Log in

Relevant bibliographies by topics / Fast Neutron Detectors / Journal articles

To see the other types of publications on this topic, follow the link: Fast Neutron Detectors.

Journal articles on the topic 'Fast Neutron Detectors'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the top 50 journal articles for your research on the topic 'Fast Neutron Detectors.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Browse journal articles on a wide variety of disciplines and organise your bibliography correctly.

1

Kushoro, Matteo Hakeem, Marica Rebai, Marco Tardocchi, et al. "Detector Response to D-D Neutrons and Stability Measurements with 4H Silicon Carbide Detectors." Materials 14, no. 3 (2021): 568. http://dx.doi.org/10.3390/ma14030568.

Full text

Abstract:

The use of wide-band-gap solid-state neutron detectors is expanding in environments where a compact size and high radiation hardness are needed, such as spallation neutron sources and next-generation fusion machines. Silicon carbide is a very promising material for use as a neutron detector in these fields because of its high resistance to radiation, fast response time, stability and good energy resolution. In this paper, measurements were performed with neutrons from the ISIS spallation source with two different silicon carbide detectors together with stability measurements performed in a laboratory under alpha-particle irradiation for one week. Some consideration to the impact of the casing of the detector on the detector’s counting rate is given. In addition, the detector response to Deuterium-Deuterium (D-D) fusion neutrons is described by comparing neutron measurements at the Frascati Neutron Generator with a GEANT4 simulation. The good stability measurements and the assessment of the detector response function indicate that such a detector can be used as both a neutron counter and spectrometer for 2–4 MeV neutrons. Furthermore, the absence of polarization effects during neutron and alpha irradiation makes silicon carbide an interesting alternative to diamond detectors for fast neutron detection.

APA, Harvard, Vancouver, ISO, and other styles

2

Xing, Zhen Ni, Yang Liu, Guo Zheng Zhu, and Shao Bei Luo. "Neutron Radiation Detection." Applied Mechanics and Materials 668-669 (October 2014): 932–35. http://dx.doi.org/10.4028/www.scientific.net/amm.668-669.932.

Full text

Abstract:

The basic principle of neutron detection was proposed in the twentieth century, especially G.F.Knoll compiled Radiation Detection And Measurement in 1979, including detailed in principles and methods of radiation detection and measurement on a variety of hot and fast neutrons. In recent decades there is not have a big breakthrough on the principle of neutron detection development, but there is a great improvement in the performance and scope of neutron detectors. Depending on the working principle of neutron detector, it is roughly divided into the following three: Gas detectors, Semiconductor detectors and Scintillator detector.

APA, Harvard, Vancouver, ISO, and other styles

3

CHATZAKIS, J., S. M. HASSAN, E. L. CLARK, A. TALEBITAHER, and P. LEE. "IMPROVED DETECTION OF FAST NEUTRONS WITH SOLID-STATE ELECTRONICS." International Journal of Modern Physics: Conference Series 27 (January 2014): 1460138. http://dx.doi.org/10.1142/s2010194514601380.

Full text

Abstract:

There is an increasing requirement for alternative and improved detection of fast neutrons due to the renewed interest in neutron diagnostics applications. Some applications require heavily shielded neutron sources that emit a substantial proportion of their emission as fast neutrons and so require high performance fast neutron detectors. In some applications, the detection of neutron bursts from pulsed neutron sources has to be synchronized to the repetition rate of the source. Typical fast neutron detectors incorporate scintillators that are sensitive to all kinds of ionizing radiations as well as neutrons, and their efficiency is low. In this paper, we present a device based on the principle of neutron activation coupled to solid-state p-i-n diodes connected to a charge amplifier. The charge amplifier is specially developed to operate with high capacitance detectors and has been optimized by the aid of the SPICE program. A solid-state pulse shaping filter follows the charge amplifier, as an inexpensive solution, capable to provide pulses that can be counted by a digital counter.

APA, Harvard, Vancouver, ISO, and other styles

4

Ouladdiaf, Bachir, Marie-Hélène Lemée-Cailleau, John Allibon, Juan Rodriguez-Carvajal, and Laurent Chapon. "Fast Neutron Laue Diffraction with CCD Detectors." Acta Crystallographica Section A Foundations and Advances 70, a1 (2014): C684. http://dx.doi.org/10.1107/s2053273314093152.

Full text

Abstract:

The large area neutron Laue diffractometer based on CCD detectors (CYCLOPS [1]) has been developed and recently completed at the ILL. High-quality Laue patterns covering an angular range of 3600horizontally and 920vertically, can be obtained in only few seconds. The diffractometer excels for fast survey of reciprocal space and fast data collections through phase transitions as well as in-situ experiments on single crystals with time resolution similar to that obtained with powder diffraction. The detector is being upgraded with new faster CCD cameras having a larger dynamic range. A protocol for detector corrections from spatial distortions and uniformity response has been established which allows to obtain accurate integrated intensities leading to good structural refinements. Examples of results of phase transitions and structural investigations will be presented.

APA, Harvard, Vancouver, ISO, and other styles

5

Ryzhikov, Vladimir D., Sergei V. Naydenov, Thierry Pochet, Gennadiy M. Onyshchenko, Leonid A. Piven, and Craig F. Smith. "Advanced Multilayer Composite Heavy-Oxide Scintillator Detectors for High Efficiency Fast Neutron Detection." EPJ Web of Conferences 170 (2018): 07010. http://dx.doi.org/10.1051/epjconf/201817007010.

