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NESC0836 TRAC-PF1.

TRAC, Thermohydraulics, Reactor Kinetics, 2 Phase Flow LOCA Analysis

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1. NAME OR DESIGNATION OF PROGRAM:  TRAC-PF1.
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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-PD2/MOD1 NESC0836/05 Tested 14-DEC-1982
TRAC-PF1 NESC0836/06 Tested 09-NOV-1983
TRAC-PF1 NESC0836/10 Tested 07-JUN-1994
TRAC-PF1 NESC0836/11 Tested 31-MAR-1993

Machines used:

Package ID Orig. computer Test computer
NESC0836/05 CRAY 1 CRAY 1
NESC0836/06 CDC 7600 CDC 7600
NESC0836/10 IBM PC PC-80486
NESC0836/11 IBM 370 series IBM 3084
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3. DESCRIPTION OF PROBLEM OR FUNCTION

TRAC-PF1 performs best-estimate analyses of loss-of-coolant accidents and other transients in pressurized light water reactors. The program can also be used to model a wide range of thermal-hydraulic experiments in reduced-scale facilities. Models employed include reflood, multi-dimensional two-  phase flow, nonequilibrium thermodynamics, generalized heat transfer, and reactor kinetics. Automatic steady-state and dump/ restart capabilities are provided. The changes reported in TRACNEWS  issues through Number 7 are incorporated in this release.
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4. METHOD OF SOLUTION

The partial differential equations describing the two-phase flow and heat transfer are solved by finite differences. The heat-transfer equations are treated using a semi- implicit differencing technique. The fluid-dynamics equations in the one-dimensional components use a multistep procedure that allows the material Courant condition to be violated. The three-dimensional vessel option uses semi-implicit differencing. The finite-difference equations for hydrodynamic phenomena form a system of coupled, nonlinear equations that are solved by a Newton-Raphson iteration procedure.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

All storage arrays in TRAC-PF1 can be dynamically allocated; the only limit on the size of a problem is the amount of central memory available. The number of reactor components in the problem, and the manner in which they are coupled are arbitrary. Reactor components available include accumulators, pipes, pressurizers, pumps, steam generators, tees, valves, 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, the maximum allowable time-step size, and whether a three-dimensional vessel model is used. If a purely one-dimensional model is used, very large time-steps can be used for slow transients. If a three-dimensional vessel is employed, a material Courant limit in the vessel may reduce the maximum time-step size allowed and increase the running time. Typical computer times for a CDC 7600 average 2-3 ms per time-step per mesh cell. Complete analysis of a detailed PWR LOCA (including reflood) will require several CP hours. The longest running sample problem requires about 70 CP seconds on the CDC 7600, about 300 CPU seconds on the IBM3033, about 1150 CP seconds on a PC  with the 20 MHz 2020+ coprocessor board or about 945 CP seconds with the 25 MHz CPR 2025+ coprocessor board.
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7. UNUSUAL FEATURES OF THE PROGRAM

TRAC-PF1 can describe most thermal-hydraulic experiments in addition to a wide variety of light water reactor (LWR) systems. The program is modular to more easily accomodate geometric descriptions of a problem, and more detailed models of physical processes, and to reduce program maintenance costs.
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8. RELATED AND AUXILIARY PROGRAMS

Seven auxiliary programs are included with the CDC version of TRAC-PF1. EXCON is a post- processor program used to convert the TRCGRF graphics output file into a set of component data files for input to the general-purpose  graphics program TRAP. GRED and GRIT also process the TRCGRF output  file. CON1 and CON2 convert older TRAC-PD2/MOD1 input decks into the new format required by TRAC-PF1. TRCUPD processes CDC UPDATE statements. These auxiliary programs are dependent upon the computing environment and will need to be replaced or modified for other computing environments. No auxiliary graphics capability is provided with the IBM version of TRAC-PF1.
NESC0836/06
TRAP                Postprocessor Graphics Program
EXCON Program to Edit TRAC TRCGRF Graphic Output Files TRCUPD              A TRAC Update Program
GRED                Program to Edit TRAC TRCGRF Output Files
GRIT                Program to Produce Graphs from TRAC TRCGRF
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9. STATUS
Package ID Status date Status
NESC0836/05 14-DEC-1982 Tested on behalf of NEADB
NESC0836/06 09-NOV-1983 Tested at NEADB
NESC0836/10 07-JUN-1994 Screened
NESC0836/11 31-MAR-1993 Tested at NEADB
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10. REFERENCES

