IAEA1209 TRANSV2.

TRANSV2, LOCA and Steady-State Thermohydraulic Analysis of MTR

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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1. NAME OR DESIGNATION OF PROGRAM: TRANSV2.

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2. COMPUTERS

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Program name	Package id	Status	Status date
TRANSV2	IAEA1209/01	Tested	25-FEB-1993

Machines used:

Package ID	Orig. computer	Test computer
IAEA1209/01	VAX under VMS	DEC VAX 6000

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3. DESCRIPTION OF PROGRAM OR FUNCTION

This program was developed for thermal-hydraulic analysis of MTR type research reactors in steady-state operation condition at nominal power or during a loss of coolant flow accident (LOFA), both for an average channel and for a hot channel. It also can be used for nondestructive reactivity accidents analyses.

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4. METHOD OF SOLUTION

The analysis carried out in TRANSV2 is based on the evaluation of the coupled thermal-hydraulic and neutronic effects. The core is represented by a single fuel plate with its associated coolant channel. A one-directional hydrodynamic model with single phase flow was used. The heat transfer is computed on the basis of a one-dimensional conduction solution in each axial section using a complete heat transfer correlation package to be applied to both downward and upward flows. The heat generation rate is assumed to be a separable function of space and time, with the spatial relationship preassigned. The point kinetics equations are solved using a backward extrapolation technique.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME

It requires about 60 seconds of CPU time to process 1000 time-steps on a VAX 11/780.

IAEA1209/01

The test cases included in this package were executed by NEADB on a DEC VAX 6000-510 computer. The following CPU times were found:
     test case 1: 00.76 sec
     test case 2: 29.15 sec
     test case 3: 27.88 sec
     test case 4: 38.19 sec
     test case 5: 05.70 sec.

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7. UNUSUAL FEATURES OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS:

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9. STATUS

Package ID	Status date	Status
IAEA1209/01	25-FEB-1993	Tested at NEADB

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10. REFERENCES

- J. Klein and K. Mishima
  Thermal-Hydraulic Analysis for Lo Aguirre Research Reactor
  Technical Report (August 1989).
- J. Klein
  Analisis Thermohidraulico del Reactor RECH-2
  Technical Report FR-02-90, Chilean Nuclear Energy Commission
  (August 1990).

IAEA1209/01, included references:

- J. Klein and K. Mishima:
TRANSV2 - A Thermal-Hydraulic Analysis Code for Research Reactors
KURRI-TR-323.

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11. MACHINE REQUIREMENTS:

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
IAEA1209/01	FORTRAN-77

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED: DEC-VMS.

IAEA1209/01

The program was implemented by NEADB on a VAX DEC 6000 running under VMS V5.4-2.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHORS

          J. Klein
          Reactor Physics Division
          Chilean Nuclear Energy Commission
          Amunategui 95, P.O. Box 188-D
          Santiago, Chile

          K. Mishima
          Research Reactor Institute
          Kyoto University
          Kumatori-Cho, Sennan-Gun
          Osaka, 590-04, Japan

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16. MATERIAL AVAILABLE

IAEA1209/01

File name	File description	Records
IAEA1209_01.001	Information file	53
IAEA1209_01.002	Command instruction	9
IAEA1209_01.003	TRANSV2-MOD1 FORTRAN source	2868
IAEA1209_01.004	Sample problem input case 1	24
IAEA1209_01.005	Sample problem input case 2	31
IAEA1209_01.006	Sample problem input case 3	31
IAEA1209_01.007	Sample problem input case 4	30
IAEA1209_01.008	Sample problem input case 5	30
IAEA1209_01.009	Sample problem output case 1	189
IAEA1209_01.010	Sample problem output case 2	1002
IAEA1209_01.011	Sample problem output case 3	1002
IAEA1209_01.012	Sample problem output case 4	1563
IAEA1209_01.013	Sample problem output case 5	1444
IAEA1209_01.014	ENERGY sample output from case 5	11000
IAEA1209_01.015	PERIOD sample output tape 10 from case 5	11000

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17. CATEGORIES

G. Radiological Safety, Hazard and Accident Analysis
H. Heat Transfer and Fluid Flow

Keywords: heat transfer, hydraulics, hydrodynamics, loss-of-coolant accident, reactivity, steady-state conditions, thermodynamics.