Full text

Abstract:

We have developed and evaluated a new approach to fast neutron and neutron-gamma detection based on large-area multilayer composite heterogeneous detection media consisting of dispersed granules of small-crystalline scintillators contained in a transparent organic (plastic) matrix. Layers of the composite material are alternated with layers of transparent plastic scintillator material serving as light guides. The resulting detection medium – designated as ZEBRA – serves as both an active neutron converter and a detection scintillator which is designed to detect both neutrons and gamma-quanta. The composite layers of the ZEBRA detector consist of small heavy-oxide scintillators in the form of granules of crystalline BGO, GSO, ZWO, PWO and other materials. We have produced and tested the ZEBRA detector of sizes 100x100x41 mm and greater, and determined that they have very high efficiency of fast neutron detection (up to 49% or greater), comparable to that which can be achieved by large sized heavy-oxide single crystals of about Ø40x80 cm3 volume. We have also studied the sensitivity variation to fast neutron detection by using different types of multilayer ZEBRA detectors of 100 cm2 surface area and 41 mm thickness (with a detector weight of about 1 kg) and found it to be comparable to the sensitivity of a 3He-detector representing a total cross-section of about 2000 cm2 (with a weight of detector, including its plastic moderator, of about 120 kg). The measured count rate in response to a fast neutron source of 252Cf at 2 m for the ZEBRA-GSO detector of size 100x100x41 mm3 was 2.84 cps/ng, and this count rate can be doubled by increasing the detector height (and area) up to 200x100 mm2. In summary, the ZEBRA detectors represent a new type of high efficiency and low cost solid-state neutron detector that can be used for stationary neutron/gamma portals. They may represent an interesting alternative to expensive, bulky gas counters based on 3He or 10B neutron detection technologies.

APA, Harvard, Vancouver, ISO, and other styles

6

Jensen, Gary L., J. C. Wang, and J. Bart Czirr. "High-efficiency fast-neutron detectors." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 333, no. 2-3 (1993): 474–83. http://dx.doi.org/10.1016/0168-9002(93)91195-s.

Full text

APA, Harvard, Vancouver, ISO, and other styles

7

Sagatova, Andrea, Bohumir Zatko, Katarina Sedlackova, et al. "Semi-insulating GaAs detectors with HDPE layer for detection of fast neutrons from D–T nuclear reaction." International Journal of Modern Physics: Conference Series 44 (January 2016): 1660233. http://dx.doi.org/10.1142/s2010194516602337.

Full text

Abstract:

Bulk semi-insulating (SI) GaAs detectors optimized for fast-neutron detection were examined using mono-energetic neutrons. The detectors have an active area of 7.36 mm2 defined by a multi-pixel structure of a AuZn Schottky contact allowing a relatively high breakdown voltage (300 V) sufficient for full depletion of the detector structure. The Schottky contact is covered by a HDPE (high density polyethylene) conversion layer, where neutrons transfer their kinetic energy to hydrogen atoms through elastic nuclear collisions. The detectors were exposed to mono-energetic neutrons generated by a deuterium (D)–tritium (T) nuclear reaction at a Van de Graaff accelerator. Neutrons reached a kinetic energy of 16.8 MeV when deuterons were accelerated by 1 MV potential. The influence of the HDPE layer thickness on the detection efficiency of the fast neutrons was studied. The thickness of the conversion layer varied from 50 [Formula: see text]m to 1300 [Formula: see text]m. The increase of the HDPE layer thickness led to a higher detection efficiency due to higher conversion efficiency of the HDPE layer. The effect of the active detector thickness modified by the detector reverse bias voltage on the detection efficiency was also evaluated. By increasing the detector reverse voltage, the detector active volume expands to the depth and also to the sides, slightly increasing the neutron detection efficiency.

APA, Harvard, Vancouver, ISO, and other styles

8

Beyer, Roland, Axel Frotscher, Arnd R. Junghans, et al. "Fast neutron inelastic scattering from 7Li." EPJ Web of Conferences 239 (2020): 01029. http://dx.doi.org/10.1051/epjconf/202023901029.

Full text

Abstract:

The inelastic scattering of fast neutrons from 7Li nuclei was investigated at the nELBE neutron-time-of-flight facility. The photon production cross section of 478 keV γ-rays from the first excited state of 7Li was determined by irradiating a disc of LiF with neutrons of energies ranging from 100 keV to about 10 MeV. The target position was surounded by a setup of 7 LaBr3 scintillation detectors and 7 high-purity germanium detectors to detect the de-excitation γ-rays. A 235U fission chamber was used to determine the incoming neutron flux. The number of detected photons was corrected for the detection efficiency, multiple scattering and the time-of-flight dependent data acquisition dead time. The preliminary results show reasonable agreement with some previous measurments but are about 15 % below the recent data taken at the GELINA facility.

APA, Harvard, Vancouver, ISO, and other styles

9

Obraztsova, O., L. Ottaviani, A. Klix, T. Döring, O. Palais, and A. Lyoussi. "Comparison between Silicon-Carbide and diamond for fast neutron detection at room temperature." EPJ Web of Conferences 170 (2018): 08006. http://dx.doi.org/10.1051/epjconf/201817008006.