- Thad D. Knight,
  TRAC-PD2 Independent Assessment,
  NUREG/CR-3866 (LA-10166-MS), December 1984.
- Dean Dobranich, Lawrence D. Buxton, and Chung-Nin Channy Wong,
  TRAC-PF1 LOCA Calculations Using Fine-Node and Coarse-Node Input
  Models,
  NUREG/CR-4044 (SAND84-2305), May 1985.
- Gregory D. Spriggs, Jan E. Koenig, and Russel C. Smith,
  TRAC-PF1 Analysis of Potential Pressurized-Thermal-Shock
  Transients at Calvert Cliffs/Unit 1 A Combustion Engineering PWR,
  NUREG/CR-4109 (LA-10321-MS), February 1985.
- Energy Division, Safety Code development Group,
  TRAC-PF1: AN Advanced Best-Estimate Computer Program for
  Pressurized Water Reactor Analysis,
  NUREG/CR-3567 (LA-9944-MS), February 1984.
- M.A. Viviande:
  Highlights of French Code Assessment Results Obtained in LOBI
  Proc. International ENS/ANS Conf. on Thermal Reactor Safety,
  Vol. 6, 421, pp 2325-2336 (1988) Societe Francaise d'Energie
  Nucleaire (SFEN), Paris.
- I. Szabo and F. David:
Comparative Study by TRAC/PF1 Calculations of Some Typical Natural    Circulation Tests Performed on Scaled Models of a P.W.R.
  Proc. International ENS/ANS Conf. on Thermal Reactor Safety,
  Vol. 6, 421, pp 2372-2381 (1988) Societe Francaise d'Energie
  Nucleaire (SFEN), Paris.
- H. Akimoto et al.:
  Assessment of TRAC-PF1/MOD1 Code for Core Thermal Hydraulic
  Behavior during Reflood with CCTF and SCTF Data
  JAERI -M 93-032 (March 1993).
- A. Ohnuki, H. Akimoto and Y. Murao:
  Assessment of TRAC-PF1/MOD1 and TRAC-PF1/MOD2 Codes for Thermal-
  Hydraulic Behavior in Pressure Vessel during Reflood in SCTF Test
  with an inclined Radial Power Distribution
  JAERI-M 93-138 (July 1993)
- A. Ohnuki, H. Akimoto and Y. Murao:
Assessment of TRAC-PF1/MOD1 Code for Thermal-Hydraulic Behavior in    Pressure Vessel during Reflood in SCTF Test with a Radial Power
  Distribution
  JAERI-M 93-139 (July 1993)
NESC0836/05, included references:
- Safety Code Development Group Energy Division (LANL):
  TRAC-PD2 - An Advanced Best-Estimate Computer Program for
  Pressurized Water Reactor Loss-of-coolant Accident Analysis
  (Draft).
- J.L. Elliott and D. Dobranich:
  TRAC Newsletter No. 4 (January 1981).
- TRAC-PD2/MOD1, NESC No.836.7600, Availability of TRAC/PD2/MOD1
  Replacement for TRAC-P1A
  NESC Note 81-60 (June 10, 1981).
- System Subroutine Descriptions, REASSGN and INSIST (used with
  EXTRACT)
  LANL (June 2, 1981).
- TRAP/EXCON Programming Manual
- J.C. Ferguson:
  TRAP - Plotting Package for TRAC
  NUREG/CR-1567 (August 1980).
- J.C. Vigil:
  TRAC-PD2 Developmental Assessment Summary
  LA-UR - 81 - 93 (January 14, 1981).
- I. Brittain, R. O'Mahoney, C. Green and M. Oliver:
  TRAC Experience at Winfrith. (June 16, 1980).
NESC0836/06, included references:
- J.C. Ferguson and M. Turner:
  TRAP - Plotting Package for TRAC
  NUREG/CR-2054 Revision
- TRAC - Input Specifications - TRAC-PF1 7.0/EXTUPD 7.6
  LA-TIA-TN-82-1 (June 1982).
- M.S. Sahota:
  TRAC-PF1 - Developmental Assement Program Technical Note
  LA-TDA/PF1-TN-81-1
- TRAC Newsletter Nr.6 (January 1982).
- TRAC Newsletter Nr.7 (May 1982).
- TRAC-PF1 - An Advanced Best-Estimate Computer Program for
  Pressurized Water Reactor Analysis
  Draft (October 29, 1982).
- B.E. Boyack:
  TRAC-PF1 - Development Assessment
  NUREG/CR-3280, LA-9704-M (July 1983).
- I. Brittain et al.:
  TRAC - Experirience at Winfrith
  (June 16, 1980).
NESC0836/10, included references:
- TRAC - Input Specifications - TRAC-PF1 7.0/EXTUPD 7.6
  LA-TIA-TN-82-1 (June 1982).
- Safety Code Development Group Energy Division (LANL):
  TRAC-PF1 - An Advanced Best-Estimate Computer Program for
  Pressurized Water Reactor Analysis
  NUREG/CR-3567, LA-9944-MS (February 1984).
- B.E. Boyack:
  TRAC-PF1 - Development Assessment
  NUREG/CR-3280, LA-9704-M (July 1983).
- TRAC Newsletter Nr.6 (January 1982).
- TRAC Newsletter Nr.7 (May 1982).
NESC0836/11, included references:
- J.C. Ferguson and M. Turner:
  TRAP - Plotting Package for TRAC
  NUREG/CR-2054 Revision
- TRAC - Input Specifications - TRAC-PF1 7.0/EXTUPD 7.6
  LA-TIA-TN-82-1 (June 1982).
- M.S. Sahota:
  TRAC-PF1 - Developmental Assement Program Technical Note
  LA-TDA/PF1-TN-81-1
- TRAC Newsletter Nr.6 (January 1982).
- TRAC Newsletter Nr.7 (May 1982).
- TRAC-PF1 - An Advanced Best-Estimate Computer Program for
  Pressurized Water Reactor Analysis
  Draft (October 29, 1982).
- B.E. Boyack:
  TRAC-PF1 - Development Assessment
  NUREG/CR-3280, LA-9704-M (July 1983).
- I. Brittain et al.:
  TRAC - Experirience at Winfrith
  (June 16, 1980).
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11. MACHINE REQUIREMENTS

