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NESC0551 MOXY/MOD032.

MOXY/MOD-1, Thermal Analysis Swelling and Rupture of BWR Fuel Elements During LOCA
MOXY-MOD32, Thermal Analysis Swelling and Rupture of BWR Fuel Elements During LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  MOXY/MOD032.
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2. COMPUTERS
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Program name Package id Status Status date
MOXY-MOD32 NESC0551/01 Tested 01-DEC-1977
MOXY-MOD32 NESC0551/04 Tested 08-AUG-1983

Machines used:

Package ID Orig. computer Test computer
NESC0551/01 IBM 370 series IBM 370 series
NESC0551/04 CDC 7600 CDC 7600
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3. DESCRIPTION OF PROBLEM OR FUNCTION

MOXY is used for the thermal analysis of a planar section of a boiling water reactor (BWR) fuel element during a loss-of-coolant accident (LOCA). The code employs models that describe heat transfer by conduction, convection, and thermal radiation, and heat generation by metal-water reaction and fission product decay. Models are included for considering fuel-rod  swelling and rupture, energy transport across the fuel-to-cladding gap, and the thermal response of the canister. MOXY requires that time-dependent data during the blowdown process for the power normalized to the steady-state power, for the heat-transfer coefficient, and for the fluid temperature be provided as input. Internal models provide these parameters during the heatup and emergency cooling phases.
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4. METHOD OF SOLUTION

An implicit numerical solution of the one- dimensional Fourier heat-conduction equation is used to compute heat conduction in fuel rods, solid inactive rods, and hollow inactive rods. Interchange of thernal radiation among surfaces is calculates  using the network method described by Sparrow and Cess.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of -
   10 time-step sets
   10 print-interval sets
50 normalized power-time pairs in considering time-dependent heat       source
50 convection heat transfer coefficient-time pairs in considering       time-dependent convection
50 fluid temperature-time par is in considering time-dependent       fluid temperature
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6. TYPICAL RUNNING TIME

Approximately 3 minutes of CPU time are required to execute the sample problems on an IBM 370/195 and 2 minutes on a CDC 7600.
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7. UNUSUAL FEATURES OF THE PROGRAM

MOXY allows the use of fairly large (i.e., greater than 1 second) time-steps.
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8. RELATED AND AUXILIARY PROGRAMS

MOXY/MOD032 is part of the Water Reactor Evaluation Model (WREM) as are RELAP4/MOD5 (NESC Abstract 369) and WREM-TOODEE2/MOD3 (NESC Abstract 712). View factors are computed using an extension of the method used in the VIEWPIN code (NESC Abstract 569). The model for fuel-to-cladding gap heat transfer coefficient was adapted from the GAPCON-THERMAL1 code.
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9. STATUS
Package ID Status date Status
NESC0551/01 01-DEC-1977 Tested at NEADB
NESC0551/04 08-AUG-1983 Tested at NEADB
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10. REFERENCES

- D.R. Evans,
  MOXY, A Digital Computer Code for Core Heat Transfer Analysis,
  IN-1392, August 1970.
- WREM: Water Reactor Evaluation Model, Revision 1,
  NUREG-75/056, May 1975.
- E.M. Sparrow and R.D. Cess,
  Radiation Heat Transfer, Belmont, California, Brooks-Cole, 1966.
- NRTS Environmental Subroutine Manual, ANC Document, December 1972.
NESC0551/01, included references:
- D.P. Evans:
  The MOXY Core Heat Transfer Code: Model Description and User's
  Guide
  PG-R-76-003 (December 1976), with Revision 1 (February 14, 1977).
- D.R. Evans:
  The MOXY Core Heat Transfer Program: View Factor Model
  Improvements
  RE-E-77-114 (February 8, 1977).
- MOXY/MOD032, ACC No. 551.360B, Tape Contents Description,
  Argonne Code Center Programming Note 77-23 (April 29, 1977).
NESC0551/04, included references:
- D.P. Evans:
  The MOXY Core Heat Transfer Code: Model Description and User's
  Guide
  PG-R-76-003 (December 1976) with Revision 1 (February 14, 1977).
- D.R. Evans:
  The MOXY Core Heat Transfer Program: View Factor Model
  Improvements
  RE-E-77-114 (February 8, 1977).
- MOXY/MOD032, NESC No. 551.7600, MOXY,MOD032 CDC 7600 Version Tape
  Description and Conversion Program Listing for Use on CDC 7600
  Compatible Systems,
  NESC Note 81-58 (March 15, 1980).
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11. MACHINE REQUIREMENTS

300K bytes of storage (IBM360) or 110,000 (octal) words of small core memory (SCM) (CDC7600), standard input/- output units, and 5 other units are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0551/01 FORTRAN+ASSEMBLER
NESC0551/04 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS/360 (IBM360) and SCOPE 2.1 (CDC7600).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by:
D.R. Evans
EG&G Idaho, Inc.
P.O. Box 1625
Idaho Falls, Idaho 83415
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16. MATERIAL AVAILABLE
NESC0551/01
File name File description Records
NESC0551_01.001 SOURCE PROGRAM (UNCOMPILABLE) - F4 - EBCDIC 3905
NESC0551_01.002 CONVERT SOURCE PROGRAM - F4 - EBCDIC 24
NESC0551_01.003 CONVERT JCL 6
NESC0551_01.004 SOURCE PROGRAM (COMPILABLE) - F4 - EBCDIC 3905
NESC0551_01.005 ENVIRONMENTAL ROUTINES - F4 - EBCDIC 509
NESC0551_01.006 ENVIRONMENTAL ROUTINES - ASSEMBLER - EBCDIC 3039
NESC0551_01.007 JCL 13
NESC0551_01.008 OVERLAY CARDS 24
NESC0551_01.009 SAMPLE PROBLEM INPUT DATA 96
NESC0551_01.010 SAMPLE PROBLEM PRINTED OUTPUT 15494
NESC0551/04
File name File description Records
NESC0551_04.001 MOXY/MOD32 INFORMATION FILE 56
NESC0551_04.002 JCL AND LIBEDIT DIRECTIVES 38
NESC0551_04.003 CONVERT SOURCE 24
NESC0551_04.004 MOXY/MOD32 SOURCE (FORTRAN-4) 3905
NESC0551_04.005 E&G ENVIRONMENTAL ROUTINES (UPDATE FMT) 6774
NESC0551_04.006 SEGMENT LOADER CARDS 10
NESC0551_04.007 MOXY/MOD32 INPUT DATA FOR TEST CASE 146
NESC0551_04.008 MOXY/MOD32 OUTPUT OF TEST CASE 42195
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17. CATEGORIES
  • H. Heat Transfer and Fluid Flow

Keywords: BWR reactors, blowdown, fuel elements, heat transfer, loss-of-coolant accident, molten metal-water reactions, thermal analysis, thermal radiation.