Full text

Abstract:

Neutron radiation detector for nuclear reactor applications plays an important role in getting information about the actual neutron yield and reactor environment. Such detector must be able to operate at high temperature (up to 600° C) and high neutron flux levels. It is worth nothing that a detector for industrial environment applications must have fast and stable response over considerable long period of use as well as high energy resolution. Silicon Carbide is one of the most attractive materials for neutron detection. Thanks to its outstanding properties, such as high displacement threshold energy (20-35 eV), wide band gap energy (3.27 eV) and high thermal conductivity (4.9 W/cm·K), SiC can operate in harsh environment (high temperature, high pressure and high radiation level) without additional cooling system. Our previous analyses reveal that SiC detectors, under irradiation and at elevated temperature, respond to neutrons showing consistent counting rates as function of external reverse bias voltages and radiation intensity. The counting-rate of the thermal neutron-induced peak increases with the area of the detector, and appears to be linear with respect to the reactor power. Diamond is another semi-conductor considered as one of most promising materials for radiation detection. Diamond possesses several advantages in comparison to other semiconductors such as a wider band gap (5.5 eV), higher threshold displacement energy (40-50 eV) and thermal conductivity (22 W/cm·K), which leads to low leakage current values and make it more radiation resistant that its competitors. A comparison is proposed between these two semiconductors for the ability and efficiency to detect fast neutrons. For this purpose the deuterium-tritium neutron generator of Technical University of Dresden with 14 MeV neutron output of 1010 n·s-1 is used. In the present work, we interpret the first measurements and results with both 4H-SiC and chemical vapor deposition (CVD) diamond detectors irradiated with 14 MeV neutrons at room temperature.

APA, Harvard, Vancouver, ISO, and other styles

10

Kraner, H. W., Z. Li, and K. U. Posnecker. "Fast neutron damage in silicon detectors." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 279, no. 1-2 (1989): 266–71. http://dx.doi.org/10.1016/0168-9002(89)91091-7.

Full text

APA, Harvard, Vancouver, ISO, and other styles

11

Chatzakis, John, Iraklis Rigakis, Syed Hassan, Eugene Laurence Clark, Paul Lee, and Michael Tatarakis. "Design of a Pixelated Imaging System for Fast Neutron Sources." Designs 3, no. 2 (2019): 25. http://dx.doi.org/10.3390/designs3020025.

Full text

Abstract:

Imaging detectors that use X-ray radiation and pulsed neutron sources have increased in sophistication in recent years due to the use of solid-state detectors. A key method for neutron detection is the nuclear activation of materials by neutrons. Neutron activation can generate radionuclides whose decay produces secondary particle emission that can be detected without interference from the X-rays and other prompt radiation sources and offers advantages over neutrons detection using scintillators. In this paper, we present the design of an imaging system for fast neutron sources. The imaging system utilizes a microcontroller network that communicates using a modified SPI protocol. This network communicates with an interface unit and passes an image to a personal computer. A computer program has been developed to reconstruct the image.

APA, Harvard, Vancouver, ISO, and other styles

12

NAKAE, L. F., G. F. CHAPLINE, A. M. GLENN, et al. "THE USE OF FAST NEUTRON DETECTION FOR MATERIALS ACCOUNTABILITY." International Journal of Modern Physics: Conference Series 27 (January 2014): 1460140. http://dx.doi.org/10.1142/s2010194514601409.

Full text

Abstract:

For many years at LLNL, we have been developing time-correlated neutron detection techniques and algorithms for applications such as Arms Control, Threat Detection and Nuclear Material Assay. Many of our techniques have been developed specifically for the relatively low efficiency (a few percent) inherent in man-portable systems. Historically, thermal neutron detectors (mainly 3 He ) were used, taking advantage of the high thermal neutron interaction cross-sections, but more recently we have been investigating the use of fast neutron detection with liquid scintillators, inorganic crystals, and in the near future, pulse-shape discriminating plastics that respond over 1000 times faster (nanoseconds versus tens of microseconds) than thermal neutron detectors. Fast neutron detection offers considerable advantages, since the inherent nanosecond production timescales of fission and neutron-induced fission are preserved and measured instead of being lost in the thermalization of thermal neutron detectors. We are now applying fast neutron technology to the safeguards regime in the form of high efficiency counters. Faster detector response times and sensitivity to neutron momentum show promise in measuring, differentiating, and assaying samples that have modest to very high count rates, as well as mixed neutron sources (e.g., Pu oxide or Mixed Cm and Pu ). Here we report on measured results with our existing liquid scintillator array and promote the design of a nuclear material assay system that incorporates fast neutron detection, including the surprising result that fast liquid scintillator becomes competitive and even surpasses the precision of 3 He counters measuring correlated pairs in modest (kg) samples of plutonium.

APA, Harvard, Vancouver, ISO, and other styles

13

Biondo, Stephane, Wilfried Vervisch, Laurent Ottaviani, Vanessa Vervisch, Raffaello Ferrone, and Abdallah Lioussy. "Simulations of Interactions between Fast Neutrons and 4H-SiC Detectors." Materials Science Forum 821-823 (June 2015): 863–66. http://dx.doi.org/10.4028/www.scientific.net/msf.821-823.863.

