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1

Giaré, William, Eleonora Di Valentino, Alessandro Melchiorri, and Olga Mena. "New cosmological bounds on hot relics: axions and neutrinos." Monthly Notices of the Royal Astronomical Society 505, no. 2 (2021): 2703–11. http://dx.doi.org/10.1093/mnras/stab1442.

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ABSTRACT Axions, if realized in nature, can be copiously produced in the early universe via thermal processes, contributing to the mass-energy density of thermal hot relics. In light of the most recent cosmological observations, we analyse two different thermal processes within a realistic mixed hot dark matter scenario which includes also massive neutrinos. Considering the axion–gluon thermalization channel, we derive our most constraining bounds on the hot relic masses ma < 7.46 eV and ∑mν < 0.114 eV both at 95 per cent CL; while studying the axion–pion scattering, without assu
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2

Vermeesch, Pieter, Martin Rittner, Irene Schimmelpfennig, Lucilla Benedetti, and ASTER Team. "Determining erosion rates in Allchar (Macedonia) to revive the lorandite neutrino experiment." Proceedings of the Royal Society A: Mathematical, Physical and Engineering Sciences 474, no. 2213 (2018): 20170470. http://dx.doi.org/10.1098/rspa.2017.0470.

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205 Tl in the lorandite (TiAsS 2 ) mine of Allchar (Majdan, FYR Macedonia) is transformed to 205 Pb by cosmic ray reactions with muons and neutrinos. At depths of more than 300 m, muogenic production would be sufficiently low for the 4.3 Ma old lorandite deposit to be used as a natural neutrino detector. Unfortunately, the Allchar deposit currently sits at a depth of only 120 m below the surface, apparently making the lorandite experiment technically infeasible. We here present 25 erosion rate estimates for the Allchar area using in situ produced cosmogenic 36 Cl in carbonates and 10 Be in all
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3

Kitabayashi, Teruyuki, and Naoto Koizumi. "Remark on Majorana CP phases in neutrino mixing and leptogenesis." Modern Physics Letters A 29, no. 16 (2014): 1450087. http://dx.doi.org/10.1142/s0217732314500874.

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We estimate Majorana CP phases for a simple flavor neutrino mixing matrix which has been reported by Qu and Ma. Sizes of Majorana CP phases are evaluated in the study of the neutrinoless double beta decay and a particular leptogenesis scenario. We find the dependence of the physically relevant Majorana CP phase on the mass of lightest right-handed neutrino in the minimal seesaw model and the effective Majorana neutrino mass which is related with the half-life of the neutrinoless double beta decay.
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4

Forero, D. V. "Neutrino predictions in a modified Babu-Ma-Valle model." Journal of Physics: Conference Series 447 (July 24, 2013): 012042. http://dx.doi.org/10.1088/1742-6596/447/1/012042.

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5

LAVOURA, L., and H. KÜHBÖCK. "PREDICTIONS OF AN A4 MODEL WITH A FIVE-PARAMETER NEUTRINO MASS MATRIX." Modern Physics Letters A 22, no. 03 (2007): 181–89. http://dx.doi.org/10.1142/s0217732307022608.

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6

Winklehner, Daniel, Janet Conrad, Joseph Smolsky, Loyd Waites, and Philip Weigel. "New Commissioning Results of the MIST-1 Multicusp Ion Source." Journal of Physics: Conference Series 2244, no. 1 (2022): 012013. http://dx.doi.org/10.1088/1742-6596/2244/1/012013.

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Abstract For the sterile neutrino experiment IsoDAR (Isotope Decay-At-Rest), we have developed a compact particle accelerator system delivering a 10 mA, continuous wave (cw) proton beam at 60 MeV to a neutrino production target. The accelerator comprises a compact isochronous cyclotron, an RFQ embedded in the cyclotron yoke, and an ion source. To reduce space charge effects during injection and acceleration, we are accelerating H+ 2 instead of protons. To produce the needed cw H+ 2 beam current of 10 mA (nominal) at the required purity and quality, we have built a new filament driven, multicus
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7

OKADA, HIROSHI. "INVESTIGATIONS OF THE FLAVOR SYMMETRY, RADIATIVE SEESAW MODEL AND COLD DARK MATTER." International Journal of Modern Physics E 16, no. 05 (2007): 1541–56. http://dx.doi.org/10.1142/s0218301307006873.

