Author Information

S. A. Anantharaman

Affiliation: Bhabha Atomic Research Centre

Division/Department: Post Irradiation and Examination Division

Address:
Mumbai, 400 085
India

Other Names:
S. Anantharaman; Sundaresan Anantharaman

Publications


Boiling Water Reactor (BWR) Pressure Vessel Surveillance Program

STP23031S
S. Anantharaman
Bhabha Atomic Research Centre


Effect of Neutron Irradiation on the Mechanical Properties of Microalloyed Steel for Reinforced Cement Concrete

STP17947S
Sundaresan Anantharaman
Bhabha Atomic Research Centre


Evaluation of Irradiation Embrittlement by Instrumented Impact Testing

STP49470S
S. Anantharaman
Bhabha Atomic Research Center


Evaluation of Ring Tensile Test Results—A Semiempirical Approach

STP49471S
S. Anantharaman
Bhabha Atomic Research Centre


Evaluation of Tarapur Atomic Power Station Pressure Vessel Surveillance Results

STP17861S
S. Anantharaman
Bhabha Atomic Research Centre


Irradiation Embrittlement Evaluation Without Lateral Expansion Measurements

STP25670S
S. Anantharaman
Bhabha Atomic Research Center


Irradiation Embrittlement of Advanced Pressure Vessel Steels

STP25665S
S. Anantharaman
Bhabha Atomic Research Centre


Mechanical Property Evaluation of Rajasthan Atomic Power Station Coolant Channel Components

STP17876S
S. Anantharaman
Bhabha Atomic Research Centre


Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications

STP152920120015
S. A. Anantharaman
Bhabha Atomic Research Centre


Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications

JAI103213
S. A. Anantharaman
Bhabha Atomic Research Centre


StockCodeTitlePublished AsAffiliationPub Date by Most Viewed
STP23031S Boiling Water Reactor (BWR) Pressure Vessel Surveillance Program S. Anantharaman Bhabha Atomic Research Centre 01 January 1986
STP17947S Effect of Neutron Irradiation on the Mechanical Properties of Microalloyed Steel for Reinforced Cement Concrete Sundaresan Anantharaman Bhabha Atomic Research Centre 01 January 1992
STP49470S Evaluation of Irradiation Embrittlement by Instrumented Impact Testing S. Anantharaman Bhabha Atomic Research Center 01 January 1990
STP49471S Evaluation of Ring Tensile Test Results—A Semiempirical Approach S. Anantharaman Bhabha Atomic Research Centre 01 January 1990
STP17861S Evaluation of Tarapur Atomic Power Station Pressure Vessel Surveillance Results S. Anantharaman Bhabha Atomic Research Centre 01 January 1992
STP25670S Irradiation Embrittlement Evaluation Without Lateral Expansion Measurements S. Anantharaman Bhabha Atomic Research Center 01 January 1987
STP25665S Irradiation Embrittlement of Advanced Pressure Vessel Steels S. Anantharaman Bhabha Atomic Research Centre 01 January 1987
STP17876S Mechanical Property Evaluation of Rajasthan Atomic Power Station Coolant Channel Components S. Anantharaman Bhabha Atomic Research Centre 01 January 1992
STP152920120015 Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications S. A. Anantharaman Bhabha Atomic Research Centre 01 April 2012
JAI103213 Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications S. A. Anantharaman Bhabha Atomic Research Centre 11 July 2011