Relevant bibliographies by topics / Fast Neutron Detectors

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  2. Dissertations / Theses
  3. Books
  4. Book chapters
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Academic literature on the topic 'Fast Neutron Detectors'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "Fast Neutron Detectors"

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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.

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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.
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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.

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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.
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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.

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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.
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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.

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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.
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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.

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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.
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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.

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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.

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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.
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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.

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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.
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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.

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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.
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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.

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Dissertations / Theses on the topic "Fast Neutron Detectors"

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PADILHA, MEIRE de C. "Deteccao de neutrons utilizando CR-39." reponame:Repositório Institucional do IPEN, 1992. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10298.

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Chen, Gongyin 1968. "Study of high-energy gamma-ray imaging detectors for fast neutron analysis." Thesis, Massachusetts Institute of Technology, 1999. http://hdl.handle.net/1721.1/85318.

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Elbasher, Mohamed Elbasher Ahmed. "Test of fast neutron detectors for spectroscopy with (3He,n) two proton stripping reactions." Thesis, Stellenbosch : Stellenbosch University, 2012. http://hdl.handle.net/10019.1/20123.

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Thesis (MSc)--Stellenbosch University, 2012.<br>ENGLISH ABSTRACT: Nine 100x100x600 mm3 plastic scintillators, formerly built for the neutron time of ight measurements at iThemba LABS, were refurbished. The position resolution of these detectors was determined using muon cosmic rays and coincident measurement techniques. Average position resolution of 4.28 cm (FWHM) was found. In order to predict the time spectrum of the large-volume detector Monte Carlo simulations have been performed. These simulations aimed at anticipating the separation of statistical neutrons, prompt gamma rays and uncorrelated gamma rays from the fast neutrons emitted in the reaction of interest. One of the neutron detectors was tested using fast neutrons from the 232Th( ,xn) reaction at 42 MeV. Statistical neutrons from fusion evaporation reactions were produced in 152Sm(12C,xn) fusion evaporation reaction. Coincidences between neutrons and gamma rays were successfully identi ed. Prompt gamma rays and uncorrelated gamma rays were also identi ed.<br>AFRIKAANSE OPSOMMING: Nege 100x100x600 mm3 plastiese scintillators, wat aanvanklik gebou was vir neutron vlugtyds meetings by iThemba LABS, was hernu. Die posisie resolusie van die detektore was bepaal deurmiddel van muon kosmiese straling en koïnsidensie meet tegnieke. Posisie resolusie van 4.28 cm (FWHM) was verkry. Monte Carlo simulasies is gebruik om die posisie resolusie van'n groot volume detektor te voorspel. Hierdie simulasies is daarop gemik om onderskeid te maak tussen statistiese neutrone, gelyktydige gamma strale en ongekorreleerde gamma strale vanaf vinnige neutrone in die reaksie van belang uitgestraal word. Een neutron detektor was getoets deur gebruik te maak van vinnige neutrone wat uit die reaksie 232Th( ,xn) by 42 MeV ontstaan. Statistiese neutrone vanaf splitsings verdampingsreaksies, gelyktydige gamma strale en ongekorreleerde gamma strale was geidenti seer. Statistiese neutrone van samesmelting verdamping reaksies was geproduseer in die reaksie 152Sm(12C,xn). Toeval tussen neutrone en gamma strale was suksesvol geïdenti seer, gevra gamma strale en ongekorreleerd gamma strale was ook geïdenti seer.
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DIAS, MAURO da S. "Desenvolvimento e aplicacao de um detector para a medida absoluta da taxa de fluencia de neutrons na regiao de MeV." reponame:Repositório Institucional do IPEN, 1988. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9898.

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Miller, Zachariah W. "A MEASUREMENT OF THE PROMPT FISSION NEUTRON ENERGY SPECTRUM FOR 235U(n,f) AND THE NEUTRON-INDUCED FISSION CROSS SECTION FOR 238U(n,f)." UKnowledge, 2015. http://uknowledge.uky.edu/physastron_etds/29.