Full text

Abstract:

Among particle detectors, particle detectors based on the wide gap semiconductor materials are many used in the nuclear area. For the reliable uses in hard and severe environment, the 4H-SiC is mainly used to the realization of nuclear detector components. This is a part of the topic of the I_SMART European project which proposes to study the nuclear detection of the thermal and fast neutron and gamma rays. In this paper, we deal with the Monte Carlo simulation results of interactions between particles and 4H-SiC detector. In particular, simulation works present the results between fast neutron and 4H-SiC sensor with a comparison between the simulation and experimental results. This article tries to point out the effect of the space charge region depletion, in particular the electric field on the signal response strength.

APA, Harvard, Vancouver, ISO, and other styles

14

Dangendorf, V., G. Laczko, M. Reginatto, et al. "Detectors for time-of-flight fast-neutron radiography 1. Neutron-counting gas detector." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 542, no. 1-3 (2005): 197–205. http://dx.doi.org/10.1016/j.nima.2005.01.100.

Full text

APA, Harvard, Vancouver, ISO, and other styles

15

DANGENDORF, V., C. KERSTEN, G. LACZKO, et al. "Detectors for energy-resolved fast-neutron imaging." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 535, no. 1-2 (2004): 93–97. http://dx.doi.org/10.1016/s0168-9002(04)01580-3.

Full text

APA, Harvard, Vancouver, ISO, and other styles

16

Akbarov, R. A., G. S. Ahmadov, F. I. Ahmadov, et al. "Fast neutron detectors with silicon photomultiplier readouts." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 936 (August 2019): 549–51. http://dx.doi.org/10.1016/j.nima.2018.11.089.

Full text

APA, Harvard, Vancouver, ISO, and other styles

17

Croci, G., G. Claps, M. Cavenago, et al. "nGEM fast neutron detectors for beam diagnostics." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 720 (August 2013): 144–48. http://dx.doi.org/10.1016/j.nima.2012.12.014.

Full text

APA, Harvard, Vancouver, ISO, and other styles

18

Giacomelli, L., C. Andreani, A. Fazzi, et al. "Diamond detectors for fast neutron irradiation experiments." Nuclear Physics B - Proceedings Supplements 215, no. 1 (2011): 242–46. http://dx.doi.org/10.1016/j.nuclphysbps.2011.04.020.

Full text

APA, Harvard, Vancouver, ISO, and other styles

19

Chandra, R., G. Davatz, H. Friederich, U. Gendotti, and D. Murer. "Fast neutron detection with pressurized4He scintillation detectors." Journal of Instrumentation 7, no. 03 (2012): C03035. http://dx.doi.org/10.1088/1748-0221/7/03/c03035.

Full text

APA, Harvard, Vancouver, ISO, and other styles

20

Haight, R. C. "Fast-neutron detectors for nuclear physics experiments." Journal of Instrumentation 7, no. 05 (2012): C05002. http://dx.doi.org/10.1088/1748-0221/7/05/c05002.

Full text

APA, Harvard, Vancouver, ISO, and other styles

21

Vartsky, D., I. Mor, M. B. Goldberg, et al. "Novel detectors for fast-neutron resonance radiography." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 623, no. 1 (2010): 603–5. http://dx.doi.org/10.1016/j.nima.2010.03.084.

Full text

APA, Harvard, Vancouver, ISO, and other styles

22

Medkour Ishak-Boushaki, G., K. Boukeffoussa, Z. Idiri, and M. Allab. "Fast neutron spectrometry using thick threshold detectors." EPJ Web of Conferences 24 (2012): 07009. http://dx.doi.org/10.1051/epjconf/20122407009.

Full text

APA, Harvard, Vancouver, ISO, and other styles

23

Cazzaniga, C., M. Rebai, R. García Alía, et al. "Fast neutron measurements with solid state detectors at pulsed spallation sources." Journal of Neutron Research 22, no. 2-3 (2020): 345–52. http://dx.doi.org/10.3233/jnr-190141.

Full text

Abstract:

Fast neutron measurements have been performed with silicon and diamond detectors at nTOF, ChipIr, and CHARM facilities. The detectors have been used in pulse mode; the deposited energy and time stamp is measured event by event for each signal above threshold. The pulsed nature of the spallation sources gives high instantaneous counting rates that dictate the use of a fast electronic chain including a current preamplifier and digital acquisition. The energy-dependent response functions of these detectors to fast neutrons can be extracted from nTOF data using time-of-flight to provide energy tagging. These measured response functions can then be used both to benchmark Monte Carlo simulations of the response functions and to interpret the measurements at ChipIR and CHARM, facilities used for the irradiation of microelectronics, where time-of-flight energy measurement at these neutron energies is not possible.

APA, Harvard, Vancouver, ISO, and other styles

24

Mor, I., D. Vartsky, D. Bar, et al. "High spatial resolution fast-neutron imaging detectors for Pulsed Fast-Neutron Transmission Spectroscopy." Journal of Instrumentation 4, no. 05 (2009): P05016. http://dx.doi.org/10.1088/1748-0221/4/05/p05016.

Full text

APA, Harvard, Vancouver, ISO, and other styles

25

Liu, Yang, Zhen Ni Xing, and Guo Zheng Zhu. "Low-Flux Neutron Radiation Detection Technology with High Sensitivity." Applied Mechanics and Materials 668-669 (October 2014): 924–27. http://dx.doi.org/10.4028/www.scientific.net/amm.668-669.924.

