Within the framework of safety analysis of currently operated nuclear power reactors, innovative Monte Carlo methods have been developed to perform both fixed source and eigenvalue simulations; taking advantage of variance reduction techniques for in-core and ex-core responses. The activity is carried out within the present work, dealing with a benchmarking with two different nuclear systems. A close collaboration is carried on with IRSN (French Institute for Radiation Protection and Nuclear Safety). In fact, two complementary sample problems were adopted: TAPIRO, a small fast research reactor and the large GEN-III PWR model employed before the TIHANGE model for the calculation of neutron and gamma detectors in and outside the pressure vessel well. The TAPIRO model provided a good benchmark, while Tihange offered a case study for ex-core detector analysis through the deep shield in the reactor well. First approach has been eigenvalue calculation during which the fission source is sampled and then wrote to a file. Secondarily, DSA is employed in fixed source simulation. In addition, in-core or ex-core local responses are added to in-core global responses to utilize DSA variance reduction technique directly in an eigenvalue simulation – thanks to the multi-response capability. Finally, a simple experimental benchmark is used to check nuclear data utilized and methodology consistency: PCA-Replica is selected for this purpose.
|Titolo:||Development and Application of Monte Carlo Neutronics Methodologies for Safety Studies of Current Operating Reactors (Analisi neutronica con Metodi Monte Carlo di Impianti Nucleari Tipo PWR)|
|Data di pubblicazione:||21-set-2016|
|Appare nelle tipologie:||5.2 Documento in Garanzia della Qualità|