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Two measurements have been made, addressing gaps in knowledge for 235U(n,f) and 238U(n,f). The energy distribution for prompt fission neutrons is not well-understood below 1 MeV in 235U(n,f). To measure the 235U(n,f) prompt fission neutron distribution, a pulsed neutron beam at the WNR facility in Los Alamos National Laboratory was directed onto a 235U target with neutron detectors placed 1 m from the target. These neutron detectors were designed specifically for this experiment and employed a unique geometry of scintillating plastic material that was designed to reject backgrounds. Fission fragments were detected using an avalanche counter. Coincidences between fission fragment production and neutron detector events were analyzed, using a double time-of-flight technique to determine the energy of the prompt fission neutrons. A separate measurement was made, investigating the neutron-induced fission cross section for 238U(n,f). This measurement also used the pulsed neutron beam at the WNR facility. The neutron flux was normalized to the well-known hydrogen standard and the fission rate was observed for beam neutrons in the energy range of 130-300 MeV. Using an extrapolation technique, the energy dependence of the cross section was determined. These new data filled a sparsely populated energy region that was not well-studied and were measured relative to the hydrogen standard, unlike the majority of available data. These data can be used to constrain the fission cross section, which is considered a nuclear reaction standard.
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Traore, Issiaka. "Etude et caractérisation des fonctions de réponse des détecteurs solides de traces nucléaires : applications à la dosimétrie radon et neutron." Phd thesis, Université de Strasbourg, 2013. http://tel.archives-ouvertes.fr/tel-01067060.

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Cette thèse a été préparée en cotutelle entre l'Université de Strasbourg et l'Université des SciencesTechniques et Technologies de Bamako (Mali). Elle s'articule principalement autour de la caractérisation des Détecteurs Solides de Traces Nucléaires (DSTN) afin de les utiliser pour la métrologie du radon et des neutrons conformément aux nouvelles recommandations de la Commission Internationale de Protection Radiologique (CIPR-103). Les fonctions de réponse de PN3 et Neutrak, associés avec des convertisseurs adaptés, ont été étudiés en les irradiant par des neutrons du calibrateur Am-Be de l'IPHC (Institut Pluridisciplinaire Hubert Curien), aux protons de 1 à 3 MeV de l'accélérateur Van de Graaff de l'INESS (INstitut d'Electronique du Solide et des Systèmes) et par des neutrons de référence thermiques et rapides auprès des installations de l'IRSN (Institut de Radiologie et de Sûreté Nucléaire). En dosimétrie neutronique, nous avons pu reproduire les résultats d'un test d'intercomparaison pour des neutrons rapides organisé par l'IRSN qui a validé nos mesures expérimentales, ce qui a permis de les appliquer aux neutrons thermiques. Un prototype de dosimètre neutrons basé sur la détection des thermiques a été testé avec succès au calibrateur de l'IPHC. Nous avons ainsi pu démontrer la faisabilité d'un dosimètre pouvant discriminer la contribution des neutrons thermiques des neutrons rapides par des convertisseurs chargés en bore BE10 et BN1. Les étalonnages de PN3 par des protons et des particules alpha permettraient de reconstituer le spectre en énergie des neutrons et de déterminer la dose associée.En métrologie radon, l'étalonnage de CR-39 dans une chambre à 222Rn a fourni une valeur de 0,12±0,02tr.cm-2.j-1.Bq-1.m3. Elle a été comparée à la valeur 0,13 tr.cm-2.j-1.Bq-1.m3 obtenue par simulation Monte Carlo à l'aide du code MCNPX. Comme application, la concentration et la dose effective annuelle du radon ont été déterminées pour la première fois dans des habitats de Bamako. Toutes les valeurs obtenues se trouvent dans les limites de sécurité recommandées par la CIPR. Également pour la première fois, des mesures par spectrométrie gamma et par contact radiographie ont été réalisées sur des échantillons de sol malien. Les activités massiques mesurées pour les régions de Ségou, Sikasso, Bamako et Kayes se trouvent dans la gamme de 19,9 à 132 Bq.kg-1.
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Mickum, George Spencer. "Development and testing of an organic scintillator detector for fast neutron spectrometry." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/47653.

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The use of organic scintillators is an established method for the measurement of neutron spectra above several hundred keV. Fast neutrons are detected largely by proton recoils in the scintillator resulting from neutron elastic scattering with hydrogen. This leads to a smeared rectangular pulse-height distribution for monoenergetic neutrons. The recoil proton distribution ranges in energy from zero to the incident neutron energy. In addition, the pulse-height distribution is further complicated by structure due to energy deposition from alpha particle recoils from interactions with carbon as well as carbon recoils themselves. In order to reconstruct the incident neutron spectrum, the pulse-height spectrum has to be deconvoluted (unfolded) using the computed or measured response of the scintillator to monoenergetic neutrons. In addition gamma rays, which are always present when neutrons are present, lead to Compton electron recoils in the scintillator. Fortunately, for certain organic scintillators, the electron recoil events can be separated from the heavier particle recoil events in turn to distinguish gamma-ray induced events from neutron-induced events. This is accomplished by using the risetime of the pulse from the organic scintillator seen in the photomultiplier tube as a decay of light. In this work, an organic scintillator detection system was assembled which includes neutron-gamma separation capabilities to store the neutron-induced and gamma-induced recoil spectra separately. An unfolding code was implemented to deconvolute the spectra into neutron and gamma energy spectra. In order to verify the performance of the system, a measurement of two reference neutron fields will be performed with the system, unmoderated Cf-252 and heavy-water moderated Cf-252. After the detection system has been verified, measurements will be made with an AmBe neutron source.
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VILELA, EUDICE C. "Deteccao de neutrons rapidos utilizando detectores solidos de tracos nucleares." reponame:Repositório Institucional do IPEN, 1990. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10247.