Full text

Abstract:

Boron-containing plastic scintillator detectors have a high detection efficiency for low-intensity thermal neutrons and fast neutrons which is currently the preferred types of neutron detector. This article is based on Monte Carlo method, studied boron-containing plastic scintillator for neutron detection performance, and analysis the energy deposition flux characteristics and detection efficiency when low intensity fission neutron incident to the boron plastic scintillator. We obtain the low-flux neutron detector performance in a variety of neutron source energy, boron-containing plastic scintillator diameter and length. Results showed that, when the boron-containing plastic scintillator lengths increase, the energy deposition flux will increase. When the length and diameter is constant, increasing source strength can increase the energy deposition flux brought by the recoil proton to a certain extent. When the source intensity over after thermal neutrons, due to the decrease of the cross section, the energy deposition fluxes brought by the react of neutrons and will decrease. The results provide help for low intensity fission neutron radiation detection technology with high sensitivity.

APA, Harvard, Vancouver, ISO, and other styles

26

Devlin, Matthew, Jaime A. Gomez, Keegan J. Kelly, et al. "Prompt Fission Neutron Spectra for Neutron-Induced Fission of 239Pu and 235U." EPJ Web of Conferences 239 (2020): 01003. http://dx.doi.org/10.1051/epjconf/202023901003.

Full text

Abstract:

We report the current results of a large effort to accurately measure the Prompt Fission Neutron Spectra (PFNS) for neutron-induced fission of 235U and 239Pu for incident neutrons with energies from 1 to 20 MeV. The Chi-Nu experiment at the Los Alamos Neutron Science Center used an unmoderated, white spectrum of neutrons to induce fission in actinide samples that were placed inside a parallel plate avalanche counter to provide a fast fission signal. A double time-of-flight technique was used to determine the incoming and outgoing neutron energies. Two neutron detector arrays, one with 54 liquid scintillators and another with 22 lithium glass detectors, were used to detect the outgoing neutrons and measure the PFNS distributions over a wide range in outgoing neutron energy, from below 100 keV to 10 MeV. Extensive Monte Carlo modeling was used to understand the experiment response and extract the PFNS. Systematic errors and uncertainties in the method have been examined and quantified. A summary of these results for incoming energies from 1 to 5 MeV is presented here.

APA, Harvard, Vancouver, ISO, and other styles

27

Fourmentel, D., J.-F. Villard, C. Destouches, B. Geslot, L. Vermeeren, and M. Schyns. "In-Pile Qualification of the Fast-Neutron-Detection-System." EPJ Web of Conferences 170 (2018): 04025. http://dx.doi.org/10.1051/epjconf/201817004025.

Full text

Abstract:

In order to improve measurement techniques for neutron flux assessment, a unique system for online measurement of fast neutron flux has been developed and recently qualified in-pile by the French Alternative Energies and Atomic Energy Commission (CEA) in cooperation with the Belgian Nuclear Research Centre (SCK•ECEN). The Fast-Neutron-Detection-System (FNDS) has been designed to monitor accurately high-energy neutrons flux (E > 1 MeV) in typical Material Testing Reactor conditions, where overall neutron flux level can be as high as 1015 n.cm-2.s-1 and is generally dominated by thermal neutrons. Moreover, the neutron flux is coupled with a high gamma flux of typically a few 1015 γ.cm-2.s-1, which can be highly disturbing for the online measurement of neutron fluxes. The patented FNDS system is based on two detectors, including a miniature fission chamber with a special fissile material presenting an energy threshold near 1 MeV, which can be 242Pu for MTR conditions. Fission chambers are operated in Campbelling mode for an efficient gamma rejection. FNDS also includes a specific software that processes measurements to compensate online the fissile material depletion and to adjust the sensitivity of the detectors, in order to produce a precise evaluation of both thermal and fast neutron flux even after long term irradiation. FNDS has been validated through a two-step experimental program. A first set of tests was performed at BR2 reactor operated by SCK•CEN in Belgium. Then a second test was recently completed at ISIS reactor operated by CEA in France. FNDS proved its ability to measure online the fast neutron flux with an overall accuracy better than 5%.

APA, Harvard, Vancouver, ISO, and other styles

28

Diakaki, M., V. Michalopoulou, A. Tsinganis, et al. "Measurement of the 236U(n,f) cross section at fast neutron energies with Micromegas Detectors." EPJ Web of Conferences 239 (2020): 05001. http://dx.doi.org/10.1051/epjconf/202023905001.

Full text

Abstract:

In the present work, the measurement of the 236U(n,f) cross section was performed, with reference to the 238U(n,f) reaction. The measurements took place at the neutron beam facility of the National Centre for Scientific Research "Demokritos" (Greece) and the quasi-monoenergetic neutron beams were produced via the 2H(d,n)3He reaction in the energy range 4–10 MeV. Five actinide targets (two 236U, two 238U and one 235U) and the corresponding Micromegas detectors for the detection of the fission fragments were used. Detailed Monte Carlo simulations were performed, on one hand for the study of the neutron flux and energy distribution at the position of each target, and on the other hand for the study of the energy deposition of the fission fragments in the active volume of the detector. The mass and homogeneity of the actinide targets were experimentally determined via alpha spectroscopy and the Rutherford Backscattering Spectrometry, respectively. The experimental procedure, the analysis, the methodology implemented to correct for the presence of parasitic neutrons and the cross section results will be presented and discussed.

