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 …

[HTML][HTML] Full core pin-level VVER-440 simulation of a rod drop experiment with the GPU-based Monte Carlo code GUARDYAN

D Legrady, G Tolnai, T Hajas, E Pazman, T Parko, I Pos - Energies, 2022 - mdpi.com
Targeting ultimate fidelity reactor physics calculations the Dynamic Monte Carlo (DMC)
method simulates reactor transients without resorting to static or quasistatic approximations …

Noise term modeling of dynamic Monte Carlo using stochastic differential equations

TZ Hajas, G Tolnai, M Margoczi, D Legrady - Annals of Nuclear Energy, 2024 - Elsevier
Abstract Dynamic Monte Carlo (DMC) method recently became a relevant tool to perform
kinetic calculations even on the scale of power plants and further to simulate coupled …

[HTML][HTML] Development of transient Monte Carlo in a fissile system with β-delayed emission from individual precursors using modified open source code OpenMC (TD)

J Romero-Barrientos, F Molina, JIM Damián… - Nuclear Engineering …, 2023 - Elsevier
Abstract In deterministic and Monte Carlo transport codes, β-delayed emission is included
using a group structure where all of the precursors are grouped together in 6 groups or …

A cell-based population control of Monte Carlo particles for the global variance reduction for transport equations

L Laguzet, G Turinici - Journal of Computational Physics, 2022 - Elsevier
We present a population control method with sampling and regulation steps for Monte Carlo
particles involved in the numerical simulation of a transport equation. We recall in the first …

Improving Monte Carlo reactor physics simulations using adaptive sampling of neutron histories

K Froehlicher - 2023 - inis.iaea.org
[en] Adaptive Multilevel Splitting (AMS) is a variance reduction method previously
implemented for neutron transport in shielding computation applications to perform variance …

Status and trends of kinetic Monte Carlo simulation in reactor physics

A Zoia - Risk-Informed Methods and Applications in Nuclear …, 2024 - Elsevier
Monte Carlo simulation is the reference method for reactor physics applications. Yet, the use
of Monte Carlo for time-dependent problems (operational or accidental reactor transients) is …

Improving variance estimation for time-dependent detectors in Monte Carlo dynamic calculations using adaptive sampling of neutrons

K Fröhlicher, M Brovchenko, J Taforeau… - M&C 2023-The …, 2023 - irsn.hal.science
Monte Carlo methods have been used for nuclear applications since the beginning of
scientific computing. Decades of method refinements now allow to perform simulations of …

Management of the UK plutonium stockpile using thorium fuelled Light Water Reactors

S Morrison - 2023 - repository.cam.ac.uk
The UK government is responsible for the world's largest stockpile of civil plutonium (Pu).
The intention is to manage the stockpile through the implementation of an appropriate …

Amélioration des simulations Monte Carlo en physique des réacteurs par échantillonnage adaptatif des histoires de neutrons

K Fröhlicher - 2023 - theses.hal.science
Adaptive Multilevel Splitting (AMS) is a variance reduction method previously implemented
for neutron transport in shielding computation applications to perform variance reduction for …