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Bjelkenstedt, Tom. "Optimization and design of a detection system based on transmission tomography with fast neutrons." Thesis, Uppsala universitet, Institutionen för fysik och astronomi, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-226394.

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This thesis is part of a project focusedon investigating the possibility ofmeasuring void distributions usingtransmission tomography with fastneutrons. The measurements are plannedto be conducted at thermal hydraulictest loops. The project, called STUNT,is carried out at Uppsala University atthe division for applied nuclearphysics.The purpose of this work was to designand optimize a detection system for thedetection of fast neutrons in the abovementioned environment. For this purpose,detector elements consisting of theplastic scintillator material EJ208 wasmodeled using the particle transportcode MCNPX.Both plate shaped elements and fibers ofdifferent dimensions where tested forperformance.Through a comparison utilizing severalfigures of merit and MATLAB, the plateshape was selected with an element widthof 2.6 mm. During the optimizationprocess a possible detector design with73 detector plates was chosen. At anenergy threshold of 11 MeV the followingdesign parameters were found; adetection efficiency of 3.0 %, a signalto background ratio of 15, a totalmeasurement time of 3600 s and a pixelresolution of 1.4 mm.A point spread function was produced andtwo projection tests where conductedusing a water filled steel cylinder asobject.<br>STUNT
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Verma, Vasudha. "Development of a Neutron Flux Monitoring System for Sodium-cooled Fast Reactors." Doctoral thesis, Uppsala universitet, Tillämpad kärnfysik, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-319945.

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Safety and reliability are one of the key objectives for future Generation IV nuclear energy systems. The neutron flux monitoring system forms an integral part of the safety design of a nuclear reactor and must be able to detect any irregularities during all states of reactor operation. The work in this thesis mainly concerns the detection of in-core perturbations arising from unwanted movements of control rods with in-vessel neutron detectors in a sodium-cooled fast reactor. Feasibility study of self-powered neutron detectors (SPNDs) with platinum emitters as in-core power profile monitors for SFRs at full power is performed. The study shows that an SPND with a platinum emitter generates a prompt current signal induced by neutrons and gammas of the order of 600 nA/m, which is large enough to be measurable. Therefore, it is possible for the SPND to follow local power fluctuations at full power operation. Ex-core and in-core detector locations are investigated with two types of detectors, fission chambers and self-powered neutron detectors (SPNDs) respectively, to study the possibility of detection of the spatial changes in the power profile during two different transient conditions, i.e. inadvertent withdrawal of control rods (IRW) and one stuck rod during reactor shutdown (OSR). It is shown that it is possible to detect the two simulated transients with this set of ex-core and in-core detectors before any melting of the fuel takes place. The detector signal can tolerate a noise level up to 5% during an IRW and up to 1% during an OSR.
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Books on the topic "Fast Neutron Detectors"

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Aslam, Akhlaq Ahmed. The development of a passive fast-neutron spectrometer based on CR-39 polymeric nuclear track detectors. University of Birmingham, 1988.

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Matiullah. Development of an energy and direction independent fast-neutron dosimeter using CR-39 polymeric (nuclear track) detector with front radiators. University of Birmingham, 1987.

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Present status of fast neutron personnel dosimetry system based on CR-39 solid state nuclear track detectors. Bhabha Atomic Research Centre, 2011.

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Book chapters on the topic "Fast Neutron Detectors"

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Kaplan, Greg I., Anatoly B. Rosenfeld, Barry J. Allen, et al. "Semiconductor Detectors for In-Phantom Thermal Neutron Flux and Boron Dose Measurements in BNCT and Fast Neutron Therapy." In Frontiers in Neutron Capture Therapy. Springer US, 2001. http://dx.doi.org/10.1007/978-1-4615-1285-1_179.

