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
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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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.
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.
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
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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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.
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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| 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.
- 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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| Package ID | Computer language |
|---|---|
| NESC0551/01 | FORTRAN+ASSEMBLER |
| NESC0551/04 | FORTRAN-IV |
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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 |
Keywords: BWR reactors, blowdown, fuel elements, heat transfer, loss-of-coolant accident, molten metal-water reactions, thermal analysis, thermal radiation.