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It is now clear that the masses of the neutrino sector are much lighter than those of the other three sectors. Canonial seesaw model would be the most famous for the above explanation. But one must introduce heavy particles that will not be able to observed with present scientific technologies. On the other hand, there are many attempts to explain the neutrino masses radiatively by means of inert Higgses, which do not have the vacuum expectation values. Then one can discuss cold dark matter candidates, because of no needing so heavy particles. The most famous work would be the Zee model17. Rec
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8

D'Eramo, Francesco, Eleonora Di Valentino, William Giarè, et al. "Cosmological bound on the QCD axion mass, redux." Journal of Cosmology and Astroparticle Physics 2022, no. 09 (2022): 022. http://dx.doi.org/10.1088/1475-7516/2022/09/022.

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Abstract We revisit the joint constraints in the mixed hot dark matter scenario in which both thermally produced QCD axions and relic neutrinos are present. Upon recomputing the cosmological axion abundance via recent advances in the literature, we improve the state-of-the-art analyses and provide updated bounds on axion and neutrino masses. By avoiding approximate methods, such as the instantaneous decoupling approximation, and limitations due to the limited validity of the perturbative approach in QCD that forced to artificially divide the constraints from the axion-pion and the axion-gluon
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9

MA, ERNEST. "SUPERSYMMETRIC A4×Z3 AND A4 REALIZATIONS OF NEUTRINO TRIBIMAXIMAL MIXING WITHOUT AND WITH CORRECTIONS." Modern Physics Letters A 22, no. 02 (2007): 101–6. http://dx.doi.org/10.1142/s0217732307022505.

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In an improved application of the tetrahedral symmetry A4 first introduced by Ma and Rajasekaran, supplemented by the discrete symmetry Z3 as well as supersymmetry, a two-parameter form of the neutrino mass matrix is derived which exhibits the tribimaximal mixing of Harrison, Perkins and Scott. This form is the same as the one obtained previously by Altarelli and Feruglio, and the inverse of that obtained by Babu and He. If only A4 is used, then corrections appear, making tan2 θ12 different from 0.5, without changing significantly sin22θ23 from one or θ13 from zero.
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10

Đặng, Thị Huyền Trân, та Thanh Phong Nguyễn. "Leptogenesis trong mô hình đối xứng S4 modular với cơ chế seesaw tối thiểu". CTU Journal of Science 61, № 3 (2025): 117–24. https://doi.org/10.22144/ctujos.2025.099.

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Mô hình đối xứng S4 modular được xây dựng với cơ chế seesaw tối thiểu nhằm làm giảm bớt số lượng các tham số tự do cũng như các hạt mới khi mở rộng Mô hình chuẩn. Mô hình nghiên cứu đã thỏa mãn tất cả các dữ liệu thực nghiệm khu vực lepton như khối lượng neutrino, các tham số của ma trận trộn lepton. Trên cơ sở đó, miền giá trị được phép của các tham số của mô hình cũng được xác định. Mô hình cũng giải thích thành công bất đối xứng giữa vật chất và phản vật chất của vũ trụ thông qua quá trình leptogenesis.
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11

Jimbo, Kouichi, Toshiyuki Shirai, Ka-Ngo Leung, and Karl van Bibber. "Proposal for a compact neutron generator based on a negative deuterium ion beam." Journal of Physics: Conference Series 2420, no. 1 (2023): 012035. http://dx.doi.org/10.1088/1742-6596/2420/1/012035.

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Abstract Interest in high intensity generators of neutrons for basic and applied science has been growing, and thus the demand for an economical neutron generator has been growing. A major driver for the development of high intensity neutron generators are studies of neutron disturbance in integrated circuits, for which a compact generator that can be easily accommodated in an ordinary size lab would be highly desirable. We have investigated possible designs for neutron generators based on the D-D fusion reaction, which produce direction dependent mono-energetic neutrons with carry-off energy
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12

Sahoo, Rudra N., Moshe Tessler, Shlomi Halfon, et al. "Stellar s-process neutron capture cross sections on ASe and ACe." EPJ Web of Conferences 279 (2023): 06002. http://dx.doi.org/10.1051/epjconf/202327906002.

