IAEA1377 HYDMN.
HYDMN, Thermal Hydraulics of Miniature Neutron Source Reactor
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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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.
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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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)
- 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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IAEA1377/01
hydmn.exe Executable filehydmn.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)
Keywords: neutron source, thermal hydraulics.