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IAEA1286 RETRAC.

RETRAC, Reactor Core Accident Simulation

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1. NAME OR DESIGNATION OF PROGRAM:  RETRAC : REactor TRansient Analysis Code.
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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
RETRAC IAEA1286/01 Arrived 19-MAR-2001

Machines used:

Package ID Orig. computer Test computer
IAEA1286/01 VAX under VMS
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The RETRAC code uses a set of coupled neutron point-kinetics equations and thermal-hydraulic conservation laws to simulate nuclear reactor core behaviour under transient or accident conditions. The reactor core is represented by single equivalent unit cells composed of three regions: fuel, clad,  and moderator (coolant).
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4. METHOD OF SOLUTION

At each time step, core thermal power is calculated by solving a set of six delayed neutron group kinetics equations with adjusted reactivity feedbacks. The numerical resolution is performed by using the Runge-Kutta-Gill method. The externally inserted reactivity is specified in the input data file,  whereas Doppler, fuel, clad, and water temperature reactivity feedbacks are calculated by the code itself. Core cooling is treated as a homogeneous one-dimensional fluid flow through a representative unit cell composed of three successive regions: fuel, clad, and coolant. Several flow regime models are considered for both single-  and two-phase states of the coolant. The conservation laws are solved by the method of characteristics coupled with an implicit finite difference scheme to ensure stability and convergence of the  numerical algorithm.
Validation tests of the RETRAC code were performed by using the International Atomic Energy Agency 10-MW benchmark cores, for protected transients. Further assessment studies are in progress using experimental data.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The RETRAC code uses steady-state thermal-hydraulic correlations. Their use is not always justified, but it seems to be quite useful in quasi-steady cases such as as loss-of-flow transients.
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6. TYPICAL RUNNING TIME

The running time depends essentially on the time step selected and the accuracy desired by the code user.
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7. UNUSUAL FEATURES OF THE PROGRAM

The method of characteristics used to solve the set of thermal-hydraulic conservation equations is a
very stable and highly converging numerical scheme, which has shown  net superiority over the one used by the PARET code, particularly in steady-state calculations.
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8. RELATED AND AUXILIARY PROGRAMS:  No additional programs are required.
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9. STATUS
Package ID Status date Status
IAEA1286/01 19-MAR-2001 Masterfiled Arrived
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10. REFERENCES

- E. Cohen:
  "Some Topics in Reactor Kinetics", Proc. 2nd Int. Conf. Peaceful
  Uses of Atomic Energy. Vol. 11, Geneva, Sept. 1 to 13, UN
  Publication (1958)
- S. Nakamura:
  Computational Methods in Engineering and Science,
  Wiley-Interscience, New York (1977)
- International Atomic Energy Agency:
Safety and Licensing Guidebook of Research Reactor Core Conversion    from the Use of High Enriched Uranium to the Use of Low Enriched
  Uranium, Vol. 3, Appendixes G and H, International Atomic Energy
  Agency, Vienna (1990)
- Research Reactor Core Conversion from the Use of High Enriched
  Uranium to the Use of Low Enriched Uranium Fuel Guidebook,
IAEA-TECDOC-233, International Atomic Energy Agency, Vienna (1980)  - W. Woodruff:
  A Kinetics and Thermal-Hydraulic Capability for the Analysis of
  Research Reactors, Nucl. Technol. 64, 196 (1984)
IAEA1286/01, included references:
- B. Baggoura et al.:
  RETRAC, A Computer Program for the Analysis of MTR Research
  Reactor Cores
  04/93/LSN/DTDSESN/CRS
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11. MACHINE REQUIREMENTS:  Minimum space required: 650 Kbytes.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1286/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  VMS.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The
code requires at least two logical units for input and output files.
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15. NAME AND ESTABLISHMENT OF AUTHORS

B. Baggoura, T. Hamidouche and A. Bousbia-Salah
Centre de Radioprotection et de Surete
Laboratoire des Analyses de Surete
02, Bd Frantz Fanon
BP 1017 Alger Gare
16000 Algiers,
Algeria
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16. MATERIAL AVAILABLE
IAEA1286/01
test-case data   mag tapeCOMRET.COM Command for execution           DATTP
source program   mag tapeRETRAC.FOR Source code                     SRCTP
test-case data   mag tapeRETRAC1.DAT Input for sample problem 1     DATTP
test-case output mag tapeRETRAC1.OUT Output for sample problem 1    OUTTP
test-case data   mag tapeRETRAC2.DAT Input for sample problem 2     DATTP
test-case output mag tapeRETRAC2.OUT Output for sample problem 2    OUTTP
report                   04/93/LSN/DTDSESN/CRS                      REPPT
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, advanced test reactor, hydraulics, irradiation, materials testing, reactor kinetics, thermodynamics, transients.