serpent utilisation in mexico - serpent - a monte carlo...

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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