APA, Harvard, Vancouver, ISO, and other styles

29

El-Sersy, A. R., S. A. Eman, and N. E. Khaled. "Fast neutron spectroscopy using CR-39 track detectors." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 226, no. 3 (2004): 345–50. http://dx.doi.org/10.1016/j.nimb.2004.06.023.

Full text

APA, Harvard, Vancouver, ISO, and other styles

30

Mikerov, V. I., I. A. Zhitnik, Ju N. Barmakov, et al. "Prospects for efficient detectors for fast neutron imaging." Applied Radiation and Isotopes 61, no. 4 (2004): 529–35. http://dx.doi.org/10.1016/j.apradiso.2004.03.078.

Full text

APA, Harvard, Vancouver, ISO, and other styles

31

ELSERSY, A., S. EMAN, and N. KHALED. "Fast neutron spectroscopy using CR-39 track detectors." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 226, no. 3 (2004): 345–50. http://dx.doi.org/10.1016/s0168-583x(04)00826-2.

Full text

APA, Harvard, Vancouver, ISO, and other styles

32

Kiener, J., V. Tatischeff, I. Deloncle, et al. "Fast-neutron induced background in LaBr3:Ce detectors." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 798 (October 2015): 152–61. http://dx.doi.org/10.1016/j.nima.2015.07.022.

Full text

APA, Harvard, Vancouver, ISO, and other styles

33

Grimes, T. F., and R. P. Taleyarkhan. "Fast neutron spectroscopy with tensioned metastable fluid detectors." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 830 (September 2016): 355–65. http://dx.doi.org/10.1016/j.nima.2016.05.118.

Full text

APA, Harvard, Vancouver, ISO, and other styles

34

Dajkó, G. "Fast Neutron Spectrometry Using CR-39 Track Detectors." Radiation Protection Dosimetry 34, no. 1-4 (1990): 9–12. http://dx.doi.org/10.1093/rpd/34.1-4.9.

Full text

APA, Harvard, Vancouver, ISO, and other styles

35

Pietropaolo, A., C. Andreani, M. Rebai, et al. "Fission diamond detectors for fast-neutron ToF spectroscopy." EPL (Europhysics Letters) 94, no. 6 (2011): 62001. http://dx.doi.org/10.1209/0295-5075/94/62001.

Full text

APA, Harvard, Vancouver, ISO, and other styles

36

Dajkó, G. "Fast Neutron Spectrometry Using CR-39 Track Detectors." Radiation Protection Dosimetry 34, no. 1-4 (1990): 9–12. http://dx.doi.org/10.1093/oxfordjournals.rpd.a080833.

Full text

APA, Harvard, Vancouver, ISO, and other styles

37

Cui, Bo, Zhiheng Fang, Zenghai Dai, et al. "Nuclear diagnosis of the fuel areal density for direct-drive deuterium fuel implosion at the Shenguang-II Upgrade laser facility." Laser and Particle Beams 36, no. 4 (2018): 494–501. http://dx.doi.org/10.1017/s026303461800054x.

Full text

Abstract:

AbstractIn inertial confinement fusion experiments that involve short-laser pulses such as fast ignition (FI), diagnosis of neutrons is usually very challenging because high-intensity γ rays generated by short-laser pulses would mask the much weaker neutron signal. In this paper, fast-response scintillators with low afterglow and gated microchannel plate photomultiplier tubes are combined to build neutron time-of-flight (nTOF) spectrometers for such experiments. Direct-drive implosion experiments of deuterium-gas-filled capsules were performed at the Shenguang-II Upgrade (SG-II-UP) laser facility to study the compressed fuel areal density (〈ρR〉) and evaluate the performance of such nTOF diagnostics. Two newly developed quenched liquid scintillator detectors and a gated ultrafast plastic scintillator detector were used to measure the secondary DT neutrons and primary DD neutrons, respectively. The secondary neutron signals were clearly discriminated from the γ rays from (n, γ) reactions, and the compressed fuel areal density obtained with the yield-ratio method agrees well with the simulations. Additionally, a small scintillator decay tail and a clear DD neutron signal were observed in an integrated FI experiment as a result of the low afterglow of the oxygen-quenched liquid scintillator.

APA, Harvard, Vancouver, ISO, and other styles

38

Szuta, M., S. Kilim, E. Strugalska-Gola, et al. "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." EPJ Web of Conferences 204 (2019): 04002. http://dx.doi.org/10.1051/epjconf/201920404002.

Full text

Abstract:

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.

APA, Harvard, Vancouver, ISO, and other styles

39

Qi, L., J. N. Wilson, M. Lebois, et al. "Prompt fission gamma-ray emission spectral data for 239Pu(n,f) using fast directional neutrons from the LICORNE neutron source." EPJ Web of Conferences 169 (2018): 00018. http://dx.doi.org/10.1051/epjconf/201816900018.

