Ram Kumar Singh Email & Phone Number

Mumbai Area, India

1. Delivered courses on computational mathematics, finite element method, plate and shell theory, engineering design, ASME pressure vessel code (section III and Section VIII) design and computational heat transfer and fluid dynamics for mechanical, civil and chemical engineering graduate and postgraduate engineers at B.A.R.C. training school (period 1979-2003). Coordinated courses on Finite Element Method, Computational Mathematics and Heat Transfer in BARC Training School and industrial courses sponsored by Indian Nuclear Society.2. Guided Ph. D. / M Tech students at IIT-Bombay, IISc Bangalore and Homi Bhabha National Institute (HBNI) and supervised B Tech and M Tech projects in BARC Training School, IIT-Bombay, Mumbai University. Served as external examiner for M Tech and Ph D theses of IITs and Mumbai University and other National Universities. Senior Professor and recognized guide for Master and Ph D programs in Mechanical/Nuclear Engineering at the Homi Bhabha National Institute, Mumbai and active in the research student mentoring program of the institute.

Powai Mumbai 400076

Delivered courses on Machine Design, Linear and Nonlinear Finite Element Analysis, Pressure Vessel and Piping Design. Supervised Master and Ph D students and supported many faculty members for formulating research proposals for national and international funding agencies.

Roorkee India

Lecture Series for M Tech/ Ph D Student for projects / Dissertations on computational mechanics on concurrent relevant topics Assistance to Faculty Members on Research ProjectsM Tech / Ph D Guide for IIT-Roorkee, IIT-Bombay, IISc Bangalore, Homi Bhabha National InstituteReview Activities in Atomic Energy Regulatory BoardBoard of research in Nuclear Science Project Review

Mumbai Area, India

(i) Coordination of safety and security studies for PHWRs, VVER, PWR, Advanced Heavy Water Reactor, Compact High Temperature Reactor, operating Research Reactors and other nuclear facilities as per national / international safety codes and guides to ensure the compliance for the requisite short / long term safety goals. With in-depth knowledge of design code requirements for the qualification of structures, systems and components expertise services for resolution of critical issues related to its compliance provided in the advisory role to Atomic Energy Regulatory Board and BARC Safety Council through trained manpower with expertise in structural, thermal hydraulics and reliability studies.(ii) Preparation of inputs for national response to Convention on Nuclear Safety, contributions to IAEA meetings on extreme events,earthquake, tsunami, external events, aircraft impact and malevolent acts. Providing expertise services to IAEA conventions, Extra Budgetary Projects, Coordinated Research Projects and standard problem exercises with trained manpower. Development of guidelines for Indian plants based on IAEA actions & plans on nuclear safety, Fukushima related technical strengthening framework of safety, active role in peer reviews and periodic safety review with different agencies.(iii) Coordination of International collaboration in reactor safety and security with OECD-NEA, US-NRC, IRSN, CNS on containment integrity, tsunami, seismic PSA, extreme events, reactor core safety, evaluation and review of Severe Accident Management Guideline.(iv) Expertise services for Indian Lead Lithium Cooled Ceramic breeder (LLCB) Test Blanket Module (TBM) design and safety assessment as per design codes such as ASME, RCCMR, ITER-SDC & PED-ESPN. Coordination for the preparation of Preliminary Safety Analysis Report / Conceptual Design Report for Indian Test Blanket Module (TBM) for International Thermonuclear Experimental Reactor (ITER) and response to ITER on the quarries.

Mumbai Area, India

(i) For containment structural safety evaluation, BARC Containment (BARCOM) Test Model was constructed, commissioned and experiments were conducted under my guidance for its ultimate load capacity evaluation. An International Round Robin Analysis with fifteen participants was coordinated for studying its failure modes and to benchmark the inelastic computer codes. This research project is very relevant in the aftermath of Chernobyl and recent Fukushima severe accident events. I initiated air craft impact load and structural reliability evaluation of PHWR/AHWR containment structures and developed nonlinear static and transient finite element codes for the damage evaluation of the Indian containment structures, which have been benchmarked with experimental results of the international standard problems of Sandia National Laboratory PWR containment model test and Nuclear Energy Agency sponsored impact benchmark tests IRIS-2010/2012. (ii) For SMiRT-21 Conference at New Delhi as Chairman of International Scientific Committee; I coordinated planning meeting, to review around 700 papers with support from around 40 members of ISC. The five days Conference with 7 keynote & 8 plenary invited lectures and 10 parallel sessions was successfully conducted with 650 international participants. In addition, 11 special workshops on Fukushima event, Tsunami, Code harmonization, IRIS-2010 benchmark and BARCOM were organized. Special Workshops specific to extreme events and Fukushima event were additionally included with intensive coordination with international experts.(iii) Actively participated in Extra Budgetary Project on tsunami in IAEA meetings and contributed on tsunami assessment of Indian nuclear power plants.(iv) Execution of plan projects for containment structural and thermal hydraulics safety evaluation, environmental dispersion assessment,fire safety and generic reactor safety assessment which includes collaboration with research, academic and technical organizations.