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Azechi, H., N. Miyanaga, R. O. Stapf, M. Yamanaka, C. Yamanaka, and T. Iguchi. "Fast Neutron Detectors for Thermonuclear Burn Time and Duration Measurements in Inertial Confinement Fusion Targets." In Springer Proceedings in Physics. Springer Berlin Heidelberg, 1988. http://dx.doi.org/10.1007/978-3-642-74088-6_40.

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Pyeon, Cheol Ho. "Reactor Kinetics." In Accelerator-Driven System at Kyoto University Critical Assembly. Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_3.

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AbstractIn static and kinetic experimental analyses, the reactivity effect of introducing a neutron guide has been examined with various materials and adjustments of the beam window. With the objective of improving the KUCA core characteristics, the implementation of the neutron guide is predicted to increase the fast neutrons in directing the fuel region. With regard to the kinetic characteristics, the subcriticality and the prompt neutron decay constant are monitored for several core configurations and detector positions. The KUCA core is equipped to make locally a hard spectrum core region with the combined use of 235U fuel, a polyethylene moderator, and a Pb–Bi reflector for criticality. In this study, the first attempt is made to examine experimentally the characteristics of kinetics parameters in ADS comprised of 235U-fueled and Pb–Bi-zoned core, and spallation neutrons generated by an injection of 100 MeV protons onto the solid Pb–Bi target. Online monitoring of reactivity has been deduced in real time by the inverse kinetic method on the basis of the one-point kinetic equation with measured neutron signals in the core. Here, measurements by the one-point kinetic equation are validated through the subcriticality evaluation with the PNS histogram and the methodology by the inhour equation.
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Perlini, G., H. Rief, M. D. Carter, and M. F. Murphy. "The S32 (n,p)P32 Threshold Detector and its Application for Fast Neutron Dosimetry (Fast Reactors and Fusion Reactors)." In Reactor Dosimetry. Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_46.

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Hep, J., A. Konečná, V. Krýsl, and V. Smutný. "The Fast Neutron Fluence and the Activation Detector Activity Calculations Using the Effective Source Method and the Adjoint Function." In Reactor Dosimetry: 14th International Symposium. ASTM International, 2012. http://dx.doi.org/10.1520/stp155020120047.

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Hep, J., A. Konečná, V. Krýsl, and V. Smutný. "The Fast Neutron Fluence and the Activation Detector Activity Calculations Using the Effective Source Method and the Adjoint Function." In Reactor Dosimetry: 14th International Symposium. ASTM International, 2012. http://dx.doi.org/10.1520/stp49644t.

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McGregor, Douglas S., and J. Kenneth Shultis. "Fast Neutron Detectors." In Radiation Detection. CRC Press, 2020. http://dx.doi.org/10.1201/9781439819401-18.

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Kasani, Hadi, Mohammad Taghi Ahmadi, Rasoul Khoda-Bakhsh, and Dariush Rezaei Ochbelagh. "Fast Neuron Detection." In Handbook of Research on Nanoelectronic Sensor Modeling and Applications. IGI Global, 2017. http://dx.doi.org/10.4018/978-1-5225-0736-9.ch015.

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In many research fields and industry such as nuclear physics, notably nuclear technology, fusion plasma diagnostics, radiotherapy and radiation protection, it is very substantial that measure fast neutron spectra. For example in nuclear reactor primary generated neutrons have energies around 2 MeV that lie fast neutron category. Also particle accelerators and Am-Be neutron source raise fast neutrons. Therefore a review of silicon based fast neutron detection with proton recoil methods is surveyed. Furthermore Carbon nanoparticles (CNPs) with simple and low cost preparation methods with exceptional electrical properties have been used widely in nanoelectronic applications such as radiation sensors. In this chapter, fast neutron detectors using Carbon based semiconductor, back-to-back Schottky diode type, and polyethylene as convertor are developed and the Am-Be fast neutron source is used in experimental measurements.
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Conference papers on the topic "Fast Neutron Detectors"

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Oxandale, Samuel W., Luke A. Stegeman, Tyler J. Hieber, et al. "Fabrication, Modeling, and Testing of a Miniaturized Fast Neutron Detector." In ASME 2019 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/imece2019-11534.

