Results 21 to 30 of about 1,543,124 (347)

Neutrons production on the IPHI accelerator for the validation of the design of the compact neutron source SONATE [PDF]

open access: yesEPJ Web of Conferences, 2020
We aim at building a compact accelerator-based neutron source (CANS) which would provide a thermal neutron flux on the order of 4x1012 n.s-1.cm-2.sr-1. Such a brilliance would put compact neutron sources on par with existing medium flux neutron research ...
Tran Hoang Ngoc   +10 more
doaj   +1 more source

System and process of thermal neutron flux producing by means of an accelerator base electron of 18 MeV

open access: yesEurasian Journal of Physics and Functional Materials, 2021
Neutrons are produced in accelerators by irradiating heavy targets with an electron or proton beam. Produced neutrons are of high energy. The purpose of our work is optimization the neutron flux by MCNP-6 code for production the thermal neutron flux ...
A. .. Didi   +5 more
doaj   +1 more source

Measurement of the neutron flux at spallation sources using multi-foil activation [PDF]

open access: yesNuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment, 2018
Activation analysis is used in this work to measure the flux of a fast neutron beamline at a spallation source over a wide energy spectrum, extending from thermal to hundreds of MeV.
D. Chiesa   +7 more
semanticscholar   +1 more source

Tolerance Flux of Thermal Neutrons [PDF]

open access: yesNature, 1949
THE danger of neutrons on the human body arises from two factors : the slowing down of fast neutrons and the absorption of neutrons. In the case of thermal neutrons, only absorption can take place, either in hydrogen to form a deuteron with emission of a 2.2-MeV. γ-ray, or by nitrogen-14 to form a carbon, with the emission of a 0.7-MeV. proton.
P, CAPRON, M, FAES, G C, TAVERNIER
openaire   +2 more sources

Development and nuclear characteristic testing of a mobile miniature fission ionization chamber neutron detector

open access: yesHe jishu, 2023
BackgroundThe miniature fission ionization chamber is a widely used neutron detector for the in-core neutron flux monitoring of a nuclear reactor. Typically, the in-core neutron flux rate measurement system of a domestic CPR1000 nuclear power unit adopts
YAN Jie   +7 more
doaj   +1 more source

TRIGA reactor absolute neutron flux measurement using activated isotopes

open access: yesProgress in Nuclear Energy, 2014
Antonio Cammi, D Chiesa, M Clemenza
exaly   +2 more sources

Current compensation for material consumption of cobalt self-powered neutron detector

open access: yesNuclear Engineering and Technology, 2020
Co Self-Powered Neutron Detector (SPND) is confronted with the problem of material consumption, which causes the response current can neither reflect the change of neutron flux in time nor be proportional to the neutron flux.
Xinxin Liu   +4 more
doaj   +1 more source

Thermal neutron flux distribution in ET-RR-2 reactor thermal column [PDF]

open access: yesNuclear Technology and Radiation Protection, 2002
The thermal column in the ET-RR-2 reactor is intended to promote a thermal neutron field of high intensity and purity to be used for following tasks: (a) to provide a thermal neutron flux in the neutron transmutation silicon doping, (b) to provide a ...
Imam Mahmoud M., Roushdy Hassan
doaj   +1 more source

Beam Shaping Assembly Optimization for Boron Neutron Capture Therapy Facility based on Cyclotron 30 MeV as Neutron Source

open access: yesASEAN Journal on Science and Technology for Development, 2018
A design of beam shaping assembly (BSA) installed on cyclotron 30 MeV model neutron source for boron neutron capture therapy (BNCT) has been optimized using simulator software of Monte Carlo N-Particle Extended (MCNPX).
Arief Fauzi   +3 more
doaj   +1 more source

Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code

open access: yesJournal of Radiation Research and Applied Sciences, 2018
Comparative studies for conversion of the fuel from high enriched uranium (HEU) to low enriched uranium (LEU) in the reactor (MNSR) were performed using DRAGON code deterministic. In this work the HEU fuel (UAl4-Al, 90% enriched with Al-clad) and LEU (12.
Jamal Al Zain   +3 more
doaj   +1 more source

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