Valerio Mascolino, Implementation of a Transient Fission Matrix hybrid algorithm for transport calculations, SC Ballroom E

Nuclear Science and Engineering & Mechanical Engineering Seminar

Implementation of a Transient Fission Matrix hybrid algorithm for 3-D time-dependent neutron transport calculations

Dr. Valerio Mascolino
Argonne National Laboratory

9 AM, Wednesday February 19, Student Center Ballroom E

In the rapidly evolving field of next-generation nuclear reactor design, advanced concepts such as molten salt reactors and fast reactors are reshaping the landscape. Traditional neutron transport simulation methods, including diffusion-based algorithms, are ill-suited to capture the complex physics inherent in these novel reactors. As the demand for precise and efficient neutron transport simulations grows, existing software solutions often face limitations. Hybrid methods that draw upon both deterministic and Monte Carlo techniques have emerged as a promising solution. The tRAPID algorithm decouples the time-dependent neutron transport problem into independent stages, enabling us to perform 3-D time-dependent neutron kinetics calculations with remarkable speed and accuracy. Leveraging the Transient Fission Matrix method, tRAPID can solve the neutron transport equation within seconds to minutes, providing the 3-D time-dependent distribution of the fission neutron source within a nuclear system. This seminar will introduce the Multi-stage Response-function Transport (MRT) approach to neutron transport simulation and delve into the details of the FM and TFM methods.