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Coupled Neutronics and Thermal-Hydraulics Simulations Using Monte Carlo and CFD
Volkan Seker, Justin W. Thomas and Thomas J. Downar Purdue University
Nuclear Engineering Building 400 Central Drive West Lafayette, IN,47907
[email protected] ; [email protected] ; [email protected]
Presented by : Dinan Andiwijayakusuma, S.Si
Paper R E V I E W
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Major Work
A major part of the work was to develop and implement methods to update the cross
section library with the temperature distribution calculated by STAR-CD for every region
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Decription the Work
MCNP --> was used to simulate the transport of neutrons through the system
STAR-CD --> solves the 3-D momentum and energy transport equations
NJOY --> Generated Cross Sections Data using data from CFD solution
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Interface
Written by FORTRAN90 with utilized two PERL script
Execute MCNP (output : “mcnp2star.dat”) Execute STAR-CD (output : “star2mcnp.dat”) Rewritten “xsdir” with new generation cross-
section identifiers,temperatures, library names dan library paths.
The Script running until the Eigen Value and flux are convergen
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Initialization
Stand alone CFD run with input initial power profile --> to obtain initial temperature distribution for MCNP cross-section library
MCNP run with standard library to obtain inital source
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Iterative Process
The iterative calculation : MCNP (input power) --> output power distribution
--> mcnp2star.dat STAR-CD (read mcnp2star.dat) --> output
temperature,density and volume each cell --> star2mcnp.dat
NJOY (read star2mcnp.dat) --> generate new CS library --> update MCNP input (new density & new temperature)
Proses tsb berulang (iteratif) sd tercapai keadaan konvergen
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Iterative Process
Proses tsb berulang (iteratif) sd tercapai keadaan konvergen
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Three Techniques for updating Cross Section
Terkait dengan “Major Works” untuk update
Cross-Section, maka ada 3 teknik/pendekatan : Perform ENJOY calculation for each nuclide in
each region Pre-generate a library for each nuclide with
small temperature increment (2K - 5K) Pre-generate a library for each nuclide with
larger temperature increment (25K - 50K)
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Result
GEOMETRY
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Result
CFD MESHING
Arah Axial : Tinggi 240cm di-diskritisasi menjadi 600 layer, shg masing2 layer 0.4cm
Arah Radial di diskritisasi sama utk masing2 layer,yaitu 2240 cells
Total cells : 600x2240= 1.344.000 CFD cells
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Result
MCNP MESHING
Azimuthal meshing = 8mesh
Axial meshing = 12mesh Jumlah total MCNP cells:
6720 with tallies performed dalam 1920 cells pada daerah fuel
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Result
Computing run-time for a single MCNP :
siklus aktif = 300,
neutron per-siklus = 500.000 neutron
running on cluster 30 nodes (spek PC: 3GHz Pentium 4 Processors RAM 2GB)
dibutuhkan waktu 6 jam Untuk total 12 iterasi dibutuhkan 100 jam
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Result
Percobaan I, dengan distribusi suhu konstan (300oC) diperoleh hasil :
Terdapat selisih MCNP lebih besar 74pcm
Perbandingan Hasil MCNP dengan DeCART Code*) :
*) deterministic transport code
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Result
Percobaan II, dengan distribusi variable suhu diperoleh :
Terdapat selisih McStar lebih besar 66pcm, perbedaannya tidak terlalu jauh dengan kasus suhu konstan
Perbandingan Hasil MCNP-STARCD (McStar) dengan DeCART/STARC-D Code*) :
*) deterministic transport code
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Result
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Result
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Result
Perbedaan hasil eigen-value utk harga k-eff :
Case I -->Temperature constant : 74 pcm
Case II --> Variable temperature : 64pcm Perbedaan hasil Power Density :
Case I -->Temperature constant : 3,2%
Case II --> Variable temperature : 4%
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Conclusion
Secara umum Coupling MCNP-CFD sangat baik, namun karena waktu komputasi yang sangat lama, maka metode ini belum bisa menggantikan coupling Deterministik DeCART-CFD.
Metode Coupling MCNP-CFD ini bisa digunakan sebagai audit-tools untuk verifikasi hasil perhitungan dengan metode deterministik pada kasus-kasus yang lebih spesifik.
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Future Works
Dengan pertimbangan akurasi tinggi pada metode coupling MCNP-CFD namun dengan waktu komputasi yang lama, maka :
Perlu dikembangkan metode yang bisa mempercepat waktu komputasinya, misal dengan teknik variance reduction
Infrastruktur komputasi yang mampu menunjang sehingga diperoleh waktu komputasi yang cepat
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Terkait dengan USPEN 2010
Mempelajari requirement input masing2 SW (Neutronik-->mis:MCNP & TH-->mis:COBRA)
Mempelajari output yang dihasilkan masing2 SW (Neutronik-->mis:MCNP & TH-->mis:COBRA)
Mempelajari teknik update cross-section, yaitu
1. Mempelajari teknik NJOY mengenerate library cross-section data
2.Mempelajari penyiapan library cross-section data secara manual dengan kenaikan suhu tertentu
Mempelajari teknik komunikasi data yang memungkinkan untuk ketiga komponen tsb
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Terkait dengan USPEN
MCNP Input :1. Geometry Properties2. Material Properties3. Source Card4. Tally Card
MCNP Output :Neutron Fluks Distribution(Converted to Power Distribution)
CFD (FLUENT) read MCNP outputPower Distribution as Heat Source
sebagai bagian input dari CFD(FLUENT)
CFD output :Temperature and density of every cells.This data used to update cross-section
New Cross-SectionLibrary Data
requires a mesh mapping or interpolation scheme between the meshes used in
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Output
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NEXT STEP
SP 1 : NEUTRONIK
SP 2 :THERMALHYDRAULIC
SP-3 :GENERATE CROSS-SECTION
SP-4 :INTERFACE TO INTEGRATED
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CLOSING
Any Suggest..???