Silvester Noronha, Ph. D Email & Phone Number

Princeton, New Jersey, Us

Devens, Massachusetts, Us

Analyzing high-field magnet designs in the nuclear fusion reactor, SPARC.

Cambridge, Ma, Us

Courbevoie, Fr

Guiding and/or reviewing calculations / analyses to support the subsequent license renewal applications of nuclear power plants for 80 years of operation.

Mount Laurel, New Jersey, Us

Leading projects and contributing to analyses and calculations to support safe operation of nuclear power plants.• Performed various fracture mechanics evaluations of NPP Class 2/3 Piping to support emergent issues.• Design calculations – FEA and CFD: structural evaluation including buckling evaluation of “wrinkled elbows” in fiber reinforced composites (FEA), fluid flow analyses.• Technical lead for fluid flow testing in lined service-water pipe loop – designed the loop, directed the testing and interpreted the study results to qualify the service-water line repair lining. • Thermal and fatigue evaluations in NPP service water piping.• Routinely develop design specifications, prepare/review design calculations and technical reports.• Routinely create CAD models and design drawings using Creo and AutoCAD.• Provides engineering support to nuclear power plants on emergent issues during operation and refueling outages.• Initiated and submitted research proposal on investigation of residual stresses in Additive Manufacturing of nuclear components for DOE ARPA-E Program as Principal Investigator.• Initiated and submitted proposal to ASME ST LLC for study of creep crack growth at elevated temperature components as Principal Investigator.Member, ASME BPV Code, Sec XI - Subgroup Evaluation Standards, Task Group – Flaw Evaluation; Korean International Working Group on Additive Manufacturing, (2018-2022)

Courbevoie, Fr

Led and contributed to investigations, analyses, and calculations to support the mitigation/repair of nuclear reactor components, and presented/documented results. Prepared/published over 200 design calculations and technical reports.o Completed numerous coupled thermo-mechanical finite element simulation using ANSYS (APDL & WB) to estimate weld residual stresses.o Provided finite element crack modeling. Performed thermal transient analyses.o Delivered multiple fracture analyses based on ASME Code Section III and Section XI, Appendix G.o Produced crack growth analyses to supplement inspection of pressure vessels and piping.o Accomplished calculations to analyze fatigue and stress corrosion crack growths to determine limiting flaws in the repair configuration that met ASME B&PV Code section XI, acceptance criteria.o Performed elastic-plastic fracture mechanics evaluation of flaws in low alloy steel components.o Conducted root cause investigation of the nuclear fuel hold-down springs failure, created stress corrosion crack tests of fuel hold-down spring to identify the failure mechanism.o Performed materials selection and qualification studies for replacement of nuclear reactor piping systems and used fuel storage casks.o Researched flaw tolerance of reactor internals and provided recommendations for aging management strategies based on FMEA. o Earned multiple CORE awards for McGuire Unit 2 Safety Injection Line Elbow Weld Overlay Fracture; Limerick RPV Nozzle Repair Weld Evaluations; TMI-1 Tech. Spec. P-T Limits; CCNP2 - PWSCC Assessment of Alloy 82 PZR N3 HS Repair; KRSKO Weld Residual Stress Simulation; and Catawba Units 1/2 nozzles flaw evaluation.o Presented multiple papers at ASME–PVP conferences, and chaired a session and presented at the fourth international conference on multiscale materials modeling; spearheaded multiple proposals for DoE/ASME.

Los Angeles, Ca, Us

Conducted research on the mechanical and fracture behaviour of structural materials primarily ferritic steels used in the design of fusion & Gen IV fission reactors. I was a grant holder (with Prof. Ghoniem) from DOE fusion energy sciences on “Multiscale modelling of deformation, fracture and failure of fusion materials and structures” (2003-2008). Taught undergraduate course “Dynamics of Particles & Rigid Bodies” (MAE 102)”. Achievements• Introduced a statistical based model to predict the observed scatter in the measurement of fracture toughness.• Discovered that crack-blunting in addition to dislocation mobility contributes significantly to sharp increase in fracture toughness (brittle - ductile transition) of ferritic steels with temperature.• Established the nature of crack tip fields from discrete dislocation methods and compared with other continuum methods. • Introduced a model for heterogeneous deformation (channel formation) in irradiated materials based on non-linear interaction between dislocations and other defect species.• Introduced a Multiscale approach for crack-tip plastic zone simulation.

Blacksburg, Va, Us

Analyzed fracture behavior of nanocrystalline materials using the multiscale method. Computer codes were developed in FORTRAN and C for molecular dynamics and dislocation simulations.

Oxford, Oxfordshire, Gb

Models and computer codes in FORTRAN were developed to simulate fracture and brittle-ductile transition in ferritic steels. Conducted fracture and fatigue testing of ferritic steels at low temperature; did microstructural analysis of ferritic steels. Crack-tip plastic behaviour is hardening materials in done by FE method (using ABAQUS).Achievements• A model was introduced to explain the constancy of microscopic fracture stress with temperature observed in cleavage of ferrtic steels. • A multiple slip plane crack-tip plasticity model was introduced.

Ph D, Materials Science

Master’S Degree, Chemistry

Bachelor’S Degree, Chemistry, Physics & Mathematics