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High-resolution neutronics model for 238Pu production in high-flux reactors
We proposed and compared three methods (filter burnup, single energy burnup, and burnup extremum analysis) to build a high-resolution neutronics...
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Application and Validation of an Improved One-to-Many Method to CFETR Neutronics Modeling
China fusion engineering test reactor (CFETR) is a magnetic confinement device which will fill the gap between the fusion experimental reactor and...
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Experimental Neutronics Investigations of Nuclear Propulsion Reactors on Prototype Test Bases
Aspects of experimental investigations of the physical characteristics of reactor cores, performed at Aleksandrov NITI as part of tests conducted on...
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Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage
The approaches used in the EUCLID/V2 integrated code to calculate the core neutronics of a sodium-cooled fast reactor at the core destruction stage...
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Implementation of high-fidelity neutronics and thermal–hydraulic coupling calculations in HNET
To perform nuclear reactor simulations in a more realistic manner, the coupling scheme between neutronics and thermal-hydraulics was implemented in...
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Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities
An approach to providing computational support for tests of TNPPs on prototype stands using software tools for the integrated modeling of neutronics...
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Calculating the Neutronics of a Yalina–Thermal Subcritical Assembly Using the Physical Birth-and-Death Model
AbstractParameters of the Yalina–Thermal neutron-multiplying medium are calculated using a physical model of the birth and death of particles. The...
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Verification and Validation of a Thermohydraulics-Neutronics Software Package for Calculating Transient Regimes in Heavy-Water Reactor Installations
A software package was developed for coupled thermohydraulic and three-dimensional neutronics calculations of a core in transient regimes of...
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Neutronics analysis of a subcritical blanket system driven by a gas dynamic trap-based fusion neutron source for 99Mo production
Gamma-emitting radionuclide 99m Tc is globally used for the diagnosis of various pathological conditions owing to its ideal single-photon emission...
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Calculation and Experimental Determination of the Neutronics Characteristics of the IRT-T Research Reactor
The results of calculations and experimental determination of the neutronics characteristics of the IRT-T research reactor are presented. The IRT-T...
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Coupled Neutronics and Thermal-Fluid Calculation for Prismatic High-Temperature Gas-Cooled Reactor Core at Steady State
With the rapid development of high-performance computers, high-precision, multi-scale and multi-physics coupling has become one of the main research...
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Neutronics and Thermal-Hydraulics Coupling Analysis of Integral Inherently Safe Fluoride-Salt-Cooled High-Temperature Advanced Reactor - Fustar
The integral inherently safe fluoride salt cooled high-temperature advanced reactor – FuSTAR is designed by **’an Jiaotong University with the...
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Neutronics assessment for Detailed Helium-Cooled And Water-Cooled DEMO Breeder Blanket Concepts
The Water-Cooled Lithium–Lead Breeding Blanket (WCLL) and Helium-Cooled Pebble Bed (HCPB) are two leading breeding blanket concept candidates to...
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Development of cosVMPT and Application of Creating 3D Neutronics Model for 360-Degree CFETR
In order to conduct nuclear analyses for Chinese Fusion Engineering Testing Reactor (CFETR) according to the latest design, it is necessary to...
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One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations
Low-concentration nuclides – impurity nuclides – are increasingly in demand in radiochemistry for defining more precisely the neutronic...
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Development and Preliminary Verification of a Neutronics-Thermal Hydraulics Coupling Code for Research Reactors with Unstructured Meshes
To maximize their adaptability and versatility, research reactors are designed to adapt to various operational conditions. These requirements result...
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Neutronics analysis of a stacked structure for a subcritical system with LEU solution driven by a D-T neutron source for 99Mo production
The utilization of neutrons markedly affects the medical isotope yield of a subcritical system driven by an external D-T neutron source. The general...
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Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant
The efficacy of uranium and thorium waste in a blanket of a thermonuclear plant, whose tasks are breeding of tritium as fuel for a thermonuclear...
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Neutronics of Lead and Bismuth
Cross-section uncertainties of Pb and Bi isotopes could consequently affect the precision of nuclear design calculations of preliminary analyses,...
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Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor
The possibility of using a tokamak as a DT-fusion reactor source of fast neutrons for irradiating waste uranium in order to produce energy and...