last modified: 16-MAY-2001 | catalog | categories | new | search |

IAEA1377 HYDMN.

HYDMN, Thermal Hydraulics of Miniature Neutron Source Reactor

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1. NAME OR DESIGNATION OF PROGRAM:  HYDMN.
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2. COMPUTERS
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Program name Package id Status Status date
HYDMN IAEA1377/01 Tested 16-MAY-2001

Machines used:

Package ID Orig. computer Test computer
IAEA1377/01 PC Windows PC Pentium III 500
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Calculation of coolant, fuel and pool temperature variations during steady-state and transient operations of a miniature neutron source reactor.
The MNSR (Miniature Neutron Source Reactor) is a small and compact reactor, tank-in-pool type, with highly enriched fuel (~ 90% U235 ).
The tank is immersed in a large pool, and the core is, in turn, immersed in the tank. The maximum nominal power is ~ 30 kW, the power being removed by natural convection. The core is formed of about 347 fuel rods, with 4 tie rods and 3 dummy elements distributed on a total of ten circles, each consisting of a number of fuel rods ranging between 6 and 62. A thick beryllium reflector (~ 10 cm) surrounds the core radially.
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8. RELATED OR AUXILIARY PROGRAMS:  SYRCO-1.
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9. STATUS
Package ID Status date Status
IAEA1377/01 16-MAY-2001 Tested at NEADB
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10. REFERENCES

- MNSR Thermal Hydraulics, Shi Shuangkai
  China Institute of Atomic Energy( 1993)
          
- MNSR training material
  Safety Analysis Report for Miniature Neutron Source                  
  Reactor  (MNSR), Guo Chengzhan, Gao Yongchun, Zhang
  Xianfa, China Institute of Atomic Energy
  MNSR document    Code MNSR-GN-2

- SYRCO-1 The Acumen-Provided, 1-D, 2-Goups Diffusion
  Reactor Code, M.Albarhoum, A.Eid, S. Mohammed
  AECS- PH\rss  218 (1998)
IAEA1377/01, included references:
- M. Albarhoum, A. Eid and S. Mohammed:
HYDMN The Thermal hydraulic Code  for MNSR
Report AEC Syria (2000)
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1377/01 FORTRAN-77
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15. NAME AND ESTABLISHMENT OF AUTHORS

   M. Albarhoum, A. Eid and S. Mohammed
   Department of Physics
   Atomic Energy Commission,
   P. O. Box, 6091,
   Damascus- Syria
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16. MATERIAL AVAILABLE
IAEA1377/01
hydmn.exe Executable file
hydmn.for Source code in Fortran
hydn.lib Cross-sections library
llibfore.lib Binary library
Modern.fon Modern font
Modern.fon Modern font
Modern.fon Modern font
reac.out Reactor output data
roman.fon Romant font
roman.fon Romant font
solve.for Solver subroutines
readme.doc Documentation on how to use (word format)
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17. CATEGORIES
  • H. Heat Transfer and Fluid Flow

Keywords: neutron source, thermal hydraulics.