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NEA-0216 HYTRAN.

HYTRAN, Open Channel Thermal and Hydraulic Transients in LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  HYTRAN.
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2. COMPUTERS
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Program name Package id Status Status date
HYTRAN NEA-0216/01 Tested 01-DEC-1966

Machines used:

Package ID Orig. computer Test computer
NEA-0216/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

For calculation of thermal and hydraulic transients in an open channel core associated with a loss  of coolant flow accident, the programme is a modified version of the WAPD programme CAT.
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4. METHOD OF SOLUTION:  Equal pressure drop over the core at any height.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The core is assumed to be divided into two regions, the first represents 'average channels' the second represents a small number of 'hot channels'.
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6. TYPICAL RUNNING TIME

Computing time about 1 minute, most time is used for the printout.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0216/01 01-DEC-1966 Tested at NEADB
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10. REFERENCES

REFERENCES.
- L. S. Tong, T. P. Cunningham, et al.:
  CAT - An IBM 704 Program for Coolant Actuated Transients in an
  Open-Lattice Core
  YAEC-145.
- A. Mendez:
A CDC 3400 - Code for Calculating Thermal and Hydraulic Transients    in an Open Channel Reactor Core
  Internal Report, GKSS, Geesthacht (1966).
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11. MACHINE REQUIREMENTS:  32 k.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0216/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  SCOPE.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

         A. Mendez
         Gesellschaft fuer Kernenergie-Verwertung in Schiffbau und Schiffahrt mbH
         2057 Geesthacht-Tesperhude
         Germany
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16. MATERIAL AVAILABLE
NEA-0216/01
File name File description Records
NEA0216_01.001 SOURCE & DATA 989
NEA0216_01.002 OUTPUT 125
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • H. Heat Transfer and Fluid Flow

Keywords: loss-of-coolant accident, pressure gradients, reactor lattices, reactor safety, thermodynamics, transients.