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PSR-0411 MORECA.

MORECA, Simulating Modular High-Temperature Gas Cooled Reactor Core Heatup

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1. NAME OR DESIGNATION OF PROGRAM:  MORECA
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2. COMPUTERS
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Program name Package id Status Status date
MORECA PSR-0411/01 Arrived 03-MAY-2002

Machines used:

Package ID Orig. computer Test computer
PSR-0411/01 IBM PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

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.
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4. METHODS:  The method of solution used was Modified Euler.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME

The sample problem runs in less than 1 minute on a Pentium II 266 Mhz PC.
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9. STATUS
Package ID Status date Status
PSR-0411/01 03-MAY-2002 Masterfiled Arrived
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10. REFERENCES
PSR-0411/01, included references:
- 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)
- RSICC
README.TXT
(May 14,1999)
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11. HARDWARE REQUIREMENTS

A 386 or better processor, with 3MB or more free disk space.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0411/01 FORTRAN-77
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13. 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.
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Oak Ridge National Laboratory, Oak Ridge, Tennessee
                through the Energy Science and Technology Software Center,
                Oak Ridge, Tennessee, USA
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16. MATERIAL AVAILABLE
PSR-0411/01
PROCAL.DBF DBASE database
CAHE2.F FTN Subroutine
DIDMOD.PRG DBASE program
FLOTI3.F FTN Subroutine
GOODOM.F FTN Subroutine
MHTS2.DAT Sample Problem Input
MOREC.OUT Sample Problem Output
MORECX.F Main FTN Program
MORECX.MAK Old Make File
MORECX.EXE Executable
ORECOM.DBF DBASE database
OREP.PRG DBASE program
OREVAR.DBF DBASE database
OVAR.NDX DBASE database index
PPCAL.PRG DBASE program
PRESS3.F FTN Subroutine
PROC.NDX DBASE database index
BOTTE4.F FTN Subroutine
PROCAL.DBT DBASE database memo
RADFA4.F FTN Subroutine
RCCSP.F FTN Subroutine
SUB350.F FTN Subroutine
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: reactor safety.