Computer Programs

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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available here.

Program name | Package id | Status | Status date |
---|---|---|---|

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 |
---|---|---|

NESC0836/06 | 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.

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.

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.

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.

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.

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.

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 ProgramEXCON 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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Package ID | Status date | Status |
---|---|---|

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)

- 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)

NESC0836/06, 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 7.6LA-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.

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.[ top ]

Package ID | Computer language |
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NESC0836/06 | FORTRAN-IV |

NESC0836/10 | FORTRAN-77 |

NESC0836/11 | FORTRAN+ASSEMBLER |

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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.

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

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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NESC0836/06

File name | File description | Records |
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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 |
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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 |
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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 |

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