Results 11 to 20 of about 201,035 (291)

Design calculation of a vertical thermal neutron beam for neutron radiography at Esfahan MNSR [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2019
In this paper, the MCNPX code is applied for feasibility study of using the Isfahan MNSR as a neutron source for neutron radiography. To produce a good neutron beam in terms of intensity and quality, the aluminum (Al) with thickness of 0.7 cm, and ...
J Khorsandi   +3 more
doaj   +1 more source

Wake Shape and Height Profile Measurements in a Concave Open Channel Flow regarding the Target in DONES

open access: yesEnergies, 2021
Wakes appearing downstream of disturbances on the surface of a water flow in a concave open channel were examined experimentally. The investigated channel geometry was similar to the liquid lithium target in DONES (Demonstration fusion power plant ...
Björn Brenneis   +4 more
doaj   +1 more source

Monte Carlo simulation-aided design of a thermal neutron generator system from 241Am-Be isotopic sources

open access: yesBrazilian Journal of Radiation Sciences, 2023
Collimated thermal neutron beams are obtained from neutron extraction channels in nuclear reactors for various applications in research and technology, such as neutron imaging techniques (neutron radiography, neutron radioscopy, neutron tomography, and ...
Antônio Cezar Orozco   +2 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

Influence of thermal neutron scattering effect of FLiBe molten salt on neutronic performance of molten salt reactors

open access: yesHe jishu, 2023
BackgroundFLiBe is commonly used as the coolant and carrier salt in liquid molten salt reactors (MSRs). Its certain moderating properties and thermal neutron scattering attributes affect the neutronic performance of the MSR, and this in turn influences ...
ZHANG Zhicheng   +3 more
doaj   +1 more source

Thermal conductivity of neutrons in neutron star cores [PDF]

open access: yesAstronomy & Astrophysics, 2001
The diffusive thermal conductivity of neutrons in dense matter [$ρ\sim (1 - 8) \times 10^{14}$ g cm$^{-3}$] of neutron star cores is calculated. The contribution from neutron--neutron and neutron--proton collisions is taken into account. We use the transition probabilities calculated for symmetric dense nucleon matter on the basis of the Dirac ...
Baiko, D. A.   +2 more
openaire   +2 more sources

Experimental confirmation of a new method for selective neutron separation [PDF]

open access: yesNuclear Energy and Technology, 2020
The article presents an experimental confirmation of the operability of neutron concentrators in devices that form and use directed high-intensity thermal neutron beams with elliptical channels made as blocks of profiled graphite and aluminum plates. The
Yuri V. Drobyshevsky   +5 more
doaj   +3 more sources

Measurement of temperature-dependent thermal neutron spectrum in CaH2 moderator material for space reactor [PDF]

open access: yesEPJ Web of Conferences, 2020
In order to accurately design a CaH2 moderated small high-temperature reactor, it is necessary to experimentally confirm the temperature-dependent thermal neutron spectrum in the CaH2 moderator material.
lee Jaehong   +6 more
doaj   +1 more source

Numerical simulation of controllable source neutron porosity logging based on CLYC detector

open access: yesHe jishu, 2021
BackgroundUsing Cs2LiYCl6:Ce (CLYC) instead of 3He detector in neutron porosity logging has become a new idea for the development of logging tools.PurposeThis study aims to investigate the feasibility of using a new CLYC crystal based detector in neutron
ZHOU Yue   +4 more
doaj   +1 more source

Thermal neutron albedo and flux for different geometries neutron guide

open access: yesNuclear Engineering and Technology, 2019
This paper presents a study on thermal neutron reflection properties of neutron guide for cylinder, spindle, elliptic and parabolic geometries using 241Am-Be neutron source (5.2 Ci) and BF3 detector, whereas neutron guide is important instrument for ...
S. Azimkhani   +2 more
doaj   +1 more source

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