CDC 7600 requires approximately 62K words of  small core memory (SCM) and 131K words of large core memory (LCM). The IBM version requires from 4000K to 7000K bytes on an IBM3033. The IBM PC version uses either the DATANAV CPR 2020+ or 2025+ or the plug-compatible DEFINICON DSI 780+ or 785 coprocessor board. The DATANAV coprocessor family is based on the MOTOROLA 68020 micro- processor operating at 16, 20, or 25 MHz with 4, 8, or 16 Mbytes of  RAM and a MOTOROLA 6888X FPU. The CPR 20XX requires 4 Mbytes of RAM  for 300K words of LCM, 8 Mbytes of RAM for 800K words of LCM, and 16 Kbytes of RAM for 1.8M words of LCM.
NESC0836/10
NEA-DB screened the package on a DELL 466/L PC/80486.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0836/05 FORTRAN+ASSEMBLER
NESC0836/06 FORTRAN-IV
NESC0836/10 FORTRAN-77
NESC0836/11 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

SCOPE 2.1.5 (CDC7600), OS/MVT (IBM370), MVS (IBM3033), DOS 3.2 or later (IBM PC).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

COMPASS replacement routines for the TRAC-PF1 linear equation solver are included in the CDC package for more efficient operation. For plotting, TRAP, the CDC version graphics program, makes use of the Integrated Software Systems Corporation's (ISSCO) proprietary software product DISSPLA. The conversion from the CDC to IBM environment was done at Gesellschaft fuer Reaktorsicherheit, West Germany, using an Amdahl 470 V/6 II with IBM MVS operating system and the FORTRAN H Extended Enhanced compiler.
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15. NAME AND ESTABLISHMENT OF AUTHOR

   7600     J.H. Mahaffy*
            Energy Division
            Los Alamos National Laboratory
            P. O. Box 1663
            Los Alamos, New Mexico 87545

   370      E.T. Dugan*
            Department of Nuclear Engineering Sciences
            University of Florida
            Gainesville, Florida 32611