Mumbai Area, India

(i) I actively participated in the design and safety evaluation of Indian Test Blanket Module (TBM) for ITER with IPR, Gandhinagar and BARC. The proposal to test the concept of liquid lead-lithium cooled ceramic breeder (LLCB) in ITER port was examined to address the neutronics, thermal hydraulics and mechanical design and safety issues. I was part of the team for obtaining the port allocation for LLCB from ITER and subsequent follow up in various meetings. (ii) Significant contributions were made tsunami simulation with FEM code TSUSOL and presented in many IAEA meetings, workshops and EBP and United States Nuclear Regulatory Commission-Atomic Energy Regulatory Board bilateral meetings. The tsunami evaluation and coordination with national agencies was carried out to obtain bathymetric and land morphology data and source term evaluation was made for accurate inundation and wave run-up modeling, which were confirmed with on-site observations at Kalpakkam, Tarapur and Vizag. sites in a National Round Robin Analysis coordinated with participants from academic, research and technical organizations. The tsunami run-up and inundation data generated for the present and future prospective nuclear coastal facilities has been extremely useful for the site evaluation and evolving and implementing site specific up-gradation measures, besides the development of National Warning System.(iii) Active participation and contributions in USNRC-AERB, OECD-NEA, IRSN-BARC bilateral meetings on generic reactor safety issues, standard problem exercises on containment safety for over-pressurization, aircraft impact, fire, thermal hydraulics, regulatory and licensing requirements. (iv) Coordination in for 540 MWe PHWR containment proof testing and commissioning and containment structural and thermal hydraulic safety evaluation, engineering, commissioning and execution of experiments in the Containment Studies Facility for blowdown, helium/hydrogen and aerosol distribution studies.

Karlsruhe Area, Germany

Hydrogen Combustion and Safety Assessment for Nuclear Reactors, Test Cell, DN-15 Tube for BWR, ITER Vacuum Vessel & other applications (i) Coordination with the institute members, external experts for hydrogen deflagration / detonation experiments. (ii) Transient dynamic analysis / numerical modeling of test cell for hydrogen combustion load and experiments for hydrogen related safety issues and guidance to post-graduate student for hydrogen combustion simulation. (iii) BWR typical tube failure investigation for hydrogen detonation load - analysis and experiments (iv) ITER Vacuum Vessel assessment for hydrogen detonation load.

Mumbai Area, India

:(i) Safety and Security related studies for nuclear containment due to aircraft impact, development of finite element codes for containment ultimate load capacity evaluation, multi-barrier impact assessment, coupled fluid-structure interaction problems. Transient dynamic analysis of nuclear double containment for aircraft impact – it involved force time history generation for various aircrafts and outer & inner containment response evaluation to address major safety and security issues.(ii) Participation in USNRC-Sandia Lab sponsored round robin on Pre-Stressed Concrete Containment Pressure Vessel (PCCV) Ultimate Load Capacity Assessment– Our results were among the best three predictions and in excellent agreement with experimental results during the pre-test / post-test phases. (iii) Indian participant for NUPEC, Japan sponsored seismic shear wall round robin – Our results were in excellent agreement and consistent with the experimental test data. (iv) Significant contributions to the Indian Atomic Energy Regulatory Board (AERB) in role of member from Technical Support Organization (TSO) for review committees, task forces and working groups for Indian nuclear plants on (a) ultimate load capacity assessment of containments of various units, (b) structural and mechanical design of reactor structures, systems and components and (c) specialized courses for human resource development for Indian regulatory body. (v) Stress analysis of nuclear structures, systems and components & seismic reevaluation.

Mumbai Area, India

(i) Simulation of HDR-PWR v.32 test problem for blowdown induced acoustic wave propagation and coupled fluid-structure interaction analysis of TAPS-Boiling Water Reactor core shroud for postulated recirculation pipeline break induced acoustic load. (ii) Re-engineering, rehabilitation, design and proof testing of Kaiga Nuclear Plant Containment Structure (iii) Fluid-structure interaction analysis for Combined Calandria Tube / Pressure Tube Failure and evaluation of in-core components for 540 MWe PHWR(iv) Seismic reevaluation of structures, systems and components, sloshing studies for reactor vessel and internals(v) Numerical analysis, design and instrumented experimental qualification of nuclear piping and pressure vessel components for 220 MWe PHWR / 540 MWe PHWR during construction, commissioning and operation.

Mumbai Area, India

Worked at BARC Trombay with basic responsibilities for novel finite element code development for structural, thermal and fluid applications, finite element stress/thermal analyses, experimental stress analysis for pressure vessel & piping components of nuclear plants/research reactors during its design, commissioning/qualification tests, computer code development for flow and thermal problems for reactor safety evaluation/rehabilitation and its continued safe operation, component failure investigation and root cause analysis, containment design and commissioning.Industrial / Consultancy Experience1.Dynamic strain measurement on a synthesis gas compressor casing, fatigue and fracture analysis with recorded strain data. This was a study for a fertilizer industry to investigate the cause of recurring failures of the compressor casing.2.Strain gauge instrumented burst test of Naphtha storage tank for a petrochemical industry and stress analysis of the tank. The test was conducted on a full size tank as part of an investigation for accident analysis.3.Static and dynamic strain measurement of a PHWR core internal (inlet manifold) in simulated flow condition to predict its fatigue behavior in service conditions. 4.Strain gauge instrumented tests of nuclear / thermal / hydel power plant equipment, piping and supports during installation, initial commissioning and hot conditioning for design qualification. 5.Residual stress experimental / analytical evaluation on PHWR pressure/calandria tube, pressure vessel, piping, support & mechanical equipment for failure investigation and root cause analysis for evolution of remedial measures.6.Finite element stress & thermal analysis of nuclear components as per ASME pressure vessel code. This includes components such as pressure vessels, shell nozzle junction, composite tube sheets and support structures. These studies have been useful during initial design and reengineering of components for nuclear plants.

Doctor Of Philosophy (Ph.D.), Structural Engineering

Master’S Degree, Nuclear Engineering

Bachelor’S Degree, Mechanical Engineering

Higher Secondary