Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis

J Wang, Q Wang, M Ding - Annals of Nuclear Energy, 2020 - Elsevier
In an operating nuclear reactor system, various physical phenomena of different properties
are intimately linked. These multiphysics phenomena include neutronics (N), thermal …

Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods

Y Ma, M Liu, B Xie, W Han, H Yu, S Huang… - Annals of Nuclear …, 2021 - Elsevier
Improved computer capabilities and parallel algorithms have enabled high fidelity coupled
analyses of classical nuclear power plant designs, which can also be applied to analyze the …

Implementation of Grey Wolf Optimization (GWO) algorithm to multi-objective loading pattern optimization of a PWR reactor

A Naserbegi, M Aghaie, A Zolfaghari - Annals of Nuclear Energy, 2020 - Elsevier
Loading pattern optimization (LPO) is a main issue of in-core fuel management. In this work,
the Grey Wolf Optimizer (GWO) algorithm based on behavior of gray wolves for hunting is …

An assessment of a VVER-1000 core during Turbo-Generator load reduction test using RELAP5/MOD3. 2 and WIMSD-5B/PARCSv2. 7

N Vahman, R Akbari-Jeyhouni, DR Ochbelagh… - Progress in Nuclear …, 2016 - Elsevier
Reactor dynamic tests, which are categorized as one of the power start-up test groups, are
the most complex tests during commissioning of the new nuclear power plants. This paper …

[HTML][HTML] Development and application in multiscale and multiphysics methodologies in Spain: Present and future trends

S Gallardo, F Álvarez-Velarde, T Barrachina… - … Engineering and Design, 2024 - Elsevier
In the field of reactor physics analysis, the coupling of multiple physics phenomena plays a
crucial role in enhancing the accuracy of predictions and understanding complex systems …

Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: Development and testing based on a computational …

JR Basualdo, V Sánchez-Espinoza, R Stieglitz… - Progress in Nuclear …, 2020 - Elsevier
This paper describes the coupling of the subchannel code SubChanFlow developed at the
Karlsruhe Institute of Technology (KIT) with the reactor dynamics diffusion code PARCS. The …

Thermal hydraulic analysis of the PWR with high uranium density accident tolerant fuels under accident transients with and without reactivity

S He, J Cai - Nuclear Engineering and Design, 2019 - Elsevier
High uranium density accident tolerant fuel (ATF) with high economy and safety seems to be
one of the most promising candidates to replace UO 2 in future reactor. The thermal …

Thermal hydraulic analysis of accident tolerant fuels for Reactivity-Initiated-Accident in PWR with different coolant channel geometries

S He, J Cai, Z Chen, R Liu - Nuclear Engineering and Design, 2019 - Elsevier
This paper describes use of sub-channel analysis code COBRA-EN to assess the thermal
hydraulic performance and influence of different coolant channel geometries on several …

Validation of DDC-3D code system for neutronics and thermal-hydraulics coupling analysis using BEAVRS benchmark

B Zhang, Z Liu, X Yuan, Y Zhang, J Zhou… - … Engineering and Design, 2024 - Elsevier
The direct whole-core calculations can provide accurate results and insights to the physics
phenomena of the reactor. It can also capture the local effects of temperature and density …

Full scope simulation of VVER-1000 blowdown source and containment pressurization in a LBLOCA by parallel coupling of TRACE and CONTAIN

O Safarzadeh, O Noori-kalkhoran, M Gei… - Progress in Nuclear …, 2021 - Elsevier
Nuclear power plants containment plays an important role as last-defined barrier in defense
in depth approach against the release of radioactive material to the environment. In this …