The LTL professionals have extensive experience in the Nuclear Power Industry. Significant experience is listed below.
Reactors
- Expert Panel Member justifying a 13% power rate request from USNRC for the Grand Gulf Nuclear Power Station
- Expert Panel Member reviewing a customer’s tie rod bow problem
- Design Review Board Member reviewing customer’s new nuclear reactor
- Consultant on USNRC Reg. Guide 1.20 (Comprehensive Vibration Assessment Program) issued in conjunction with the next generations of pressurized water reactors
- Stress analysis of reactor internals
- FEA analysis of reactor internal core barrel/nozzle/flange assembly thermal stress and fatigue analysis based of various loading conditions
- Structural Analysis and Structural Design Criteria for reactor vessel internals, reactor vessel, spent Fuel Storage Racks, PWR Fuel Assembly, PWR Fuel Rods, steam generators, high-cycle and environmental assisted fatigue
- Dynamic Analysis for transportation, Seismic, Loss of Coolant Accident (LOCA) and flow-induced vibrations, reactor internals, spent fuel storage rack, fresh fuel shipping containers – normal transportation and accident, steam generators with tube bundle
- Manufacturing Projects for reactor internals and steam generator-engineering evaluation of manufacturing and field (installation) deviations, PWR Fuel Rods-development of acceptance criteria for in-process welding imperfections, Steam generators-conversion of engineering to design drawings, fresh fuel shipping container
- Reactor core CFD analysis using ANSYS CFX
- FEA model for nuclear reactor core barrel with neutron panel details
Small Modular Reactor
- SMR. FEA analysis on structural integrity analysis for small modular nuclear power stations, analysis includes: steam generator tube forming/buckling analysis, reactor internal component stress analysis, supporting structure seismic analysis using ASME CODE SECTION III NA/NB/NC/ND/NF/NG
- SMR. FEA analysis of building design/analysis under seismic/LOCA/DECAY loading conditions
Nuclear Fuel
- PWR fuel assembly
- PWR fresh fuel shipping container
- Fuel assembly and reactor internals debris mitigation
- Mechanical Testing of PWR Fuel Assemblies
Nuclear Power Plant Buildings (Seismic Category I and II)
- Building, reconstructing and submitting large FEA system model for customer’s nuclear island in a new plant
- Sloshing analysis using FEA model for a customer’s large cooling tank with matching results with analytical calculation
- FEA analysis of NPP buildings. Macro for loading generation for ANSYS/ANSYS-LSDYNA, run linear static, nonlinear elastic/plastic, bench mark concrete model with test results and other FEA results
- Analysis by writing in house code. Comparison between discrete and smeared model on reinforced concrete beam with William-Warnke constitutive equation
- Analysis by writing in house code. Energy dissipation capacity of a shear wall under cyclic load
- Analysis by writing in house code. Governing loading analysis on reinforced concrete containment of nuclear power plant
- Building FEA models for some components in a customer’s new power plant
- FEA mesh refinement of global FEA model containing for refined results (civil engineering application)
- Proposing design modifications during verification and review of a customer’s large steel structure for rigging and construction
- Spectrum analysis and time history analysis for a customer’s nuclear island global model
- Seismic analysis using a customer’s global FEA model to assess loading for walls and floors
Non-Linear Analysis of Civil and Mechanical Issues in Nuclear Power
- FEA analysis of yield stress and concrete cracking of Nelson stud
- FEA analysis of thermal analysis with variable material properties
Topics in Nuclear Power (Non-Reactor)
- Validate a customer’s motor-operated valve diagnostic system
- FEA analysis and FEA model building for impact assessment for ABWR nuclear power plant
- FEA analysis of dryer lifting lug stress analysis for Brunswick, evaluate structure integrity based on ASME code
- FEA analysis of IMS Shelf seismic analysis
- FEA analysis of weld stress for dryer
- Consultant to a customer on the Replacement Once-Through Steam Generator (ROTSG) excessive wear root cause analysis
- EPRI Expert Panel to review the excessive vibration problem in a customer’s shut down cooling line
- A customer’s feedwater line excessive vibration problem root cause assessment
- Stress analysis of Steam Generators
Flow-Induced Vibrations (FIV) applications for Nuclear Power
- Consultant to a customer on the root cause analysis and mitigation of excessive vibration problem in one of their units’ shutdown cooling line
- Results review for reactor coolant pump (RCP) analysis
- FEA system model for reactor vessel and internals (RVI) for Flow Induced Vibrations (FIV) analysis
- FIV load assessment using combined analytical and FEA methods for a customer’s repair project on the bolts of clevis pins inside the vessel during an outage
- Root-cause analyses of vibration-induced failure of a customer’s steam generator tubes