Post on 07-Aug-2020
Serpent Utilisation in MexicoA.M. Gómez1, E. del Valle2, M.A. Barrera2, L. Arriaga2, G. Ibarra2,
E. de las Peñas3, G. Bastida3, R.C. López3, J.L. François3
1Instituto Nacional de Investigaciones Nucleares2Instituto Politécnico Nacional, Escuela Superior de Física y Matemáticas
3Facultad de Ingeniería, Universidad Nacional Autónoma de México
5th International Serpent User Group MeetingOctober 13-16, 2015 - Knoxville, Tennessee
A.M. Gómez-Torres, F. Puente-Espel, E. del Valle-Gallegos, J.L. François, C. Martin-del-Campo, G. Espinosa-Paredes, 2015. AZTLAN: Mexican Platform for Analysis and Design of Nuclear Reactors. Proceedings of ICAPP 2015, May 03-06, 2015 - Nice (France), Paper 15493.
AZTLAN Platform
BWR – Hot XS Data bank
AZLIB – BWR Core
3D SIMULATION OF AN OPERATING CYCLE IN A BWR REACTOR CORE
Main goal: to obtain thelength of an operating cyclein a BWR reactor core.
Core characteristics:• 444 fuel assemblies• 109 cruciform control rods• 120 fresh fuel assemblies• 324 fuel assemblies from
previous cycles• Light water as moderator
and coolant
• 25 nodes per fuel assembly• Thermal power = 2027 MWt• Fuel temperature = 900K• Moderator and coolant
temperature = 600K
• Void fraction = 0.4• Black boundary conditions• All Rods Out (ARO)• 5x107 neutron histories• 61 isotopes considered in the
fuel burnup process
ASSUMPTIONS
RESULTS
The length of the operating cycle = 14.631 GWd/TM
0,90
0,95
1,00
1,05
1,10
0,0 5,0 10,0 15,0 20,0 25,0
k eff
Specific burnup (GWd/TM)
Long-life breed/burn reactor• Central zone (orange) 10%/at U235 enrichment.• Middle zone (red) 15%/at U235 enrichment.• Peripheral zone (yellow) 3.5%/at U235 enrichment.• Reflector (gray) HT-9 SS hexagonal blocks.
Roberto Carlos López-Solís, Juan Luis Francois. Long-life breed/burn reactor design through reshuffle scheme. International Journal of Nuclear Energy Science and Technology, 2015 (accepted for publication).
NUCLEAR CODE KANEXT
Becker, M. et al., 2011. “KANEXT, a tool for nuclear reactor calculations: Description of the export version”. Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology, Karlsruhe, Germany.
K-EFFECTIVE
1
1,005
1,01
1,015
1,02
1,025
1,03
1,035
1,04
1,045
1,05
0 20 40 60 80 100 120 140 160 180 200
Keff
Burnup (GWd/T)
SERPENT_ANA
SERPENT_IMP
KAN_P3-25_GROUPS
KAN_P3-33_GROUPS
Lopez, R. and Francois, J.L., 2014. “Comparison of KANEXT and SERPENT for Fuel Depletion Calculations of a Sodium Fast Reactor”. The 19th Pacific Basin Nuclear Conference (PBNC 2014). Vancouver, British Columbia, Canada, August 24-28, 2014.
INVENTORIES ZONE 2
Sodium Fast Reactor (SFR)
• 487 fuel subassemblies,• 270 radial reflector subassemblies• 27 control rod subassemblies.
The core is divided into inner and outer core zones, which are composed of 286and 201 fuel subassemblies, respectively.
The control rods are divided into primary and secondary, which are composedof 18 and 9 control rod subassemblies, respectively.
Axial view of the core of SFR Radial view of the core of SFR
Corekeff
ARO ARIp ARIps
Carbide 1.058 1.03 1.015Oxide 1.068 1.029 1.012
Metallic 1.038 0.9 0.836Medium Oxide 1.081 0.939 0.877
Multiplication factor of 4 different cores.
