasankari Kannan, Sherly Ray, 2020 .

Performance evaluation of AHWR flux mapping system during normal operational scenarios

A. Tiwari, V. S. Yellapu, Umasankari Kannan, 2022, Nuclear Engineering and Design.

Optimization of flux mapping in-core detector locations in AHWR using clustering approach

Akhilanand Pati Tiwari, Anurag Gupta, Umasankari Kannan, 2020 .

Dysprosium as a resonance absorber and its effect on the coolant void reactivity in Advanced Heavy Water Reactor (AHWR)

S. Ganesan, U. Kannan, Umasankari Kannan, 2010 .

Operational characteristics of LWR core fuelled with thorium-based fuel

D. Raj, Umasankari Kannan, 2023, Annals of Nuclear Energy.

Estimation of safety parameters of equilibrium cycle of Indian Pressurized Water Reactor (IPWR)

D. Raj, Umasankari Kannan, 2020 .

Design and development of a neutron detection based novel criticality accident alarm system (CAAS) using liquid activation technique

K. Deo, Deepa Sathian, Umasankari Kannan, 2024, Nuclear Engineering and Design.

Investigation on the Use of the Monte Carlo Iterative k-Source Scheme for the Study of Neutron Subcritical Multiplication

A. Mallick, Umasankari Kannan, Anurag Gupta, 2022, Nuclear Science and Engineering.