NESC1031 TRAC-BD1.
TRAC-BD1, LOCA Analysis of BWR with 3-D Pressure Vessel and Multi Bundle Fuel Model
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| TRAC-BD1 | NESC1031/01 | Tested | 21-DEC-1984 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NESC1031/01 | CDC CYBER 176 | CDC CYBER 740 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
TRAC-BD1 performs best estimate analyses of loss-of-coolant accidents (LOCA) and other transients in boiling water reactors (BWRs). The program provides LOCA analysis capability for BWRs and for many BWR-related thermal-hydraulic experimental facilities. The program features a three-dimensional treatment of the BWR pressure vessel, a detailed model of a BWR fuel bundle including multi-rod, multi-bundle, radiation heat transfer, and leakage path modeling capability; flow-regime-dependent constitutive equation treatment; reflood tracking capability both for falling films and bottom flood quench fronts; and consistent treatment of the entire accident sequence. Dump/restart capabilities are also provided.
TRAC-BD1 performs best estimate analyses of loss-of-coolant accidents (LOCA) and other transients in boiling water reactors (BWRs). The program provides LOCA analysis capability for BWRs and for many BWR-related thermal-hydraulic experimental facilities. The program features a three-dimensional treatment of the BWR pressure vessel, a detailed model of a BWR fuel bundle including multi-rod, multi-bundle, radiation heat transfer, and leakage path modeling capability; flow-regime-dependent constitutive equation treatment; reflood tracking capability both for falling films and bottom flood quench fronts; and consistent treatment of the entire accident sequence. Dump/restart capabilities are also provided.
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4. METHOD OF SOLUTION
The system of partial differential equations describing the two-phase flow and heat transfer is solved by use of finite difference techniques. The heat transfer equations are treated as one-dimensional using a semi-implicit differencing technique. The finite difference equations for hydrodynamic phenomena form a system of coupled, nonlinear equations solved by a Newton-Raphson iteration procedure.
The system of partial differential equations describing the two-phase flow and heat transfer is solved by use of finite difference techniques. The heat transfer equations are treated as one-dimensional using a semi-implicit differencing technique. The finite difference equations for hydrodynamic phenomena form a system of coupled, nonlinear equations solved by a Newton-Raphson iteration procedure.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
All storage arrays in the program are dynamically allocated; the only limit on the size of a problem is the amount of memory available. The number of reactor components in the problem and the manner in which they are coupled is arbitrary. Reactor component models available in TRAC-BD1 include pipes, pumps, separator-dryers, tees, valves, fuel channels, jet pumps, and vessels with associated internals.
All storage arrays in the program are dynamically allocated; the only limit on the size of a problem is the amount of memory available. The number of reactor components in the problem and the manner in which they are coupled is arbitrary. Reactor component models available in TRAC-BD1 include pipes, pumps, separator-dryers, tees, valves, fuel channels, jet pumps, and vessels with associated internals.
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6. TYPICAL RUNNING TIME
Running time is highly problem-dependent and is a function of the total number of mesh cells and the maximum allowable time-step size. Total run time can be estimated from a unit run time of 2 to 3 ms per mesh cell per time step and an average time-step size of 5 ms. The longest running sample problem requires about 2.5 minutes of CPU time on the CDC6600.
Running time is highly problem-dependent and is a function of the total number of mesh cells and the maximum allowable time-step size. Total run time can be estimated from a unit run time of 2 to 3 ms per mesh cell per time step and an average time-step size of 5 ms. The longest running sample problem requires about 2.5 minutes of CPU time on the CDC6600.
NESC1031/01
NEA-DB executed test case 1 of the package on CYBER 740 in 340 CPU seconds.[ top ]
7. UNUSUAL FEATURES OF THE PROGRAM
TRAC-BD1 is a highly versatile program that can describe many thermal-hydraulic experiments in addition to the wide variety of BWR reactor system designs. The program was developed under stringent quality control measures that provide a detailed historical account of the entire development process.
TRAC-BD1 is a highly versatile program that can describe many thermal-hydraulic experiments in addition to the wide variety of BWR reactor system designs. The program was developed under stringent quality control measures that provide a detailed historical account of the entire development process.
