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Anuj Kumar Deo
Observed names:
Anuj Deo,
Anuj K. Deo
Institution:
Atomic Energy Regulatory Board
Observed institution:
Atomic Energy Regulatory Board
ORCID:
0000-0002-1383-1933
Observed ORCID:
0000-0002-1383-1933
OpenAlex ID:
A5008137229
Burst investigation on zircaloy-4 claddings in inert environment
2014
·
Mohd. Kaleem Khan
, Manabendra Pathak
, et al.
·
Annals of Nuclear Energy
·
28
Burst criterion for zircaloy-4 fuel cladding in an inert environment
2013
·
Mohd. Kaleem Khan
, Manabendra Pathak
, et al.
·
Nuclear Engineering and Design
·
16
Steam condensation on a circular tube in the presence of non-condensables (air) in passive containment cooling system
2023
·
Deepak K. Solanki
, Dhileeban N．
, et al.
·
International Journal of Heat and Mass Transfer
·
15
Measurement of thermal properties of ferro siliceous sacrificial radiation shielding concrete using semi-infinite transient heat conduction model
2023
·
Akshay U. Shirsat
, Anuj Kumar
, et al.
·
Construction and Building Materials
·
8
Measurement of ablation and estimation of the interfacial heat flux profiles during molten corium concrete interactions
2024
·
Pedduri Jayakrishna
, Prakash Nanthagopalan
, et al.
·
Nuclear Engineering and Design
·
6
Thermo-mechanical and Thermophysical Properties of Ferro-siliceous Sacrificial Concrete on Exposure to Elevated Temperatures
2024
·
P. V. P. Moorthi
, Anuj Kumar
, et al.
·
International Journal of Thermophysics
·
4
International Fuel Performance Study of Fresh Fuel Experiments for Pcmi Effects During Ria Experiments
2024
·
Seokbin Seo
, Charles Folsom
, et al.
·
Nuclear Engineering and Design
·
4
PDF
Experimental investigations and inverse heat transfer analysis to study heat transfer and ablation behaviour of concrete exposed to oxyacetylene flame
2024
·
Pedduri Jayakrishna
, Prakash Nanthagopalan
, et al.
·
Annals of Nuclear Energy
·
1
Measurement of temperature distribution and estimation of interfacial heat flux profiles during the interaction of different molten metals with ferrosiliceous concrete
2025
·
Pedduri Jayakrishna
, Akshay U. Shirsat
, et al.
·
Nuclear Engineering and Design
In-vessel retention analysis for a typical PHWR
2017
·
Anuj Kumar Deo
, P. K. Baburajan
, et al.
·
Life Cycle Reliability and Safety Engineering
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Works count:
10
Citation count:
82
H-index:
5
I10-index:
3
Year
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