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We report on experiments at the Soreq Applied Research Accelerator Facility Liquid-Lithium Target (SARAF-LiLiT) laboratory dedicated to the study of s-process neutron capture reactions. The kW-power proton beam at 1.92 MeV (1-2 mA) from SARAF Phase I yields high-intensity 30 keV quasi-Maxwellian neutrons (3-5 1010 n/s). The high neutron intensity enables Maxwellian averaged cross sections (MACS) measurements of samples with short-lived decay products. Neutron capture reactions on natSe and natCe were investigated by activation in the LiLiT neutron beam and γ-spectrometry measurements of their
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13

Khorasanov, Georgiy, Dmitriy Samokhin, Aleksandr Zevyakin, Yevgeniy Zemskov, and Anatoliy Blokhin. "Lead reactor of small power with metallic fuel." Nuclear Energy and Technology 4, no. 2 (2018): 99–102. http://dx.doi.org/10.3897/nucet.4.30527.

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The possibility for obtaining a hard neutron spectrum in small reactor cores has been considered. A harder spectrum than spectra in known fast sodium cooled and molten salt reactors has been obtained thanks to the selection of relatively small core dimensions and the use of metallic fuel and natural lead (natPb) coolant. The calculations for these compositions achieve an increased average neutron energy and a large fraction of hard neutrons in the spectrum (with energies greater than 0.8 MeV) caused by a minor inelastic interaction of neutrons with the fuel with no light chemical elements and
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14

Kumada, Hiroaki, Susumu Tanaka, Fujio Naito, et al. "Neutron beam performance of iBNCT as linac-based neutron source for boron neutron capture therapy." EPJ Web of Conferences 231 (2020): 01003. http://dx.doi.org/10.1051/epjconf/202023101003.

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The linac-based neutron source “iBNCT” developed by the Tsukuba team has been shown to generate a large intensity of neutrons. To confirm the applicability of the device to BNCT, several characteristic measurements have been implemented. In a water phantom experiment, when the accelerator was operated with an average current of 1.4 mA, the maximum thermal neutron flux was approximately 7.8 × 108 (cm-2s-1). From estimation of the stability of the linac, the results demonstrate its applicability to actual treatment.
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15

Weissman, L., A. Kreisel, and A. Shor. "Characterization of the LEBT based neutron source." Journal of Instrumentation 19, no. 08 (2024): T08007. http://dx.doi.org/10.1088/1748-0221/19/08/t08007.

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Abstract Neutron generation by implantation and subsequent beam interaction of 40 keV deuterons at Soreq Applied Research Accelerator Facility (SARAF) low energy beam transport (LEBT) section was measured and characterized. The generation of 2.45 MeV neutrons by a deuteron beam of several mA was verified by a neutron spectrometer. Relative neutron yields were studied as a function of beam energy and beam spot size using two types of available implantation surfaces. The buildup of neutron yield was studied at long and short time scales. Absolute neutron yield was measured via activation at seve
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16

Khorasanov, Georgiy, Dmitriy Samokhin, Aleksandr Zevyakin, Yevgeniy Zemskov, and Anatoliy Blokhin. "Lead reactor of small power with metallic fuel." Nuclear Energy and Technology 4, no. (2) (2018): 99–102. https://doi.org/10.3897/nucet.4.30527.

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The possibility for obtaining a hard neutron spectrum in small reactor cores has been considered. A harder spectrum than spectra in known fast sodium cooled and molten salt reactors has been obtained thanks to the selection of relatively small core dimensions and the use of metallic fuel and natural lead (<sup>nat</sup>Pb) coolant. The calculations for these compositions achieve an increased average neutron energy and a large fraction of hard neutrons in the spectrum (with energies greater than 0.8 MeV) caused by a minor inelastic interaction of neutrons with the fuel with no light chemical el
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17

Taskaev, Sergey, Evgenii Berendeev, Marina Bikchurina, et al. "Neutron Source Based on Vacuum Insulated Tandem Accelerator and Lithium Target." Biology 10, no. 5 (2021): 350. http://dx.doi.org/10.3390/biology10050350.

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A compact accelerator-based neutron source has been proposed and created at the Budker Institute of Nuclear Physics in Novosibirsk, Russia. An original design tandem accelerator is used to provide a proton beam. The proton beam energy can be varied within a range of 0.6–2.3 MeV, keeping a high-energy stability of 0.1%. The beam current can also be varied in a wide range (from 0.3 mA to 10 mA) with high current stability (0.4%). In the device, neutron flux is generated as a result of the 7Li(p,n)7Be threshold reaction. A beam-shaping assembly is applied to convert this flux into a beam of epith
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18

Nishitani, Takeo, Sachiko Yoshihashi, Yuuki Tanagami, et al. "Neutronics Analyses of the Radiation Field at the Accelerator-Based Neutron Source of Nagoya University for the BNCT Study." Journal of Nuclear Engineering 3, no. 3 (2022): 222–32. http://dx.doi.org/10.3390/jne3030012.