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8. RELATED AND AUXILIARY PROGRAMS
One of the output files written by TRAC contains graphics information that can be used to produce plots. Auxiliary programs that read the plot file are provided separately in the Idaho National Engineering Laboratory Scientific Data Management System (ISDMS) software (NESC Abstract 1034).
One of the output files written by TRAC contains graphics information that can be used to produce plots. Auxiliary programs that read the plot file are provided separately in the Idaho National Engineering Laboratory Scientific Data Management System (ISDMS) software (NESC Abstract 1034).
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10. REFERENCES
- M.M. Aburomia,
BWR Refill-Reflood Program, TRAC-BWR Component Development,
NUREG/CR-2135 (EPRI NP-1583/GEAP-24941), December 1981.
- Craig M. Kullberg,
Overview of TRAC-BD1 (Version 12) Assessment Studies,
NUREG/CR-4196 (EGG-2382), April 1985.
- M.M. Aburomia,
BWR Refill-Reflood Program, TRAC-BWR Component Development,
NUREG/CR-2135 (EPRI NP-1583/GEAP-24941), December 1981.
- Craig M. Kullberg,
Overview of TRAC-BD1 (Version 12) Assessment Studies,
NUREG/CR-4196 (EGG-2382), April 1985.
NESC1031/01, included references:
- Jay W. Spore, et al.:TRAC-BD1: An Advanced Best Estimate Computer Program for Boiling
Water Reactor Loss-of-Coolant Accident Analysis.
Volume 1: Model Description.
Volume 2: Users Guide.
Volume 3: Code Structure and Programming Information.
Volume 4: Developmental Assessment.
NUREG/CR-2178 Vol. 1-4 (October 1981)
- TRAC-BD1, NESC No. 1031.C176, TRAC-BD1 Tape Description and
Implementation Information,
National Energy Software Center Note 84-29 (April 30, 1984).
- TRAC-BD1, NESC No. 1031.C176B, TRAC-BD1 Edition B Non-CDC Tape
Description and Implementation Information,
National Energy Software Center Note 84-30 (April 30, 1984).
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11. MACHINE REQUIREMENTS
CDC CYBER176 computer with 65K words of small core memory (SCM) and 220K words of large core memory (LCM). Minor changes to the standard version are needed to reduce the SCM requirements to this size, since the standard version uses approximately 123K words to obtain maximum efficiency.
CDC CYBER176 computer with 65K words of small core memory (SCM) and 220K words of large core memory (LCM). Minor changes to the standard version are needed to reduce the SCM requirements to this size, since the standard version uses approximately 123K words to obtain maximum efficiency.
NESC1031/01
Main storage requirements for running test case 1 of the package on CDC CYBER 740 are 340,000 (octal) words of SCM and 300,000 (octal) words of LCM.[ top ]
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NESC1031/01
| File name | File description | Records |
|---|---|---|
| NESC1031_01.003 | TRAC-BD1 INFORMATION FILE | 47 |
| NESC1031_01.004 | TRAC-BD1 SOURCE (UPDATE FORMAT) | 41593 |
| NESC1031_01.005 | TRAC-BD1 LIBRARY SOURCE (UPDATE FORMAT) | 2994 |
| NESC1031_01.006 | TRAC-BD1 TEST CASE 1 INPUT DATA | 659 |
| NESC1031_01.007 | TRAC-BD1 TEST CASE 1 PRINTED OUTPUT | 4429 |
| NESC1031_01.008 | TRAC-BD1 TEST CASE 2 INPUT DATA | 1306 |
| NESC1031_01.009 | TRAC-BD1 TEST CASE 2 PRINTED OUTPUT | 6053 |
| NESC1031_01.010 | TRAC-BD1 SOURCE (CARD IMAGES) | 50412 |
| NESC1031_01.011 | TRAC-BD1 LIBRARY SOURCE (CARD IMAGES) | 2479 |
| NESC1031_01.012 | JCL TO RUN TEST CASE 1 | 55 |
Keywords: BWR reactors, accidents, heat transfer, loss-of-coolant accident, reactor kinetics, reactor safety, thermodynamics, transients, two-phase flow.