Fast neutron detection efficiency of ATLAS-MPX detectors for the evaluation of average neutron energy in mixed radiation fields

2011 ◽  
Vol 633 ◽  
pp. S226-S230 ◽  
Author(s):  
J. Bouchami ◽  
A. Gutiérrez ◽  
T. Holý ◽  
V. Král ◽  
C. Lebel ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Neutron Energy ◽  
Detection Efficiency ◽  
Neutron Detection ◽  
Radiation Fields ◽  
Fast Neutron Detection ◽  
Neutron Detection Efficiency ◽  
Average Neutron ◽  
Average Neutron Energy

scholarly journals Measurement of fast neutron detection efficiency with 6Li and 7Li enriched CLYC scintillators

2016 ◽  
Vol 763 ◽  
pp. 012006 ◽  
Author(s):  
A Mentana ◽  
F Camera ◽  
A Giaz ◽  
N Blasi ◽  
S Brambilla ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Detection Efficiency ◽  
Neutron Detection ◽  
Fast Neutron Detection ◽  
Neutron Detection Efficiency

scholarly journals Fast neutron detection efficiency of 6Li and 7Li enriched CLYC scintillators using an Am-Be source

2018 ◽  
Vol 13 (11) ◽  
pp. P11010-P11010 ◽  
Author(s):  
N. Blasi ◽  
S. Brambilla ◽  
F. Camera ◽  
S. Ceruti ◽  
A. Giaz ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Detection Efficiency ◽  
Neutron Detection ◽  
Fast Neutron Detection ◽  
Neutron Detection Efficiency

Average neutron detection efficiency for DEMON detectors

2013 ◽  
Vol 709 ◽  
pp. 68-71 ◽  
Author(s):  
S. Zhang ◽  
W. Lin ◽  
M.R.D. Rodrigues ◽  
M. Huang ◽  
R. Wada ◽  
...  
Keyword(s):  
Detection Efficiency ◽  
Neutron Detection ◽  
Neutron Detection Efficiency ◽  
Average Neutron

scholarly journals Impact of average neutron energy on the fast neutron fluency measurement by Np237 fission to capture ratio and reverse dark current of planar silicon detector methods

2019 ◽  
Vol 204 ◽  
pp. 04002
Author(s):  
M. Szuta ◽  
S. Kilim ◽  
E. Strugalska-Gola ◽  
M. Bielewicz ◽  
N.I. Zamyatin ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Cross Section ◽  
Neutron Energy ◽  
Silicon Detector ◽  
Nuclear Data ◽  
Capture Cross ◽  
Silicon Detectors ◽  
Planar Silicon ◽  
Average Neutron ◽  
Average Neutron Energy

This work is a subsequent step to study the feasibility of fast neutron fluency measurements using two different complementary methods. Np-237 samples and planar silicon detectors were mounted very close to each other on different sections of a subcritical assembly irradiated with the proton beam of 0,66 GeV (the Quinta assembly at the Joint Institute for Nuclear Research, Dubna, Russia) to provide both samples with the same neutron fluency. We have processed the experimental data of irradiated Np-237 actinide samples and silicon detectors directly placed on two sections of the QUINTA setup without a lead shield-reflector. Applying the try and error method we have found found that the neutron energy for which the ratio of the fission cross section to the capture cross section of the actinide Np-237 from the nuclear data base is equal to the measured ratio of the fissioned and captured actinide isotopes. The retrieved distinct fission and capture cross sections for the distinct neutron energy from the nuclear data base describe the average values. The considered above experimental and earlier obtained data have been shown that the higher is the average neutron energy the smaller is the difference of the neutron fluency measurement between the two methods. This effect has been expected since the silicon detector method efficiently measures the fast neutrons of the energy higher than about 170 keV while the actinide method covers a wider energy range.

