Dynamic modeling and two-degree-of-freedom controller design for pressurized water reactor core
Sign Up to like & getrecommendations! Published in 2021 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2020.108043
Abstract: Abstract The task of this investigation is to model pressurized water reactor core and design a reactor power controller that has a strong robustness in various operating conditions. The comparisons of different nodal models of… read more here.
Keywords: two degree; freedom controller; controller; reactor core ... See more keywords
Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2020.05.003
Abstract: Abstract To study the thermophysical and neutronic properties of thorium-plutonium fuel, a conceptual design of a hybrid facility consisting of a subcritical Th–Pu reactor core and a source of additional D-D neutrons that places on… read more here.
Keywords: facility; source; magnetic trap; reactor core ... See more keywords
Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2020.11.023
Abstract: Abstract The operation of the nuclear reactor requires accurate and fast methods and techniques for analysing its kinetics. These techniques become even more important when the MOX-fuel is used due to the lower value of… read more here.
Keywords: analysis; reactor core; mox fuel; birth death ... See more keywords
SMART reactor core design optimization based on FCM fuel
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2020.110970
Abstract: Abstract Fully ceramic microencapsulated (FCM) fuel is originally proposed for replacement in light water reactors (LWRs) to enhance thermal hydraulic performance and reactor safety features. However, reactor core cycle length might be degraded by the… read more here.
Keywords: reactor core; reactor; smart reactor; fcm fuel ... See more keywords
A PCA compression method for reactor core transient multiphysics simulation
Sign Up to like & getrecommendations! Published in 2020 at "Progress in Nuclear Energy"
DOI: 10.1016/j.pnucene.2020.103441
Abstract: Abstract The paper deals with the adaptation and application of the data compression algorithms to reactor core multiphysics analysis. Large capacity makes the storage, transfer and processing of multiphysics data cumbersome and expensive. The general… read more here.
Keywords: compression; pca compression; method; reactor core ... See more keywords
Towards an End-to-end Radiation Defect Quantitative Characterization Workflow Using Advanced Microscopy Images
Sign Up to like & getrecommendations! Published in 2020 at "Microscopy and Microanalysis"
DOI: 10.1017/s1431927620016980
Abstract: The safety and reliability of next-generation fission and future fusion energy systems depend in-part on the development of advanced reactor core structural materials. Changes in mechanical properties of nuclear reactor core structural materials under a… read more here.
Keywords: microscopy; towards end; radiation; core structural ... See more keywords
AI-based design of a nuclear reactor core
Sign Up to like & getrecommendations! Published in 2021 at "Scientific Reports"
DOI: 10.1038/s41598-021-98037-1
Abstract: The authors developed an artificial intelligence (AI)-based algorithm for the design and optimization of a nuclear reactor core based on a flexible geometry and demonstrated a 3× improvement in the selected performance metric: temperature peaking… read more here.
Keywords: reactor core; geometry; nuclear reactor; design ... See more keywords
Uncertainty Quantification Approach for the Versatile Test Reactor Core Design
Sign Up to like & getrecommendations! Published in 2022 at "Nuclear Science and Engineering"
DOI: 10.1080/00295639.2022.2035181
Abstract: Abstract The Versatile Test Reactor (VTR) is being developed to provide a flexible source of neutrons for the accelerated testing of materials. To support this flexibility, the design must be informed by uncertainty assessment that… read more here.
Keywords: test reactor; uncertainty; versatile test; core design ... See more keywords
Electrical Resistivity Reconstruction of Graphite Moderator Bricks From Multi-Frequency Measurements and Artificial Neural Networks
Sign Up to like & getrecommendations! Published in 2021 at "IEEE Sensors Journal"
DOI: 10.1109/jsen.2021.3080127
Abstract: This paper discusses an artificial neural inversion approach for non-destructive testing of the graphite moderator bricks that make up the cores of Advanced Gas-Cooled Reactors (AGR). The study employed fully connected feedforward neural networks consisting… read more here.
Keywords: graphite moderator; multi frequency; neural networks; artificial neural ... See more keywords