• ARO: All Rods Out
• ARI: All Rods In ARIp: primary control rods inserted ARIps: primary and secundary control rods inserted
Material Dg [cm] Σrg [1/cm] νΣfg [1/cm] Σεg [MW/102n.cm] Σsg'→g [1/cm]
1
4.09661E+00 7.28708E-02 5.36171E-02 1.30505E-03 0.00000E+00 5.00983E-02 4.90095E-03 1.78124E-042.30162E+00 1.98899E-02 9.47777E-03 9.09310E-01 0.00000E+00 0.00000E+00 1.54361E-02 2.30304E-041.55450E+00 8.32829E-03 3.33553E-03 8.55298E-02 0.00000E+00 0.00000E+00 0.00000E+00 5.56236E-031.07986E+00 6.49822E-03 3.99923E-03 3.85541E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00
2
4.18033E+00 7.10131E-02 5.24437E-02 1.31905E-03 0.00000E+00 4.88770E-02 4.93440E-03 1.51790E-042.34531E+00 1.95329E-02 1.02544E-02 9.09417E-01 0.00000E+00 0.00000E+00 1.48897E-02 2.22550E-041.57647E+00 8.34702E-03 3.79005E-03 8.54063E-02 0.00000E+00 0.00000E+00 0.00000E+00 5.46305E-031.08568E+00 6.77477E-03 4.44922E-03 3.85774E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00
3
1.02407E+01 3.01936E-02 0.00000E+00 0.00000E+00 0.00000E+00 2.32750E-02 9.12127E-04 4.12018E-054.29368E+00 8.98953E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 8.67823E-03 4.90841E-053.14682E+00 5.42974E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 4.45401E-032.18145E+00 3.54261E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00
4
1.01675E+01 2.96688E-02 0.00000E+00 0.00000E+00 0.00000E+00 2.33139E-02 9.01802E-04 0.00000E+004.33688E+00 9.21916E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 8.50863E-03 4.82090E-053.27917E+00 6.02474E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 3.74710E-032.33371E+00 3.49076E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00
5
2.83664E+00 1.05948E-01 0.00000E+00 0.00000E+00 0.00000E+00 9.00399E-02 6.14743E-03 1.39382E-041.77622E+00 1.65257E-02 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 1.59143E-02 2.45365E-041.31997E+00 6.82350E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 6.45849E-037.84679E-01 3.18517E-03 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00
Cross sections for the carbide core materials
Fase 1b
1,39
1,395
1,4
1,405
1,41
1,415
1,42
1,425
1,43
1,435
1,44
A F A determ. Serpent
kinf Fase 1b1000 [K]
Casos de Estudio.
_ .-=-. .-=-. .-==-. { } __ .' O o '. .' O o '. / -<' )--< { } .' O'. / o .-. O \ / o .-. O \ / .---` { } / .-. o\ /O / \ o\ /O / \ o\ /O /
\ `-` / \ O`-'o / \ O`-'o / \ O`-`o / `-.-` '.____.' `._____.' `.____.'
Serpent 2 beta
A Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code
- Version 2.1.20 (April 7, 2014) -- Contact: Jaakko.Leppanen@vtt.fi
- MPI Parallel calculation mode available
- OpenMP Parallel calculation mode available
- Geometry and mesh plotting available
- Default data path not set
Begin calculation on Tue Oct 6 14:40:03 2015
Reading input file "pbmr2906"...***** Tue Oct 6 14:40:03 2015 (seed = 1444160403)Warning message from function Mem:
Null pointer (free)
% --- Universe surrounding particles:
surf 20 inf
cell 10 2 matrix1 -20
% --- Read particles:
disp 10 2 0.09043 4.55000E-02 1
%---------------------------------------------------------
Fusion-fission transmutation system
Kotschenreuther, M., Valanju, P.M., Mahajan, S.M., Schneider, E.A., 2009. Fusion -fission transmutation scheme - efficient destruction of nuclear waste. Fusion Engineering and Design 84, 83-88.
External source En=14 MeVsrc 1 sc 4 se 14.0
�𝑇𝑇 = 𝐿𝐿𝐿𝐿 𝛷𝛷 [𝜎𝜎𝜎𝜎𝜎𝜎
𝜆𝜆 + 𝜎𝜎𝜎𝜎𝜎𝜎𝛷𝛷 1 − 𝜎𝜎− 𝜆𝜆+𝜎𝜎𝜎𝜎𝜎𝜎 𝑡𝑡 −𝜎𝜎𝜎𝜎𝜎𝜎 − 𝜎𝜎𝐿𝐿
𝜆𝜆 + 𝜎𝜎𝜎𝜎𝜎𝜎 − 𝜎𝜎𝐿𝐿 𝛷𝛷 𝜎𝜎−𝜎𝜎𝜎𝜎𝜎𝜎𝑡𝑡 − 𝜎𝜎− 𝜆𝜆+𝜎𝜎𝜎𝜎 𝜎𝜎 𝑡𝑡
0,00E+00
2,00E+02
4,00E+02
6,00E+02
8,00E+02
1,00E+03
1,20E+03
1,40E+03
1,60E+03
1,80E+03
2,00E+03
Arriba Abajo Interior Exterior
0,00
5.000,00
10.000,00
15.000,00
20.000,00
25.000,00
30.000,00
1 3 5
gram
s
years
Produccion de tritio
Consumo de Tritio
Producción de tritio anual (gramos).
Thank you!
juan.louis.francois@gmail.com
http://lairn.fi-p.unam.mx/http://www.facebook.com/GRINUNAM
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