   PC       L.A.I. Arrieta*
            Comissao Nacional de Energia Nuclear
            Rio de Janeiro, Brazil
* Contact
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16. MATERIAL AVAILABLE
NESC0836/05
File name File description Records
NESC0836_05.003 TRAC-PD2/MOD1 INFORMATION FILE 37
NESC0836_05.004 TRAC-PD2/MOD1 SOURCE PROGRAM (FORTRAN-4) 39224
NESC0836_05.005 TRAC-PD2/MOD1 JCL 37
NESC0836_05.006 TRAC-PD2/MOD1 INPUT FOR TEST CASE 1 77
NESC0836_05.007 TRAC-PD2/MOD1 INPUT FOR TEST CASE 2 128
NESC0836_05.008 TRAC-PD2/MOD1 INPUT FOR TEST CASE 3 607
NESC0836_05.009 TRAC-PD2/MOD1 INPUT FOR TEST CASE 4 103
NESC0836_05.010 TRAC-PD2/MOD1 INPUT FOR TEST CASE 5 122
NESC0836_05.011 TRAC-PD2/MOD1 INPUT FOR TEST CASE 6 571
NESC0836_05.012 TRAC-PD2/MOD1 INPUT FOR TEST CASE 7 722
NESC0836_05.013 TRAC-PD2/MOD1 INPUT FOR TEST CASE 8 72
NESC0836_05.014 TRAC-PD2/MOD1 INPUT FOR TEST CASE 9 360
NESC0836_05.015 TRAC-PD2/MOD1 INPUT FOR TEST CASE 10 40
NESC0836_05.016 TRAC-PD2/MOD1 INPUT FOR TEST CASE 11 40
NESC0836_05.017 TRAC-PD2/MOD1 INPUT FOR TEST CASE 12 40
NESC0836_05.018 TRAC-PD2/MOD1 OUTPUT OF TEST CASE 9 5576
NESC0836/06
File name File description Records
NESC0836_06.003 TRAC-PF1 INFORMATION FILE 82
NESC0836_06.004 TRAC-PF1 SOURCE IN CDC UPDATE FORMAT 38984
NESC0836_06.005 TRAC-PF1 CORRECTIONS IN CDC UPDATE FORMAT 1765
NESC0836_06.006 TRAC-PF1 SOURCE IN CDC COMPILE FORMAT 49281
NESC0836_06.007 TRAC-PF1 INPUT DATA FOR TEST CASE 1 150
NESC0836_06.008 TRAC-PF1 INPUT DATA FOR TEST CASE 2 131
NESC0836_06.009 TRAC-PF1 INPUT DATA FOR TEST CASE 3 806
NESC0836_06.010 TRAC-PF1 INPUT DATA FOR TEST CASE 4 131
NESC0836_06.011 TRAC-PF1 PRINTED OUTPUT OF TEST CASE 1 1208
NESC0836_06.012 TRAC-PF1 PRINTED OUTPUT OF TEST CASE 2 1454
NESC0836_06.013 TRAC-PF1 PRINTED OUTPUT OF TEST CASE 3 5526
NESC0836_06.014 TRAC-PF1 PRINTED OUTPUT OF TEST CASE 4 1901
NESC0836_06.015 TRAP SOURCE (FORTRAN) IN CDC UPDATE FORMAT 11637
NESC0836_06.016 TRAP SOURCE (FORTRAN) IN CDC COMPILE FORMAT 16951
NESC0836_06.017 LBLIST, TRAP DEPENDENT VARIABLE LABEL DATA 744
NESC0836_06.018 EXCON SOURCE (FORTRAN) IN CDC UPDATE FORMAT 2589
NESC0836_06.019 EXCON SOURCE (FORTRAN) IN CDC COMPILE FMT 1865
NESC0836_06.020 CON1 SOURCE (FORTRAN) 4197