Full text

Abstract:

Prompt fission gamma-ray spectra (PFGS) have been measured for the 239Pu(n,f) reaction using fast neutrons at Ēn=1.81 MeV produced by the LICORNE directional neutron source. The setup makes use of LaBr3 scintillation detectors and PARIS phoswich detectors to measure the emitted prompt fission gamma rays (PFG). The mean multiplicity, average total energy release per fission and average energy of photons are extracted from the unfolded PFGS. These new measurements provide complementary information to other recent work on thermal neutron induced fission of 239Pu and spontaneous fission of 252Cf.

APA, Harvard, Vancouver, ISO, and other styles

40

Mohammadi, Sara, Marziyeh Behmadi, Aghil Mohammadi, and Mohammad Taghi Bahreyni Toossi. "THERMAL AND FAST NEUTRON DOSE EQUIVALENT DISTRIBUTION MEASUREMENT OF 15-MV LINEAR ACCELERATOR USING A CR-39 NUCLEAR TRACK DETECTORS." Radiation Protection Dosimetry 188, no. 4 (2020): 503–7. http://dx.doi.org/10.1093/rpd/ncaa001.

Full text

Abstract:

Abstract The main purpose of this study is to measure the contribution of the thermal and fast neutron dose along the central axis of the 15 MV Elekta Precise linac in a tissue equivalent phantom. In order to achieve this purpose, different points were selected in three field sizes of 5 × 5 cm2, 10 × 10 cm2 and 15 × 15 cm2. Fast and thermal neutrons were measured using CR-39 nuclear track detectors with and without thermal neutron converter of 10B, respectively. According to the results, the fast neutron dose equivalent was decreased as the depth increased (field size 5 × 5, 10 × 10 and 15 × 15 cm2 fall from 0.35 to 0.15, 0.5 to 0.3 and 0.5 to 0.3, respectively). Thermal dose equivalent was increased as the depth increased in the tissue equivalent phantom (field size 5 × 5, 10 × 10 and 15 × 15 cm2 rise from 0.1 to 0.4, 0.4 to 0.8 and 0.4 to 0.9, respectively). In conclusion, at depth &lt;3 cm, most existing neutrons are fast and CR-39 films are sensitive to fast neutrons; therefore, they are more appropriate than thermoluminescent dosemeters in measuring neutron dose equivalent.

APA, Harvard, Vancouver, ISO, and other styles

41

Eleme, Z., M. Alexandropoulou, A. Georgiadou, et al. "Determination of the Neutron Beam Spatial Profile at n_TOF EAR-2 using the CR-39 Track Detectors." HNPS Proceedings 23 (March 8, 2019): 28. http://dx.doi.org/10.12681/hnps.1903.

Full text

Abstract:

Within the present work the neutron beam spatial profile was determined at the sample position in EAR-2 at the n_TOF facility at CERN. The CR-39 detectors were coupled with a 2mm PE foil serving as neutron-to-proton converter. Two irradiations were performed in the 10x5 cm surface of CR-39 detectors. Proton tracks were revealed in the CR-39 detectors resulting from the elastic scattering of fast neutrons on the hydrogen atoms in the PE converter. Afterwards, the CR-39 detectors were chemically etched in aqueous NaOH solution and latent tracks were considerably enlarged to become visible under an optical microscope. After the scanning of the detectors surface, the acquired images were analyzed using the ImageJ program. In the present work, the experimental setup and procedure will be presented along with the results concerning the characterization of the neutron beam spatial profile at the sample position in the n_TOF EAR-2.

APA, Harvard, Vancouver, ISO, and other styles

42

Hegazy, Aya Hamdy, V. R. Skoy, and K. Hossny. "Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5." EPJ Web of Conferences 177 (2018): 02003. http://dx.doi.org/10.1051/epjconf/201817702003.

Full text

Abstract:

Neutron generators are now used in various fields. They produce only fast neutrons; D-D neutron generator produces 2.45 MeV neutrons and D-T produces 14.1 MeV neutrons. In order to optimize shielding-collimator parameters to achieve higher neutron flux at the investigated sample (The signal) with lower neutron and gamma rays flux at the area of the detectors, design iterations are widely used. This work was applied to ROMASHA setup, TANGRA project, FLNP, Joint Institute for Nuclear Research. The studied parameters were; (1) shielding-collimator material, (2) Distance between the shielding-collimator assembly first plate and center of the neutron beam, and (3) thickness of collimator sheets. MCNP5 was used to simulate ROMASHA setup after it was validated on the experimental results of irradiation of Carbon-12 sample for one hour to detect its 4.44 MeV characteristic gamma line. The ratio between the signal and total neutron flux that enters each detector was calculated and plotted, concluding that the optimum shielding-collimator assembly is Tungsten of 5 cm thickness for each plate, and a distance of 2.3 cm. Also, the ratio between the signal and total gamma rays flux was calculated and plotted for each detector, leading to the previous conclusion but the distance was 1 cm.

APA, Harvard, Vancouver, ISO, and other styles

43

Jovanovic, I., A. Foster, V. Kukharev, et al. "Spectroscopic neutron detection using composite scintillators." International Journal of Modern Physics: Conference Series 44 (January 2016): 1660232. http://dx.doi.org/10.1142/s2010194516602325.