Behaviour of BeCu dynode photomultiplier tubes in high radiation fields and their use in fast neutron detection

1988 ◽  
Vol 35 (1) ◽  
pp. 368-371
Author(s):  
J.K. Mayer ◽  
J.J.G. Durocher ◽  
G.R. Smith
Keyword(s):  
Fast Neutron ◽  
Neutron Detection ◽  
High Radiation ◽  
Photomultiplier Tubes ◽  
Radiation Fields ◽  
Fast Neutron Detection

Measurements of the cross-section of 111Cd(n,n′)111mCd reaction for 241Am/Be neutrons

2021 ◽  
pp. 2150084
Author(s):  
G. S. M. Ahmed ◽  
M. Tohamy ◽  
P. Bühler ◽  
M. N. H. Comsan
Keyword(s):  
Cross Section ◽  
Neutron Energy ◽  
Cross Sections ◽  
Detection Efficiency ◽  
Neutron Fluence ◽  
Reaction Products ◽  
The Cross ◽  
Cadmium Target ◽  
Average Neutron ◽  
Average Neutron Energy

The cross-section of the [Formula: see text] reaction was measured with [Formula: see text] neutrons using a natural cadmium target [Formula: see text]. The neutron fluence and mean neutron energy of the source were determined using the ISO 8529-1 neutron spectrum and the known cross-sections of the monitor reaction [Formula: see text]. In order to measure the poor [Formula: see text]-ray activity of the reaction products, an HPGe detector with 70% detection efficiency surrounded by an adequate graded shield was applied. The efficiency calculations for the detector were performed using standard point calibration sources and the EFFTRAN efficiency code. Using the measured values of the neutron flux and the induced [Formula: see text]-ray activity of [Formula: see text], the cross-section of the [Formula: see text] reaction at the average neutron energy of 4.05 MeV was found to be [Formula: see text] mb. An estimation of the contribution to the total cross-section by the accompanied reactions [Formula: see text] and [Formula: see text] was achieved and the related cross-sections were found to be 0.16 mb and 8.99 mb, respectively.

scholarly journals LiCaAlF6 scintillators in neutron and gamma radiation fields

2016 ◽  
Vol 44 ◽  
pp. 1660234 ◽  
Author(s):  
L. Viererbl ◽  
V. Klupák ◽  
M. Vinš ◽  
M. Koleška ◽  
J. Šoltés ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Fast Neutron ◽  
Single Crystals ◽  
Pulse Height ◽  
Neutron Detection ◽  
Light Signal ◽  
Radiation Fields ◽  
Radiation Sources ◽  
Two Samples ◽  
Fast Neutron Detection

Intentionally doped LiCaAlF6 (LiCAF) single crystals are prospective scintillators, especially for thermal neutron detection through the 6Li(n,t)4He nuclear reaction. Four different LiCAF scintillator samples were tested in various neutron and gamma fields. Two of the tested samples were LiCAF:Eu and LiCAF:Eu,Na single crystals, and another two samples were made of LiCAF:Eu micro crystals dispersed in transparent rubber, with different rubber dimensions. All LiCAF samples contain lithium enriched to[Formula: see text]Li. A plutonium–beryllium source was used as a neutron source. The neutron spectrum was modified by moderator and filter to get different ratios between thermal, epithermal and fast neutron fluence rates. The MCNP code was used for calculations of the fluence rates for different configurations. Radionuclides [Formula: see text]Cs and [Formula: see text]Co were applied as gamma radiation sources. The light signal from the scintillator was evaluated with a photomultiplier and a multichannel analyzer. The purpose of this work was to study the characteristics of LiCAF scintillators, especially the ability to discriminate signals from neutron and gamma radiation, which is the basic scintillator condition for neutron detection in mixed neutron-gamma radiation fields. Generally, the discrimination can be done by the pulse height and/or the pulse shape of the evaluated signals. Both methods can be used for a LiCAF scintillator. However, only the pulse height discrimination method is discussed in this paper. The possibility of fast neutron detection with LiCAF scintillators was also tested.

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