Accession Number : ADA174237
Title : Validation of the Modular Modeling System for Use in Accident Analysis at a Small-Scale Reactor Plant.
Descriptive Note : Master's thesis,
Corporate Author : PENNSYLVANIA STATE UNIV UNIVERSITY PARK COLL OF ENGINEERING
Personal Author(s) : Doty,Charles V
PDF Url : ADA174237
Report Date : Dec 1986
Pagination or Media Count : 145
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.
Descriptors : *COMPUTER PROGRAM VERIFICATION, *REACTOR ACCIDENTS, *MATHEMATICAL PREDICTION, ACCURACY, PRESSURIZED WATER REACTORS, REACTOR COOLANTS, LOSSES, THESES
Subject Categories : Computer Programming and Software
Nuclear Power Plants and Fission Reactor Eng
Distribution Statement : APPROVED FOR PUBLIC RELEASE