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The Nagoya University Accelerator-driven Neutron Source (NUANS) is an accelerator-based neutron source by 7Li(p,n)7Be reaction with a 2.8 MeV proton beam up to 15 mA. The fast neutrons are moderated and shaped to beam with a Beam Shaping Assembly (BSA). NUANS is aiming at the basic study of the Boron Neutron Capture Therapy (BNCT) such as an in vitro cell-based irradiation experiment using a water phantom. Moreover, the BSA is developed as a prototype of one for human treatment. We have evaluated the radiation field of NUANS by a Monte Carlo code PHITS. It is confirmed that the radiation chara
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19

Muraz, Jean-François, Daniel Santos, Véronique Ghetta, et al. "Development of a regenerated Beryllium target and a thermal test facility for Compact Accelerator-based Neutron Sources." EPJ Web of Conferences 231 (2020): 03003. http://dx.doi.org/10.1051/epjconf/202023103003.

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Recently, the possibility to use compact accelerators coupled to high current ion sources for the production of intense low energy proton or deuteron beams has motivated many research laboratories to develop accelerator based neutrons sources for several purposes, including Neutron Capture Therapy (NCT). The NCT needs a high flux, about 10 9 n.cm-2.s-1, of thermal neutrons (E&lt;10 keV) at the tumour site. Up to now, the NCT required neutron flux was mainly delivered by nuclear reactors. However, the production of such neutron flux is now possible using proton or deuteron beams on specific tar
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20

Schmidt, A., C. Goyon, A. Link, et al. "Measuring characteristic differences between high- and low-performing discharges on the MegaJOuLe Neutron Imaging Radiography (MJOLNIR) DPF." Physics of Plasmas 29, no. 6 (2022): 062708. http://dx.doi.org/10.1063/5.0089121.

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A dense plasma focus (DPF) is a compact coaxial plasma gun, which completes its discharge as a Z-pinch, producing short (&lt;100 ns) pulses of ions, x rays, and/or neutrons. Lawrence Livermore National Laboratory recently constructed and began operating a new device, the MJOLNIR (MegaJOuLe Neutron Imaging Radiography) DPF, which is designed for single-pulse flash neutron radiography. This device has achieved neutron yields of up to 4.1 × 1011 neutrons/pulse at 3.3 MA peak current, and higher-current commissioning is under way. Like most DPFs, MJOLNIR exhibits variable yields in some configurat
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21

Sadighzadeh, A., A. Salehizadeh, M. Mohammadzadeh, et al. "Prediction of Neutron Yield of IR-IECF Facility in High Voltages Using Artificial Neural Network." Journal of Engineering 2014 (2014): 1–7. http://dx.doi.org/10.1155/2014/798160.

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Artificial neural network (ANN) is applied to predict the number of produced neutrons from IR-IECF device in wide discharge current and voltage ranges. Experimentally, discharge current from 20 to 100 mA had been tuned by deuterium gas pressure and cathode voltage had been changed from −20 to −82 kV (maximum voltage of the used supply). The maximum neutron production rate (NPR) of 1.46 × 107 n/s had occurred when the voltage was −82 kV and the discharge current was 48 mA. The back-propagation algorithm is used for training of the proposed multilayer perceptron (MLP) neural network structure. T
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22

Korobeynikov, Valery V., Valery V. Kolesov, and Igor A. Ignatiev. "Computational simulation of minor actinide burning in a BN-600 reactor with fuel without uranium and plutonium." Nuclear Energy and Technology 9, no. 1 (2023): 59–64. http://dx.doi.org/10.3897/nucet.9.102776.

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The paper presents the results of studies on the burning of minor actinides (MA) extracted from SNF of thermal reactors in a BN-600 reactor, which uses the complete set of MAs instead of traditional nuclear fuel types: uranium and/or plutonium. The advantages of such approach to MA burning are that long-lived waste is recycled and energy is produced that can be used, e.g., to generate electricity. Besides, where, e.g., a reactor with uranium or MOX fuel is used for transmutation, apart from burning “foreign” minor actinides, it will additionally generate “its own” MAs. The studies have shown t
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23

Korobeynikov, Valery V., Valery V. Kolesov, and Igor A. Ignatiev. "Computational simulation of minor actinide burning in a BN-600 reactor with fuel without uranium and plutonium." Nuclear Energy and Technology 9, no. (1) (2023): 59–64. https://doi.org/10.3897/nucet.9.102776.

