29th Symposium on Fusion Technology (SOFT 2016)

O5A.3 Recent developments in the TRIPOLI-4® Monte-Carlo code for fusion applications

8 Sep 2016, 17:20

20m

Forum Hall 2nd floor (Prague Congress Centre)

Board: 3

Oral H. Fuel Cycle and Breeding Blankets O5A

Speaker

Fadhel Malouch (Den-Service d’études des réacteurs et de mathématiques appliquées (SERMA))

Description

TRIPOLI-4® is a 3D continuous-energy Monte-Carlo particle transport code, developed by CEA, and devoted to shielding, reactor physics, criticality safety and nuclear instrumentation. TRIPOLI-4® is currently able to simulate four kinds of particles: Neutrons from 20 MeV down to 10^-5-5 eV, Photons from 50 MeV down to 1 keV, Electrons and positrons from 100 MeV down to 1 keV. The TRIPOLI-4® version 9 (released in 2013) includes some features especially conceived for the fusion community, such as the possibility to define particle sources by means of subroutines (without recompiling the code) and the addition of the torus volume in the TRIPOLI-4® geometry. External tools are also available that allow converting a CAD model into a TRIPOLI-4® geometry: MCAM developed by FDS Team and McCad developed by KIT. For the TRIPOLI-4® version 10 (released for in December 2015), a new option has been added concerning the energy interpolation mode used for the neutron exit energy distribution. This option offers the users the opportunity to choose between the raw evaluation and a more physical treatment of these data (unit-base interpolation). Thus, it is now possible to quantify the impact of such an interpolation on high energy neutron and coupled neutron-gamma sources for fusion analyses. Moreover, an activation scheme is being developed in TRIPOLI-4® to calculate shutdown dose rates for fusion applications. It is based on the Rigorous-Two-Step method (R2S) coupling the Monte-Carlo code TRIPOLI-4® with the depletion code MENDEL: TRIPOLI-4® Monte-Carlo code performs a neutron transport calculation in order to compute the flux in each region susceptible to produce decay gammas. MENDEL depletion code computes the nuclide inventories and the decay photon sources for each region based on the neutron fluxes previously calculated by TRIPOLI-4®. TRIPOLI-4® transports the decay photons and computes the dose rates induced in each region of interest.