Full text

Abstract:

Shielded special nuclear material (SNM), especially highly enriched uranium, is exceptionally difficult to detect without the use of active interrogation (AI). We are investigating the potential use of low-dose active interrogation to realize simultaneous high-contrast imaging and photofission of SNM using energetic gamma-rays produced by low-energy nuclear reactions, such as [Formula: see text]B(d,n[Formula: see text]C and [Formula: see text]C(p,p[Formula: see text]C. Neutrons produced via fission are one reliable signature of the presence of SNM and are usually identified by their unique timing characteristics, such as the delayed neutron die-away. Fast neutron spectroscopy may provide additional useful discriminating characteristics for SNM detection. Spectroscopic measurements can be conducted by recoil-based or thermalization and capture-gated detectors; the latter may offer unique advantages since they facilitate low-statistics and event-by-event neutron energy measurements without spectrum unfolding. We describe the results of the development and characterization of a new type of capture-gated spectroscopic neutron detector based on a composite of scintillating polyvinyltoluene and lithium-doped scintillating glass in the form of millimeter-thick rods. The detector achieves >108 neutron–gamma discrimination resulting from its geometric properties and material selection. The design facilitates simultaneous pulse shape and pulse height discrimination, despite the fact that no materials intrinsically capable of pulse shape discrimination have been used to construct the detector. Accurate single-event measurements of neutron energy may be possible even when the energy is relatively low, such as with delayed fission neutrons. Simulation and preliminary measurements using the new composite detector are described, including those conducted using radioisotope sources and the low-dose active interrogation system based on low-energy nuclear reactions.

APA, Harvard, Vancouver, ISO, and other styles

44

Ivkovic, Ana, Dario Faj, Mladen Kasabasic, et al. "The influence of shielding reinforcement in a vault with limited dimensions on the neutron dose equivalent in vicinity of medical electron linear accelerator." Radiology and Oncology 54, no. 2 (2020): 247–52. http://dx.doi.org/10.2478/raon-2020-0024.

Full text

Abstract:

AbstractBackgroundHigh energy electron linear accelerators (LINACs) producing photon beams with energies higher than 10 MeV are widely used in radiation therapy. In these beams, fast neutrons are generated, which results in undesired contamination of the therapeutic beam. In this study, measurements and Monte Carlo (MC) simulations were used to obtain neutron spectra and dose equivalents in vicinity of linear accelerator.Materials and methodsLINAC Siemens Oncor Expression in Osijek University Hospital is placed in vault that was previously used for 60Co machine. Then, the shielding of the vault was enhanced using lead and steel plates. Measurements of neutron dose equivalent around LINAC and the vault were done using CR-39 solid state nuclear track detectors. To compensate energy dependence of detectors, neutron energy spectra was calculated in measuring positions using MC simulations.ResultsThe vault is a source of photoneutrons, but a vast majority of neutrons originates from accelerator head. Neutron spectra obtained from MC simulations show significant changes between the measuring positions. Annual neutron dose equivalent per year was estimated to be less than 324 μSv in the measuring points outside of the vault.ConclusionsSince detectors used in this paper are very dependent on neutron energy, it is extremely important to know the neutron spectra in measuring points. Though, patient dosimetry should include neutrons, estimated annual neutron doses outside the vault were far below exposure limit of ionizing radiation for workers.

APA, Harvard, Vancouver, ISO, and other styles

45

Mauri, G., F. Messi, K. Kanaki, et al. "Fast neutron sensitivity of neutron detectors based on Boron-10 converter layers." Journal of Instrumentation 13, no. 03 (2018): P03004. http://dx.doi.org/10.1088/1748-0221/13/03/p03004.

Full text

APA, Harvard, Vancouver, ISO, and other styles

46

KRASILNIKOV, Anatoli V., Vladimir N. AMOSOV, Nikolay N. GORELENKOV, et al. "Neutron and Fast Atom Spectrometry Using Natural Diamond Detectors." Journal of Plasma and Fusion Research 75, no. 8 (1999): 967–76. http://dx.doi.org/10.1585/jspf.75.967.

Full text

APA, Harvard, Vancouver, ISO, and other styles

47

IKEDA, Yasushi, Takayo MURAMATSU, and Gen-ichi MATSUMOTO. "Fast neutron radiography with CR39 solid state track detectors." RADIOISOTOPES 35, no. 7 (1986): 367–74. http://dx.doi.org/10.3769/radioisotopes.35.7_367.

Full text

APA, Harvard, Vancouver, ISO, and other styles

48

Kwiatkowski, R., A. Malinowska, A. Szydlowski, J. Dankowski, A. Kurowski, and K. Gatarczyk. "Dielectric track detectors in fast neutron measurements and dosimetry." Radiation Measurements 138 (November 2020): 106434. http://dx.doi.org/10.1016/j.radmeas.2020.106434.

Full text

APA, Harvard, Vancouver, ISO, and other styles

49

Mikerov, V., V. Samosyuk, and S. Verushkin. "Detectors based on imaging plates for fast neutron radiography." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 542, no. 1-3 (2005): 192–96. http://dx.doi.org/10.1016/j.nima.2005.01.099.

Full text

APA, Harvard, Vancouver, ISO, and other styles

50

Flammang, Robert W., John G. Seidel, and Frank H. Ruddy. "Fast neutron detection with silicon carbide semiconductor radiation detectors." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 579, no. 1 (2007): 177–79. http://dx.doi.org/10.1016/j.nima.2007.04.034.

Full text

APA, Harvard, Vancouver, ISO, and other styles

We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!