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Dr. Raju S Ananth

Distinguished Professor, Department of Aerospace Engineering, School of Engineering

Qualification: Ph. D., MS, BSME

Bio Publications Experience Research Patents
Bio

Dr. Raju S Ananth received his MS Thermal Sciences from IIT Bombay and PhD in Mechanical and Aerospace Sciences from University of Rochester, USA. His areas of expertise include Flow Induced Vibrations, Structural Dynamics, Finite-ElementModeling, Fluids and Heat Transfer, Statistics and Reliability, Random Data Analysis, Reliability of surfaces subjected to Friction/ Wear, Metrology using Optical Systems and Electromagnetics. Dr. Ananth Served in an expert panel looking into the San Onofre Steam Generator tube wear issues. Involved in projects that dealt with predicting flow fields and forces due to accidents such as pipe breaks including predicting forces due to traveling acoustic wave fronts. Also involved in generating time histories from response spectra for the purpose of conducting non-linear seismic analysis. Contributions during career at various disk drive companies like Halo (Startup), Western Digital, Maxtor, SyQuest and Unisys were mainly in the area of Tribology (Physical and Chemical Interaction of Surfaces). Designed innovative tests and used tools including analytical chemistry to assess the reliability of the interface between the Magnetic Head and the data disk. Also was an active member of a number of task forces dealing with root cause investigations of magnetic head crashes.

Education

  • Ph.D., Mechanical and Aerospace Sciences, University of Rochester
  • MS, Thermal Sciences, IIT Bombay, India
  • BSME, Government College of Technology, India
Publications

Conference Proceedings

Year : 2016

3D Solution of the Flow Field in a Boiling Water Reactor Annulus due to a Recirculation Outlet Line Break Using Heat Transfer Analogy

Cite this Research Publication : Raju Ananth, Minji Fong, 3D Solution of the Flow Field in a Boiling Water Reactor Annulus due to a Recirculation Outlet Line Break Using Heat Transfer Analogy, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 24th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Electric Power Research Institute (EPRI) Creep Fatigue Workshop, American Society of Mechanical Engineers, 2016, https://doi.org/10.1115/pvp2016-63091

Publisher : American Society of Mechanical Engineers

Year : 2014

The Rocking and Stability of Spent Fuel Casks

Cite this Research Publication : Raju Ananth, Shari Day, Mrinal Bose, The Rocking and Stability of Spent Fuel Casks, Volume 8: Seismic Engineering, American Society of Mechanical Engineers, 2014, https://doi.org/10.1115/pvp2014-28780

Publisher : American Society of Mechanical Engineers

Year : 2012

Flow Loads on the Shroud in a Boiling Water Reactor due to a Recirculation Outlet Line Break: A Comparative Study Between Potential Flow and Computational Fluid Dynamics Methodologies

Cite this Research Publication : Raju Ananth, Sandra Sowah, Jay Gillis, Flow Loads on the Shroud in a Boiling Water Reactor due to a Recirculation Outlet Line Break: A Comparative Study Between Potential Flow and Computational Fluid Dynamics Methodologies, Volume 4: Fluid-Structure Interaction, American Society of Mechanical Engineers, 2012, https://doi.org/10.1115/pvp2012-78116

Publisher : American Society of Mechanical Engineers

Year : 2010

Boiling Water Reactor Jet Pump Acoustic Loads Resulting From a Recirculation Outlet Line Break Loss of Coolant Accident: Some Sensitivity Studies

Cite this Research Publication : Daniel V. Sommerville, Raju Ananth, Boiling Water Reactor Jet Pump Acoustic Loads Resulting From a Recirculation Outlet Line Break Loss of Coolant Accident: Some Sensitivity Studies, ASME 2010 Pressure Vessels and Piping Conference: Volume 4, ASMEDC, 2010, https://doi.org/10.1115/pvp2010-25866

Publisher : ASMEDC

Year : 2009

Fluid Flow Field in the Annulus of Boiling Water (BWR) Nuclear Reactors Under Normal and Accident Conditions

