Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors

T Zhang, J Xiong, L Liu, Z Li, K Zhuang - Annals of Nuclear Energy, 2019 - Elsevier
This paper presents recent progress of the development and implementation of the integral
transport variational nodal method (VNM) to the neutronics modelling of hexagonal …

Reactor core design with enriched gadolinia burnable absorbers for soluble Boron-Free operation in the innovative SMR

JS Kim, G Bae, J Yoon - Nuclear Engineering and Design, 2024 - Elsevier
Effective strategies for maintaining reactor reactivity at a consistent level are indispensable
to enable soluble boron-free (SBF) operation in innovative small modular reactor (i-SMR) …

Development of an artificial neural network model for generating macroscopic cross-sections for RAST-AI

S Dzianisau, K Saeju, HC Lee, D Lee - Annals of Nuclear Energy, 2023 - Elsevier
Homogenized macroscopic cross-sections (XS) are necessary for running core-wise nodal
diffusion calculations. XS sets are usually generated using time-consuming lattice physics …

Super-homogenisation factors in pinwise calculations by the reactor dynamics code DYN3D

U Grundmann, S Mittag - Annals of Nuclear Energy, 2011 - Elsevier
Super-homogenisation (SPH) factors were generated by a modified version of the code
DYN3D for PWR fuel assemblies in hot-zero-power states defined in the OECD MOX/UO2 …

A Source-expansion-based method for transient Pin-Power reconstruction

J Bai, C Wan, Y Li, H Wu, F Li - Annals of Nuclear Energy, 2021 - Elsevier
In this paper, the transient pin-power reconstruction based on source-expansion method has
been proposed. The transient calculation is sufficient to simulate the reactor-physics process …

Acceleration of 3D pin-by-pin calculations based on the heterogeneous variational nodal method

T Zhang, H Wu, L Cao, Y Li - Annals of Nuclear Energy, 2018 - Elsevier
The pin-by-pin method with homogenization performed at the pin cell level is of
considerable interest in thermal reactor physics calculations. However, significant …

Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR

JJ Herrero, N García-Herranz, D Cuervo… - Annals of Nuclear …, 2012 - Elsevier
Performing three-dimensional pin-by-pin full core calculations based on an improved
solution of the multi-group diffusion equation is an affordable option nowadays to compute …

[HTML][HTML] Pin power reconstruction for hexagonal geometry in nodal neutronics program Ants

V Valtavirta, A Rintala, U Lauranto - Annals of Nuclear Energy, 2022 - Elsevier
The pin power reconstruction methodology for hexagonal geometry in the multigroup nodal
neutronics program Ants is described and verified against full core Serpent Monte Carlo …

Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor

A Peakman, R Gregg, T Bennett, M Casamor… - Annals of Nuclear …, 2022 - Elsevier
The increasing deployment of renewable energy sources and greater electrification of
demand is requiring more frequent use of load following in pressurised water reactors …

Implementation of a fast running full core pin power reconstruction method in DYN3D

AM Gomez-Torres, VH Sanchez-Espinoza… - … Engineering and Design, 2014 - Elsevier
This paper presents a substantial extension of the pin power reconstruction (PPR) method
used in the reactor dynamics code DYN3D with the aim to better describe the heterogeneity …