Results 11 to 20 of about 25,004 (172)

Percolation properties of the neutron population in nuclear reactors. [PDF]

open access: yesPhysical Review E, 2022
Reactor physics aims at studying the neutron population in a reactor core under the influence of feedback mechanisms, such as the Doppler temperature effect.
B. Dechenaux   +2 more
semanticscholar   +1 more source

Adjusting the nuclear reactor's neutron transport and diffusion theory for an alternative description and modelling of postage or supplies delivery processes

open access: yes, 2021
There seems to exist significant similarities between a reactor system and a supply chain from collection to delivery. In the reactor case, neutrons are continuously produced and absorbed in nuclear fuel. In a supply system case, items are continuously collected and continuously delivered to destinations.
openaire   +2 more sources

Perturbation Theory-Based Whole-Core Eigenvalue Sensitivity and Uncertainty (SU) Analysis via a 2D/1D Transport Code

open access: yesScience and Technology of Nuclear Installations, 2020
For nuclear reactor physics, uncertainties in the multigroup cross sections inevitably exist, and these uncertainties are considered as the most significant uncertainty source. Based on the home-developed 3D high-fidelity neutron transport code HNET, the
Ji Ma, Chen Hao, Lixun Liu, Yuekai Zhou
doaj   +1 more source

Parareal in time 3D numerical solver for the LWR Benchmark neutron diffusion transient model [PDF]

open access: yes, 2014
We present a parareal in time algorithm for the simulation of neutron diffusion transient model. The method is made efficient by means of a coarse solver defined with large time steps and steady control rods model.
Baudron, Anne-Marie A. -M.   +4 more
core   +5 more sources

Pin-by-pin Calculation of Reactor Core-Based on Quasi-diffusion in Rectangular Grid

open access: yesYuanzineng kexue jishu, 2023
Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety analysis. The second generation of core calculation theory and methods based on advanced component homogenization theory and modern coarse grid block ...
YAN Jiangtao;LIU Kun;ZHUANG Kun;WANG Senshan;ZHANG Kaihui;ZHANG Xinxin
doaj  

Development of a Spatial Domain Decomposition Scheme for Monte Carlo Neutron Transport

open access: yesVolume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform large-scale neutron transport simulations, such as full-core burnup or high-fidelity multiphysics.
Manuel García   +5 more
semanticscholar   +1 more source

Non-classical transport with angular-dependent path-length distributions. 2: Application to pebble bed reactor cores

open access: yes, 2013
We describe an analysis of neutron transport in the interior of model pebble bed reactor (PBR) cores, considering both crystal and random pebble arrangements.
Larsen, Edward W., Vasques, Richard
core   +1 more source

A Novel Adjoint-Based Reduced-Order Model for Depletion Calculations in Nuclear Reactor Physics

open access: yesEnergies
The licensing of new reactors implies the use of verified and validated neutronic codes. Numerical validation can rely on sensitivity and uncertainty studies, but they require repeated execution of time-consuming neutron flux and depletion calculations ...
T. Sauzedde, P. Archier, F. Nguyen
semanticscholar   +1 more source

Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference

open access: yes, 2016
A Monte Carlo-based Bayesian inference model is applied to the prediction of reactor operation parameters of a PWR nuclear power plant. In this non-perturbative framework, high-dimensional covariance information describing the uncertainty of microscopic ...
Ahnert, Carolina   +5 more
core   +2 more sources

Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module

open access: yesEPJ Nuclear Sciences & Technologies, 2016
In nuclear safety research, the quality of the results of simulation codes is widely determined by the reactor design and safe operation, and the description of neutron transport in the reactor core is a feature of particular importance.
Labarile Antonella   +4 more
doaj   +1 more source

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