Validation of the Modular Modeling System for Use in Accident Analysis at a Small-Scale Reactor Plant.

Abstract

The Modular Modeling System (MMS) was developed for the study of the thermal hydraulic performance of pressurized water reactor plants at steady state and during some slowly varying transients. To determine the limits of transient severity this code can endure, two experiments conducted at the Loss of Fluid Test (LOFT) facility were simulated using the IBM/CMS computer. These experiments are a small break loss of coolant accident (Experiment L3-5) and an excessive steam generator load increase (Experiment L6-3). In the case of the former, the Modular Modeling System failed to accurately predict the performance of the LOFT facility. The MMS was, however, successful in predicting the significant thermal-hydraulic parameters of Experiment L6-3. The MMS predictions of the LOFT facility's performance during this experiment were more accurate than those of the more sophisticated RETRAN code. This success validates the MMS' ability to predict the performance of nuclear power plants that are scaled much smaller than central station plants.

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Document Details

Document Type
Technical Report
Publication Date
Dec 01, 1986
Accession Number
ADA174237

Entities

People

  • Charles V. Doty

Organizations

  • Pennsylvania State University

Tags

Communities of Interest

  • Air Platforms
  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Computers
  • Coolant Pumps
  • Electric Power
  • Equations
  • Generators
  • High Pressure
  • Instrumentation
  • Nuclear Power Plants
  • Nuclear Reactors
  • Pressurized Water Reactors
  • Reactor Coolants
  • Reactor Cores
  • Reactor Kinetics
  • Secondary Flow
  • Test Facilities
  • Thermodynamic Properties
  • United States

Fields of Study

  • Physics

Readers

  • Combustion and Flow Dynamics.
  • Computational Modeling and Simulation
  • Energy Conservation and Renewable Energy Engineering.