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1

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)

Chauthwani, G.C., Kannan, Umasankari

Journal:

Nuclear Engineering and Design

Year:

2019

Language:

english

File:

PDF, 2.22 MB

english, 2019

2

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

Jain, Lakshay, Karthikeyan, Ramamoorthy, Kannan, Umasankari

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 4.27 MB

english, 2020

3

Reactivity worth of liquid poison jets in the moderator

Kamala Balakrishnan, Umasankari Kannan, Anil Kakodkar

Journal:

Annals of Nuclear Energy

Year:

1993

Language:

english

File:

PDF, 865 KB

english, 1993

4

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

Umasankari Kannan, S. Ganesan

Journal:

Annals of Nuclear Energy

Year:

2010

Language:

english

File:

PDF, 453 KB

english, 2010

5

Numerical Investigations of the Effect of Radial Power Distribution and Inlet Orifice on the Stability Behavior of Parallel Multichannel Type Natural Circulation Boiling Water Reactor

Singh, Sapna, Singal, Garima, Nayak, A. K., Kannan, Umasankari

Journal:

Journal of Nuclear Engineering and Radiation Science

Year:

2018

Language:

english

File:

PDF, 8.59 MB

english, 2018

6

Analysis for decay heat in natural uranium fueled Pressure Tube type Heavy Water Reactor using the indigenous computer code IGDC

Chauthwani, G.C., Kannan, Umasankari

Journal:

Nuclear Engineering and Design

Year:

2019

File:

PDF, 1.69 MB

2019

7

Fuzzy Logics as an Integral Part of Evolutionary Algorithms

Thakur, Amit, Kannan, Umasankari

Journal:

Nuclear Science and Engineering

Year:

2019

Language:

english

File:

PDF, 1.05 MB

english, 2019

8

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

Raj, Devesh, Kannan, Umasankari

Journal:

Life Cycle Reliability and Safety Engineering

Year:

2020

File:

PDF, 764 KB

2020

9

Energy from thorium—An Indian perspective

KANNAN, UMASANKARI, KRISHNANI, P D

Journal:

Year:

2013

Language:

english

File:

PDF, 1.17 MB

english, 2013

10

Book Reviews

KANNAN, UMASANKARI, KRISHNANI, P D

Journal:

Physics in Perspective

Year:

2013

Language:

english

File:

PDF, 147 KB

english, 2013

11

Steady state flow analysis of two-phase natural circulation in multiple parallel channel loop

Bhusare, V.H., Bagul, R.K., Joshi, J.B., Nayak, A.K., Kannan, Umasankari, Pilkhwal, D.S., Vijayan, P.K.

Journal:

Nuclear Engineering and Design

Year:

2016

Language:

english

File:

PDF, 1.12 MB

english, 2016

12

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

Kumar, Sunil, Vijayan, P.K., Kannan, Umasankari, Sharma, Manish, Pilkhwal, D.S.

Journal:

Applied Thermal Engineering

Year:

2017

Language:

english

File:

PDF, 5.66 MB

english, 2017

13

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

Khan, Suhail Ahmad, Jagannathan, V., Kannan, Umasankari, Mathur, Arvind

Journal:

Nuclear Energy and Technology

Year:

2016

Language:

english

File:

PDF, 9.77 MB

english, 2016

14

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

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

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 12.47 MB

english, 2017

15

3D space-time analysis of ATWS in compact high temperature reactor with integrated thermal-hydraulic model in code ARCH-TH

Dwivedi, D.K., Gupta, Anurag, Kannan, Umasankari

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.83 MB

english, 2017

16

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

Kumar, Sunil, Grover, R.B., Vijayan, P.K., Kannan, Umasankari

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 7.88 MB

english, 2017

17

Isotopic and Energy Groupwise Dependence of Fuel Temperature Coefficient of Reactivity in Natural Uranium-Fueled Pressurized Heavy Water Reactors

Umasankari, Kannan, Ganesan, S.

Journal:

Nuclear Science and Engineering

Year:

2007

Language:

english

File:

PDF, 489 KB

english, 2007

18

Analysis of Coolant Void Reactivity of Advanced Heavy Water Reactor Through Isotopic Reaction Rates

Umasankari, Kannan, Ganesan, S.

Journal:

Nuclear Science and Engineering

Year:

2011

Language:

english

File:

PDF, 1.15 MB

english, 2011

19

Studies on Reactivity Coefficients of Thorium-Based Fuel (Th- 233 U)O 2 with Molten Salt (Flibe) Cooled Pebble

Singh, Indrajeet, Gupta, Anurag, Kannan, Umasankari

Journal:

Nuclear Science and Engineering

Year:

2018

Language:

english

File:

PDF, 1.66 MB

english, 2018

20

Analysis for decay heat in natural uranium fueled Pressure Tube type Heavy Water Reactor using the indigenous computer code IGDC

Chauthwani, G.C., Kannan, Umasankari

Journal:

Nuclear Engineering and Design

Year:

2019

Language:

english

File:

PDF, 1.69 MB

english, 2019

21

A Diffusion Monte Carlo–Based Algorithm for Estimation of Higher Modes of a Reactor

Srivastava, Argala, Singh, K. P., Mallick, Amod Kishore, Kannan, Umasankari, Degweker, S. B.

Journal:

Nuclear Science and Engineering

Year:

2019

Language:

english

File:

PDF, 1.77 MB

english, 2019

22

A Diffusion Monte Carlo–Based Algorithm for Estimation of Higher Modes of a Reactor

Srivastava, Argala, Singh, K. P., Mallick, Amod Kishore, Kannan, Umasankari, Degweker, S. B.

Journal:

Nuclear Science and Engineering

Year:

2019

File:

PDF, 1.77 MB

2019

23

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

Kumar, Anek, Kannan, Umasankari, Ganesan, S.

Journal:

Nuclear Science and Engineering

Year:

2019

Language:

english

File:

PDF, 1.97 MB

english, 2019

24

New homogenised axial diffusion coefficients from lattice calculations

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

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 568 KB

2019

25

Use of finite-difference diffusion Monte Carlo method to generate Shannon entropy of the fission distribution in a nuclear reactor core

Srivastava, Argala, Mallick, Amod Kishore, Singh, K. P., Kannan, Umasankari

Journal:

Life Cycle Reliability and Safety Engineering

Year:

2020

File:

PDF, 592 KB

2020

26

Perspectives on nuclear data for advanced reactor design and analysis

Kannan, Umasankari

Journal:

Life Cycle Reliability and Safety Engineering

Year:

2020

File:

PDF, 3.42 MB

2020

27

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

Anupreethi, B., Gupta, Anurag, Kannan, Umasankari, Tiwari, Akhilanand Pati

Journal:

Nuclear Engineering and Design

Year:

2020

File:

PDF, 5.31 MB

2020

28

Optimization of AHWR core design: neutronics and thermal-hydraulics analysis and calculations

Bharti, Vishal, Chandraker, D. K., Chakraborty, Arindam, Thakur, Amit, Sarkar, Debasmit, Singh, Baltej, Kannan, Umasankari, Nayak, A. K., Sinha, S. K.

Journal:

Life Cycle Reliability and Safety Engineering

Year:

2020

File:

PDF, 1.11 MB

2020

29

Development of in-core fuel management tool for AHWR using artificial neural networks

Thakur, Amit, Sarkar, Debasmit, Bharti, Vishal, Kannan, Umasankari

Journal:

Annals of Nuclear Energy

Year:

2021

File:

PDF, 22 KB

2021

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