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The paper presents the results of studies on the burning of minor actinides (MA) extracted from SNF of thermal reactors in a BN-600 reactor, which uses the complete set of MAs instead of traditional nuclear fuel types: uranium and/or plutonium. The advantages of such approach to MA burning are that long-lived waste is recycled and energy is produced that can be used, e.g., to generate electricity. Besides, where, e.g., a reactor with uranium or MOX fuel is used for transmutation, apart from burning "foreign" minor actinides, it will additionally generate "its own" MAs. The studies have shown t
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24

Koshkarev, A. M., I. M. Shchudlo, and S. Yu Taskaev. "Development and Implementation of the D-Pace Ion Source Automation System for the VITA Accelerator." SIBERIAN JOURNAL OF PHYSICS 19, no. 1 (2024): 54–60. http://dx.doi.org/10.25205/2541-9447-2024-19-1-54-60.

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The VITA accelerator neutron source based on a vacuum insulated tandem accelerator operates at the Institute of Nuclear Physics SB RAS. The development of a separate compact facility for the generation of fast neutrons is an actual task, it will allow the treatment of malignant tumors via boron-neutron capture therapy with fast neutrons and a number of other applications. To control the facility, store and analyze data, the author has previously created an automation system that allows the operator to provide long-term stable proton or deuteron beam production in a wide range of energy and cur
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25

BYSTRITSKY, V. M., V. M. GREBENYUK, S. S. PARZHITSKI, et al. "Experimental investigation of dd reaction in range of ultralow energies using Z-pinch." Laser and Particle Beams 18, no. 2 (2000): 325–33. http://dx.doi.org/10.1017/s0263034600182230.

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Experimental results on measurement of dd-reaction cross sections in the energy range of 0.1–1.5 keV using the Z-pinch technique are presented. The experiment was fulfilled at the high current generator of the High-Current Electronics Institute, city of Tomsk, Russia. The dd-fusion neutrons were registered by time-of-flight scintillator detectors and BF3 detectors of thermal neutrons. The estimates were obtained at 90% of the confidence level for the upper limits of the neutron-producing dd-reaction cross sections for average deuteron collision energies of 0.11, 0.34, 0.37, and 1.46 keV. These
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26

Hidaka, Hiroshi, Shigekazu Yoneda, Kunihiko Nishiizumi, and Marc Caffee. "The Neutron Energy Spectra of Lunar Meteorites Evaluated from Sm and Er Isotopic Compositions." Astrophysical Journal 925, no. 2 (2022): 209. http://dx.doi.org/10.3847/1538-4357/ac423a.

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Abstract Cosmic-ray exposure records of 13 lunar meteorites, Dhofar 081, Dhofar 910, Dhofar 911, Northwest Africa (NWA) 482, NWA 2995, NWA 2996, NWA 3136, NWA 3163, NWA 4472, NWA 4734, NWA 4884, NWA 4932, and NWA 4936, were characterized from the abundances of spallogenic (10Be and 26Al) and neutron-captured (36Cl, 41Ca,150Sm, and 168Er) nuclides produced by cosmic-ray irradiation. Assuming a single-stage irradiation model for individual meteorites, 11 of the 13 meteorites had resided at shallow depths in the range of 55 to 330 g cm−2 from the lunar surface and experienced cosmic-ray irradiati
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27

Paul, Michael, Ido Silverman, Shlomi Halfon, et al. "A 50 kW Liquid-Lithium Target for BNCT and Material-Science Applications." EPJ Web of Conferences 231 (2020): 03004. http://dx.doi.org/10.1051/epjconf/202023103004.

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A compact Liquid Lithium Target (LiLiT) has been operating at SARAF for several years with beam power of several kW (1.9-2.5 MeV, up to 2 mA). When bombarding the lithium with low energy protons neutrons are generated. The neutron source, mainly used for nuclear astrophysics research, was decommissioned in 2016 towards an upgraded model - with possible applications to Boron Neutron Capture Therapy (BNCT) and material-science studies. The improved version has been designed to sustain 50 kW proton beam power (2.5 MeV, ~20 mA) to provide sufficient neutron flux required for clinical BNCT applicat
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28

Darnowski, Piotr, and Nikolaj Uzunow. "Minor actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor." Nukleonika 60, no. 1 (2015): 171–79. http://dx.doi.org/10.1515/nuka-2015-0034.