NESC0836_06.021 CON2 SOURCE (FORTRAN) 810
NESC0836_06.022 SGNDE, SGNSL SOURCE (FORTRAN & COMPASS) 556
NESC0836_06.023 TRCUPD SOURCE (FORTRAN) 568
NESC0836_06.024 GRIT SOURCE (FORTRAN) 671
NESC0836_06.025 GRED SOURCE (FORTRAN) 534
NESC0836/10
File name File description Records
NESC0836_10.001 Information file 94
NESC0836_10.002 TRAC-PF1 Fortran source, part 1 13285
NESC0836_10.003 TRAC-PF1 Fortran source, part 2 11862
NESC0836_10.004 TRAC-PF1 Fortran source, part 3 10991
NESC0836_10.005 TRAC-PF1 Fortran source, part 4 9320
NESC0836_10.006 TRAC-PF1 Fortran source, part 5 10155
NESC0836_10.007 TRAC-PF1 Fortran source, part 6 7402
NESC0836_10.008 TRAC-PF1 Fortran source, part 7 12167
NESC0836_10.009 TRAC-PF1 Fortran source, part 8 12854
NESC0836_10.010 Sample problem 1 150
NESC0836_10.011 Sample problem 2 131
NESC0836_10.012 Sample problem 3 131
NESC0836_10.013 Sample problem 4 806
NESC0836_10.014 Sample problem 5 24
NESC0836_10.015 Sample problem 1 output 1552
NESC0836_10.016 Sample problem 2 output 1757
NESC0836_10.017 Sample problem 3 output 2216
NESC0836_10.018 Sample problem 4 output 7254
NESC0836_10.019 DOS file-names 18
NESC0836/11
File name File description Records
NESC0836_11.001 Information file 90
NESC0836_11.002 TRAC-PF1 FORTRAN Source 88037
NESC0836_11.003 TRAC-PF1 Assembly language source 149
NESC0836_11.004 TRAC-PF1 Source for graphics,BLOCK DATA. 2895
NESC0836_11.005 TRAC-PF1 Sample problem 1: Four pipe heated 150
NESC0836_11.006 TRAC.PF1 Sample input 2:Fletch flooding rate 131
NESC0836_11.007 TRAC-PF1 Sample input 3: Zion reactor core. 130
NESC0836_11.008 TRAC-PF1 Sample input 4:PWR coarse node ver. 805
NESC0836_11.009 TRAC-PF1 Sample 1 printed output 1558
NESC0836_11.010 TRAC.PF1 Sample 2 printed output 1750
NESC0836_11.011 TRAC.PF1 Sample 3 printed output 2379
NESC0836_11.012 TRAC.PF1 Sample 4 printed output 7246
NESC0836_11.013 TRAC.PF1 Sample 1 output on FT07F001 49
NESC0836_11.014 TRAC.PF1.Sample 2 output on FT07F001 43
NESC0836_11.015 TRAC.PF1 Sample 3 output on FT07F001 66
NESC0836_11.016 TRAC.PF1 Sample 4 output on FT07F001 41
NESC0836_11.017 TRAC-PF1 JCL and user information 317
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

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