Cite this Research Publication : Raju Ananth, Karen Fujikawa, Jay Gillis, Fluid Flow Field in the Annulus of Boiling Water (BWR) Nuclear Reactors Under Normal and Accident Conditions, Volume 4: Fluid-Structure Interaction, ASMEDC, 2009, https://doi.org/10.1115/pvp2009-77442

Publisher : ASMEDC

Year : 2009

Decompression Pressure Wave Loads in a Boiling Water Reactor (BWR) Due to Recirculation Pipe Break

Cite this Research Publication : John Molyneux, Raju Ananth, Jay Gillis, Decompression Pressure Wave Loads in a Boiling Water Reactor (BWR) Due to Recirculation Pipe Break, Volume 4: Fluid-Structure Interaction, ASMEDC, 2009, https://doi.org/10.1115/pvp2009-77781

Publisher : ASMEDC

Year : 2005

Dynamic Pressure Data Acquisition Via Strain Gage Measurements

Cite this Research Publication : Gyorgy Szasz, Karen K. Fujikawa, Raju Ananth, Dynamic Pressure Data Acquisition Via Strain Gage Measurements, Volume 1: 20th Biennial Conference on Mechanical Vibration and Noise, Parts A, B, and C, ASMEDC, 2005, https://doi.org/10.1115/detc2005-85729

Publisher : ASMEDC

Experience
  • Distinguished Professor, Amrita Vishwa Vidyapeetham (July 2022 – Present)
  • Senior Consultant, Structural Integrity Associates Inc., San Jose, Ca. (2006-2016)
  • Consultant, Structural Integrity Associates, Inc., San Jose, CA (2003 – 2006)
  • Consultant, General Electric, Nuclear Energy Division, San Jose, CA (2001 – 2002)
  • Senior Principal Tribology Engineer, Halo Data Devices, Inc., San Jose, CA (2000 – 2001)
  • Western Digital Corporation, San Jose, CA (1994 -2000)
  • Senior Staff Engineer, Advanced Mechanical Engineering (1999 – 2000)
  • Senior Principal Engineer, Advanced Tribology Department (1994 – 1999)
  • Maxtor Corporation, San Jose, CA (1990 – 1994)
  • SyQuest Technology, Advisory Engineer, Fremont, CA (1989 – 1990)
  • Unisys, Santa Clara, CA (1979 – 1989)
  • Manager, Head Disk Mechanics, Disk Drive Engineering (1985 – 1989)
  • Manager, Mechanical Technology, Recording Technology Center (1982 – 1985)
  • Staff Engineer, Recording Technology Center (1979 – 1982)
  • Engineer, Nuclear Division, General Electric, San Jose, CA (1974 – 1979)
  • Post – Doctoral Fellow, Avionics Lab, Wright-Patterson AFB, Dayton, Ohio. (1973 – 1974)
Research

Past projects include analyzing and measuring linear and rotational vibrations of power generating equipments such as pumps and steam turbines. He is actively involved in understanding and solving flow induced vibration problems of reactor internals, As a consultant at GE he worked on predicting the flow-induced forces on jet-pumps and feed-water nozzle fatigue both from a classical and fracture mechanic points of view.
Significant contributions early in the professional career at General Electric (GE) were in the area of “Flow Induced Vibrations (FIV).” At GE generated a FIV Design Guide document that is widely used in the industry. Also performed analysis and tests on a number of Boiling Water Nuclear Reactor components including jet-pumps, guide tubes and fuel rods.

Patents
  • 5,831 , 792, “Slider Having a Debris Barrier Surrounding a Transducer,” Nov 3, 1998
  • 5,454, 157, “Method of Manufacturing a Hermitically Sealed Disk Drive,” Oct 3, 1995
  • 5,327,311, “Techniques for Providing Back Bar and Boss for Slider,” (A precursor to the Padded Slider), July 5, 1994
  • 5,299,082, “Actuator Assembly with Compensated Outer Arms,” March 29, 1994
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