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Reactor Core Performance Evaluation

  • NSE supports customers with safety evaluation services on reactor core design. Core analysis is performed to ascertain the core conditions for maintaining the fuel integrity during the postulated accidents. Major technical expertise includes reactor physics and kinetics, core thermal-hydraulics, and fuel performance analysis.
  • Reactor Physics and Fuel Evaluation
    • Core power distributions evaluation
    • Core parameters such as reactivity coefficients and shutdown margin
    • Reactor kinetics
    • Fuel centerline melting evaluation
    • Fuel performance analysis
    • Core protection system evaluation
  • Core Thermal-Hydraulics Evaluation
    • DNB analysis
    • Uncertainty analysis of core variables and CHF correlations
    • Evaluation of core safety limits
  • Recent Projects
    • Evaluation of the SMART Nuclear fuel assembly CHF correlation
    • Safety evaluation on operating range extension of the regulating CEA for KSNP
    • Evaluation on ROP trip setpoint over pressure tube creep of CANDU reactors
    • Evaluation on adaption of the PARCS code for core design audit analyses

Plant System Safety Analysis

  • NSE provides professional evaluation on the results of safety analyses performed for nuclear power plant design and licensing. Safety analysis covers LOCA analysis for evaluating the adequacy of Emergency Core Cooling System design and non-LOCA analyses. Thermal-hydraulic system codes such as MARS or RELAP5 are used, and reactor kinetics and fuel analysis codes can additionally be coupled to the system codes for detailed core evaluation during the transients.
  • LOCA Analysis
    • Peak clad temperature
    • Total amount of hydrogen generation
    • Total oxidation of the cladding
    • Coolability evaluation of core geometry
    • Long term cooling evaluation
    • Fuel rupture evaluation
    • Adequacy evaluation of assumptions and uncertainties
  • Non-LOCA Analysis
    • Loss of off-site power
    • Loss of feedwater
    • Boron dilution
    • Feedwater pipe breaks
    • Ejection of control rod assembly, etc.
    • These transients are evaluated in terms of DNB, fuel melting, system pressure, dose limits, etc.
  • Recent Projects
    • Technical support in detailed evaluation of containment spray actuation event of ShinKori Unit 1.
    • RETAS workbench functional upgrade and validation on integral effect tests
    • Pre-analysis on simulator for regulatory audit and training and development of a prototype engine
    • Core nodalization effects in the main steam line break analysis using the MARS/PARCS Coupled Code
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