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Abstract This work outlines the positive-intrinsic-negative diode fabrication process for a Miniaturized Fast Neutron Detector and documents alpha source testing of a single positive-intrinsic-negative diode. The Miniaturized Fast Neutron Detector provides information about the kinetic energy distribution of neutrons with resolution up to 20 MeV and has 1–2% of the volume of comparable current state-of-the-art neutron spectrometers, namely Bonner Ball Neutron Detector sets and Capture-Gated Neutron Scintillator Detectors. The Miniaturized Fast Neutron Detector can be used to estimate neutron doses for heavy charged particle therapy patients improving the understanding of secondary cancer risks, monitor secondary neutron radiation more efficiently in therapy treatment facilities, and perform an important role in protecting astronauts from radiation.
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Haight, Robert C. "NEUTRON DETECTOR SYSTEMS FOR NEUTRON NUCLEAR DATA MEASUREMENTS." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0085.

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Hertel, Nolan E., Zhonglu Wang, Eric Burgett, and Arlene Lennox. "FERMILAB NEUTRON THERAPY FACILITY / NEUTRON SPECTRUM DETERMINATION BY THRESHOLD FOILS." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0041.

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Klein, Horst, and Frank D. Brooks. "SCINTILLATION DETECTORS FOR FAST NEUTRONS." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0097.

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BABA, Mamoru. "QUASI-MONOEBREGETIC NEUTRON SOURCE." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0086.

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Andriamonje, S., I. Giomataris, and J. Pancin. "FAST NEUTRON DETECTORS BASED ON MICROMEGAS TECHNOLOGY." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0010.

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Niedermayr, Thomas, Ionel Dragos Hau, Stephan Friedrich, Arnold Burger, Uptal Roy, and Zane W. Bell. "HIGH ENERGY RESOLUTION FAST NEUTRON SPECTROMTER." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0013.

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Viesti, Giuseppe, S. Pesente, G. Nebbia, D. Fabris, M. Lunardon, and S. Moretto. "THE NEUTRONIC CHECK POINT: FAST NEUTRON TRANSMISSION MEASUREMENTS TO DETECT EXPLOSIVE IN VEHICLES." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0032.

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Blomgren, Jan. "REFERENCE CROSS SECTIONS RELEVANT FOR NEUTRON DETECTORS." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0089.

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Blomgren, Jan, P. Mermod, M. Hayashi, et al. "FAST NEUTRON SCATTERING ON CARBON AND OXYGEN." In International Workshop on Fast Neutron Detectors and Applications. Sissa Medialab, 2007. http://dx.doi.org/10.22323/1.025.0071.

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Reports on the topic "Fast Neutron Detectors"

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Enqvist, Andreas. Used Fuel Storage Monitoring Using Helium-4 Scintillation Fast Neutron Detectors and Neutron Spectral Analysis. Office of Scientific and Technical Information (OSTI), 2019. http://dx.doi.org/10.2172/1493584.

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Blackston, Matthew A., Paul Hausladen, J. Felix Liang, and Jason Newby. Performance Of Fast-Neutron Imaging Detectors Based On Plastic Scintillator EJ-299-34. Office of Scientific and Technical Information (OSTI), 2013. http://dx.doi.org/10.2172/1128961.

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Li, Z., and H. W. Kraner. Measurements of possible type inversion in silicon junction detectors by fast neutron irradiation. Office of Scientific and Technical Information (OSTI), 1991. http://dx.doi.org/10.2172/5528749.

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Walker, Preston James. Assembly and characterization of fast neutron detectors for TREAT fuel motion monitoring system. Office of Scientific and Technical Information (OSTI), 2019. http://dx.doi.org/10.2172/1546702.

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Stange, Sy, and Edward Allen Mckigney. Comparison of Fast Neutron Detector Technologies. Office of Scientific and Technical Information (OSTI), 2015. http://dx.doi.org/10.2172/1169676.

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August, R. A., G. W. Phillips, and J. H. Cutchin. A High Efficiency Fast Neutron Detector. Defense Technical Information Center, 1989. http://dx.doi.org/10.21236/ada211248.

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Iverson, Erik B. Order-of-Magnitude Estimate of Fast Neutron Recoil Rates in Proposed Neutrino Detector at SNS. Office of Scientific and Technical Information (OSTI), 2006. http://dx.doi.org/10.2172/974593.

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Blackston, Matthew A., Paul Hausladen, and Jason Newby. Position-Sensitive Fast-Neutron Detector Development in Support of Fuel-Cycle R&D MPACT Campaign. Office of Scientific and Technical Information (OSTI), 2010. http://dx.doi.org/10.2172/1054981.

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Chiang, L. G. Method to Correlate CFD Discriminator Level and Energy Deposition by Neutrons and Photons in a Fast Plastic Scintillating Detector. Office of Scientific and Technical Information (OSTI), 2000. http://dx.doi.org/10.2172/815159.

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