Coupling the GUARDYAN code to subchanflow

D Legrady, M Pukler, B Panka, G Tolnai - EPJ Nuclear Sciences & …, 2023 - epjn.epj.org
GUARDYAN is a GPU-based dynamic Monte Carlo code developed at the Budapest
University of Technology and Economics, Hungary. Dynamic Monte Carlo computes the …

A GPU-based direct Monte Carlo simulation of time dependence in nuclear reactors

B Molnar, G Tolnai, D Legrady - Annals of Nuclear Energy, 2019 - Elsevier
Abstract A novel 3D Monte Carlo (MC) neutron transport code, GUARDYAN, was developed
to simulate direct time dependence in nuclear reactors. GUARDYAN (GpU Assisted Reactor …

Kinetic methods in Monte Carlo code RMC and its implementation to C5G7-TD benchmark

X Guo, X Shang, J Song, G Shi, S Huang… - Annals of Nuclear …, 2021 - Elsevier
Reactor safety analyses require high-fidelity numerical solutions of transient neutron
transport problems. A predictor–corrector quasi-static (PCQS) method based on the Monte …

Analysis of population control techniques for time-dependent and eigenvalue Monte Carlo neutron transport calculations

I Variansyah, RG McClarren - Nuclear Science and Engineering, 2022 - Taylor & Francis
An extensive study of population control techniques (PCTs) for time-dependent and
eigenvalue Monte Carlo (MC) neutron transport calculations is presented. We define PCT as …

Monte Carlo simulations of the SPERT III E-core transient experiments

D Mancusi, M Faucher, A Zoia - The European Physical Journal …, 2022 - epjplus.epj.org
We perform simulations of two reactivity-insertion experiments in the SPERT III E-core
nuclear research reactor. The simulations use the TRIPOLI-4® Monte Carlo neutron …

An effective initial particle sampling technique for Monte Carlo reactor transient simulations

I Variansyah, RG McClarren - arXiv preprint arXiv:2305.07646, 2023 - arxiv.org
We propose a technique to effectively sample initial neutron and delayed neutron precursor
particles for Monte Carlo (MC) simulations of typical off-critical reactor transients. The …

[HTML][HTML] Population-based variance reduction for dynamic Monte Carlo

D Legrady, M Halasz, J Kophazi, B Molnar… - Annals of Nuclear …, 2020 - Elsevier
Abstract Dynamic Monte Carlo (DMC) simulation of realistic nuclear reactors requires
powerful variance reduction methods for even a few seconds of real time calculations. State …

Variance reduction and noise source sampling techniques for Monte Carlo simulations of neutron noise induced by mechanical vibrations

H Belanger, D Mancusi, A Rouchon… - Nuclear Science and …, 2023 - Taylor & Francis
Neutron noise in nuclear power reactors refers to the small fluctuations around the average
neutron flux at steady state resulting from time-dependent perturbations inside the core. The …

High-fidelity treatment for object movement in time-dependent Monte Carlo transport simulations

I Variansyah, RG McClarren - arXiv preprint arXiv:2305.07641, 2023 - arxiv.org
We investigate the use of time-dependent surfaces in Monte Carlo transport simulation to
accurately model prescribed, continuous object movements. The performance of the …

Multigroup constant calculation with static α-eigenvalue Monte Carlo for time-dependent neutron transport simulations

I Variansyah, BR Betzler, WR Martin - Nuclear Science and …, 2020 - Taylor & Francis
Multigroup constants for deterministic methods that preserve the time-dependent physics of
the neutron transport equations are derived. Alternative multigroup constant weighting …