RELAP Transient Analysis

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The Reactor Excursion and Leak Analysis Program (RELAP5) is a light water reactor transient analysis code developed for the United States Nuclear Regulatory Commission (US NRC) for simulation of a wide variety of hydraulic and thermal transients in both nuclear and nonnuclear systems involving mixtures of steam, water, noncondensable gases and solutes under single phase and two phase conditions.

BENEFITS/FEATURES

The RELAP5 code has received extensive validation and international participation in the development and testing of the code over the years.  It is available for UNIX and PC platforms, with excellent post-processing software (APTPLOT).  Its versatility enables the analyst to build models of system behaviors. 

Features

  • Fluid flow models
  • Heat transfer characterization
  • Non-condensable gas characterization
  • Core kinetics
  • Control systems
  • Specialized component models
  • Pipe element models
  • Straightforward input from isometric drawings
  • User control of wall friction/irreversible losses
  • Flow regimes dynamically computed and include bubbly/slug/annular/stratified
  • Pump models
  • Homologous curve implementation
  • Pump speed solution based on torque equations
  • Vertical stratified flow models
  • Valve Models
    -  Motor/check/servo models
    -  User controls on closing speed/time
    -  Check valve models are idealized
  • Boundary Conditions (BC) Models
    -  User specified flow and pressure BC
  • Specialized Junction Models
    -  Horizontal stratified vapor pull through models

EXPERTISE/SOLUTIONS

Fauske & Associates, LLC (FAI) engineers regularly utilize RELAP5 for thermal hydraulic safety analysis, including pre test prediction and post test evaluation, as illustrated in the figure above.  Major experience includes extensive piping dynamic loads evaluations for AP1000® systems as well as system evaluations on operating nuclear plants in the U.S. and overseas. 

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630-323-8750
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