A Sensitivity Study of the Critical Flow Models Used in RELAP4/MOD 5 Blowdown Analysis of a General Electric BWR.

Abstract

This study uses the RELAP4/MOD5 Computer Code to analyze the effects of critical flow modeling on the thermal-hydraulic transient response of a General Electric boiling water reactor to a major primary coolant line rupture. Included is a presentation of the equations, assumptions, and limitations of the critical flow models available for use in RFLAP4. Additionally, an evaluation of a temporary solution to a RELAP4 coding error associated with stagnation properties calculation is presented.

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Document Details

Document Type
Technical Report
Publication Date
Nov 01, 1978
Accession Number
ADA072584

Entities

People

  • Mark Vearil Carle

Organizations

  • Naval Postgraduate School

Tags

Communities of Interest

  • Cyber
  • Energy and Power Technologies
  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Boiling Water Reactors
  • Computer Programming
  • Computers
  • Engineering
  • Equations
  • Equations Of State
  • Flow Rate
  • Heat Capacity
  • Heat Transfer
  • Heat Transfer Coefficients
  • Jet Pumps
  • Mass Flow
  • Momentum
  • Nuclear Reactors
  • Specific Heat
  • Stagnation Pressure
  • Surface Temperature

Readers

  • Combustion and Flow Dynamics.
  • Computational Modeling and Simulation