last modified: 07-DEC-1989 | catalog | categories | new | search |

NEA-1292 HEATHYD.

HEATHYD, Steady-State Thermal Hydraulic Analysis of Low-Enriched U Fuel Reactor

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1. NAME OR DESIGNATION OF PROGRAM:  HEATHYD.
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2. COMPUTERS
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Program name Package id Status Status date
HEATHYD NEA-1292/01 Tested 07-DEC-1989

Machines used:

Package ID Orig. computer Test computer
NEA-1292/01 Many Computers Many Computers
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3. DESCRIPTION OF PROGRAM OR FUNCTION

HEATHYD is a code for the steady-state heat transfer calculation of research nuclear reactors  with forced convection. It models heat transfer and coolant flow for assemblies of parallel fuel plates of MTR type with any axial power  distribution.
The thermodynamic model accounts for single phase cooling and sub- cooled boiling condition using the transition criterion of Bergeles- Rosenow. In addition to the calculation of the channel flow velocities and coolant pressure drops, HEATHYD calculates axial distribution of the coolant and clad-surface temperatures. Safety margins to the critical heat flux as a result of burnout condition or flow instability are determined.
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4. METHOD OF SOLUTION

Applying the finite difference method, HEATHYD  solves the equations of heat conduction and heat transfer to the coolant. For the physical properties of the coolant as a function of the coolant temperature polynomials of degree 6 are used. Depending  on the coolant condition, different correlations for the heat transfer coefficient can be applied. The analysis of the critical cooling conditions resulting in burnout or flow instability, is performed according to the correlations developed by Mirshak/ Labuntsov and Forgan/Whittle.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:  Five seconds.
NEA-1292/01
NEA-DB ran the test case included in this package on IBM 3090/600 and DEC VAX 8810 computers. CPU times required were less than .5 seconds on IBM and less than 5 seconds on VAX.
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7. UNUSUAL FEATURES OF THE PROGRAM

Consideration of axial/ transversal-radial power distribution.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-1292/01 07-DEC-1989 Tested at NEADB
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10. REFERENCES:
NEA-1292/01, included references:
- Liaquat Ali Khan and Rahim Nabbi:
  HEAT-TRANSFER Analysis of the Existing Heu and Proposed Leu Cores
  of Pakistan Research Reactor
  JUEL-2118 (February 1987)
- HEATHYD Manual
  Input Description
  (8 November 1989)
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11. MACHINE REQUIREMENTS:  IBM-370 series, VAX computers.
NEA-1292/01
348K bytes on IBM 3090.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1292/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  VM/CMS(IBM);
VMS(VAX).
NEA-1292/01
MVS (IBM 3090); VMS (VAX 8810).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

     R. NABBI
     Zentralabteilung Forschungsreaktoren und
     Kerntechnische Betriebe
     Kernforschungsanlage Juelich
     D-5170 JUELICH
     Postfach 1913
     Federal Republic of Germany
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16. MATERIAL AVAILABLE
NEA-1292/01
File name File description Records
NEA1292_01.001 This information file 73
NEA1292_01.002 HEATHYD Source Program (FORTRAN-77) 929
NEA1292_01.003 IBM-PC Compile-link-run commands 6
NEA1292_01.004 DEC-VAX Compile-link-run commands 9
NEA1292_01.005 IBM-MVS Compile-link-run job contol 101
NEA1292_01.006 Sample Problem Input Data 31
NEA1292_01.007 Sample Problem Printed Output 614
NEA1292_01.008 Description on How to Prepare the Input 89
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17. CATEGORIES
  • H. Heat Transfer and Fluid Flow

Keywords: cladding, convection, coolant loops, fuel elements, heat conduction, heat transfer, hydraulics, steady flow, steady-state conditions, thermodynamics.