Design of reduced size long counter with flat response function from few keV to 20 MeV [PDF]
Nuclear Technology and Radiation Protection, 2016 In this study, a reduced size neutron long counter with improved response function was designed using SuperMC simulation code. The main parts of the reduced size long counter are 3He proportional counter, cylindrical moderators made of ...
Mazunga Mohamed +3 more
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Specifications for a coupled neutronics thermal-hydraulics SFR test case [PDF]
, 2017 Coupling neutronics/thermal-hydraulics calculations for the design of nuclear reactors is a growing trend in the scientific community. This approach allows to properly represent the mutual feedbacks between the neutronic distribution and the thermal ...
TASSONE, ALESSANDRO
core +1 more source
Development of Gd-Si-O dispersed 316L stainless steel for improving neutron shielding performance
Nuclear Materials and Energy, 2020 The low solubility of gadolinium (Gd) limits its application in iron-based neutron shielding alloys. In this study, a high content of Gd up to 7.87 wt.% was added into 316L stainless steel by mechanical alloying (MA) of Gd2O3 with 316L powder. Neutronics
Xinyi Yang +5 more
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Measurement and Analysis of Neutron Leakage Spectra from Pb and LBE Cylinders with D-T Neutrons
EPJ Web of Conferences, 2017 For validating the current evaluated neutron data libraries, neutron leakage spectra from lead and lead bismuth eutectic (LBE) cylinders have been measured using an intense D-T pulsed neutron source with time-of-flight (TOF) method by Institute of ...
Chen Size +6 more
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Core design optimization for a novel heavy water moderated molten salt reactor
He jishu, 2021 BackgroundHeavy water moderated molten salt reactor (HWMSR) adopts heavy water as moderator and heavy metal elements dissolved in fluoride salt as the fuel, which has high neutron economy. But large temperature difference of fuel salt outlet will lead to
WU Jianhui +6 more
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ADAPTIVE SOLUTION OF THE NEUTRON DIFFUSION EQUATION WITH HETEROGENEOUS COEFFICIENTS USING THE MIXED FINITE ELEMENT METHOD ON STRUCTURED MESHES [PDF]
EPJ Web of Conferences, 2021 The neutron transport equation can be used to model the physics of the nuclear reactor core. Its solution depends on several variables and requires a lot of high precision computations.
Do Minh-Hieu +2 more
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The hybrid model for sampling multiple elastic scattering angular deflections based on Goudsmit-Saunderson theory [PDF]
Nuclear Technology and Radiation Protection, 2017 An algorithm for the Monte Carlo simulation of electron multiple elastic scattering based on the framework of SuperMC (Super Monte Carlo simulation program for nuclear and radiation process) is presented.
Wasaye Muhammad Abdul +4 more
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Frontiers in Energy Research, 2021 Tritium breeding blanket (TBB) is an essential component in a fusion reactor, which has functions of tritium breeding, energy generation, and neutron shielding.
Shen Qu +6 more
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Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module [PDF]
, 2016 © 20xx IEEE. Personal use of this material is permitted. Permission from IEEE must be obtained for all other uses, in any current or future media, including reprinting/republishing this material for advertising or promotional purposes, creating new ...
Fernández, I. +6 more
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Applied Sciences, 2023 The Plasma Facing Components (PFCs) of the divertor target contribute to the fundamental functions of heat removal and particle exhaust during fusion operation, being subjected to a very hostile and complex loading environment characterized by intense ...
Simone Noce +8 more
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