TY - JOUR
T1 - Neutronic assessment and criticality analysis of the in-vessel fuel storage facilities in the CDT project
AU - Di Maria, Salvatore
AU - Ottolini, Marco
AU - Sarotto, Massimo
AU - Martin-Fuertes, Francisco
AU - Vazquez, M.
AU - Malambu Mbala, Edouard
AU - Teles, Pedro Peixoto
AU - Castelliti, Diego
AU - Vaz, Pedro
AU - Reale, Marco
AU - Mansani, Luigi
AU - Baeten, Peter
PY - 2011/1
Y1 - 2011/1
N2 - The main objective of the CDT project is to establish an engineering design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) that is the pilot plant of an industrial-scale of both an Accelerator Driven System (ADS) and a Lead Fast Reactor (LFR), based on the MYRRHA reactor concept, planned to be built during the next decade. An important issue regarding the reactor design of the MYRRHA/FASTEF experiment is the in-vessel fuel storage facility for fresh fuel, as it might have an impact on the criticality of the overall system that must be analyzed and quantified. In this work, the neutronic analysis of the in-vessel fuel storage facility and its coupling with the critical core was performed, using the state of the art Monte Carlo program MCNPX 2.6.0. Using this program several parameters were analyzed, like the criticality behavior (namely the Keff), the fission power production and the radiation damage (the displacements per atom).
AB - The main objective of the CDT project is to establish an engineering design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) that is the pilot plant of an industrial-scale of both an Accelerator Driven System (ADS) and a Lead Fast Reactor (LFR), based on the MYRRHA reactor concept, planned to be built during the next decade. An important issue regarding the reactor design of the MYRRHA/FASTEF experiment is the in-vessel fuel storage facility for fresh fuel, as it might have an impact on the criticality of the overall system that must be analyzed and quantified. In this work, the neutronic analysis of the in-vessel fuel storage facility and its coupling with the critical core was performed, using the state of the art Monte Carlo program MCNPX 2.6.0. Using this program several parameters were analyzed, like the criticality behavior (namely the Keff), the fission power production and the radiation damage (the displacements per atom).
KW - Neutronic assessment
KW - Criticality analysis
KW - In-vessel fuel storage
KW - CDT
UR - https://ecm.sckcen.be/OTCS/llisapi.dll/overview/46314449
U2 - 10.13182/FST12-A13436
DO - 10.13182/FST12-A13436
M3 - Article
SN - 1536-1055
VL - 61
SP - 98
EP - 301
JO - Fusion Science and Technology
JF - Fusion Science and Technology
IS - 1T
ER -