RSICC CODE PACKAGE PSR-411
1. NAME AND TITLE
MORECA: Computer Code System for Simulating Modular High-Temperature Gas Cooled Reactor Core Heatup.
Oak Ridge National Laboratory, Oak Ridge, Tennessee through the Energy Science and Technology Software Center, Oak Ridge, Tennessee.
3. CODING LANGUAGE AND COMPUTER
FORTRAN 77; IBM PC (P00411/PC386/00).
4. NATURE OF PROBLEM SOLVED
MORECA was developed for analyzing postulated long-term core heatup scenarios for which active cooling systems used to remove afterheat following the accidents can be assumed to be unavailable. Simulations of long-term loss-of-convection accidents, both with and without depressurization of the primary coolant, have shown that maximum core temperatures stay below the point at which any significant fuel failures and fission product releases are expected. Sensitivity studies also have been done to determine the effects of errors in the predictions due both to uncertainties in the modeling and to the assumptions about operational parameters. MORECA models the U.S. Department of Energy reference design of a standard modular high-temperature gas-cooled reactor (MHTGR). It is based on the ORNL ORECA code system.
5. METHOD OF SOLUTION
The method of solution used was Modified Euler.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
The sample problem runs in less than 1 minute on a Pentium II 266 Mhz PC.
8. COMPUTER HARDWARE REQUIREMENTS
A 386 or better processor, with 3 MB or more free disk space.
9. COMPUTER SOFTWARE REQUIREMENTS
FORTRAN 77 compiler, MS DOS 6.0, WINDOWS 3.1 or higher versions. An executable created with the Digital Visual Fortran Vers. 5.0 compiler is included in the package.
RSICC, "README.TXT" (May 14, 1999).
S.J. Ball, "MORECA: A Computer Code for Simulating Modular High-Temperature Gas-Cooled Reactor Core Heatup Accidents," NUREG/CR-5712, ORNL/TM-11823 (October 1991).
11. CONTENTS OF CODE PACKAGE
Included are the reference document and the software program source and executable with sample problem input and output on one 3.5" diskette in a self-extracting compressed DOS file.
12. DATE OF ABSTRACT
KEYWORDS: LOCA; REACTOR SAFETY