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NESC1031 TRAC-BD1.

TRAC-BD1, LOCA Analysis of BWR with 3-D Pressure Vessel and Multi Bundle Fuel Model

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1. NAME OR DESIGNATION OF PROGRAM:  TRAC-BD1.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
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.
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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.
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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.
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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.
NESC1031/01
NEA-DB executed test case 1 of the package on CYBER 740 in 340 CPU seconds.
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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.
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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).
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9. STATUS
Package ID Status date Status
NESC1031/01 21-DEC-1984 Tested at NEADB
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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.
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.
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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC1031/01 FORTRAN+COMPASS
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

CDC CYBER176 NOS/BE 1.4 operating system and OVERLAY loader.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Memory
should be set to zero prior to execution. FORTRAN equivalents of the COMPASS matrix inversion routines are included in the package.
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15. NAME AND ESTABLISHMENT OF AUTHORS

              J.W. Spore, M.W. Giles, G.L. Singer*,
              and R.W. Shumway
              EG&G Idaho, Inc.
              P.O. Box 1625
              Idaho Falls, Idaho 83415
* Contact
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16. MATERIAL AVAILABLE
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
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, accidents, heat transfer, loss-of-coolant accident, reactor kinetics, reactor safety, thermodynamics, transients, two-phase flow.