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Abstract An analysis of the influence of addition of minor actinides (MA) to the fast reactor fuel on the most important safety characteristics was performed. A special emphasis was given to the total control rods worth in order to describe qualitatively and quantitatively its change with MA content. All computations were performed with a homogeneous assembly model of modified BN-600 sodium-cooled fast reactor core with 0, 3 and 6% of MA. A model was prepared for the Monte Carlo neutron transport code MCNP5 for fresh fuel in the beginning-of-life (BOL) state. Additionally, some other parameter
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29

Yan, Xuewen, Pei Qiao, Deyuan Li, Hua Li, Liye Liu, and Faguo Chen. "Design of BSA for BCNT device based on 10 MeV proton beam generated by accelerator and evaluation of clinical dose." Journal of Instrumentation 20, no. 07 (2025): P07029. https://doi.org/10.1088/1748-0221/20/07/p07029.

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Abstract The rapid development of accelerators has accelerated the clinical application of Boron Neutron Capture Therapy (BNCT). The beam moderation and Beam Shaping Assembly (BSA) in Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT) device is crucial for the production of epithermal neutrons. Based on the 10 MeV proton beam generated by accelerator, the BSA was designed using the Monte Carlo simulation method, and the BSA design scheme was verified by the dose distribution of the epithermal neutron beam in the human head model. The results show that when the current intensity of proto
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30

Konashi, Kenji, Kunihiro Itoh, Tsugio Yokoyama, and Michio Yamawaki. "Utilization Research and Development of Hydride Materials in Fast Reactors." Advances in Science and Technology 94 (October 2014): 23–31. http://dx.doi.org/10.4028/www.scientific.net/ast.94.23.

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Metal hydrides have high hydrogen atom density, which is equivalent to that of liquid water. An application of the hafnium hydride has been investigated as a neutron absorber in the Fast Breeder Reactors (FBRs). Fast neutrons are efficiently moderated by hydrogen in Hf hydrides and are absorbed by Hf. Since three isotopes of Hf have large cross sections, increase in the life of control rod is considered by Hf hydride. Results of design study of the core with Hf hydride control rods shows that the long lived hafnium hydride control rod is feasible in the large sodium-cooled FBR. Results of irra
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31

Knaster, Juan, and Yoshikazu Okumura. "Accelerators for Fusion Materials Testing." Reviews of Accelerator Science and Technology 08 (January 2015): 115–42. http://dx.doi.org/10.1142/s1793626815300078.

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Fusion materials research is a worldwide endeavor as old as the parallel one working toward the long term stable confinement of ignited plasma. In a fusion reactor, the preservation of the required minimum thermomechanical properties of the in-vessel components exposed to the severe irradiation and heat flux conditions is an indispensable factor for safe operation; it is also an essential goal for the economic viability of fusion. Energy from fusion power will be extracted from the 14 MeV neutron freed as a product of the deuterium–tritium fusion reactions; thus, this kinetic energy must be ab
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32

Blaser, Jean-Pierre, Otto Haas, Claude Petitjean, et al. "Experimental Investigation of Cold Fusion Phenomena in Palladium." CHIMIA 43, no. 9 (1989): 262. https://doi.org/10.2533/chimia.1989.262.

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We conducted at the Paul Scherrer Institute a series of Pd-D2O electrolysis experiments to investigate the existence of the «cold fusion» phenomenon. In a D2O-test cell and a H2O-reference cell, a search for excess heat was made, using a closed-circuit calorimetry set-up, and running currents onto 1 mm and 2 mm palladium cathode wires from 120 to 545 mA/cm2. Simultaneously, with a NE213 neutron and a BGO gamma detector, we searched for the occurrence of excess neutrons or gammas that might arise from nuclear fusion processes. Our results are negative, i.e. we detected no excess heat within les
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33

Wang, Deli, Daniel Moses, Guillermo Bazan, Alan Heeger, and Jyostana Lal. "CONFORMATION OF A CONJUGATED POLYELECTROLYTE IN AQUEOUS SOLUTION: SMALL ANGLE NEUTRON SCATTERING." Journal of Macromolecular Science, Part A 38, no. 12 (2001): 1175–89. http://dx.doi.org/10.1081/ma-100108376.

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34

Venkatesan, T. R., K. Pande, and K. Gopalan. "40Ar-39Ar Darting of Deccan Basalts." Journal Geological Society of India 27, no. 1 (1986): 102–9. http://dx.doi.org/10.17491/jgsi/1986/270102.

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Abstract The feasibility of dating igneous rocks by the 40Ar-39Ar method in India using the Apsara nuclear reactor at BARC, Bombay is reported, based on measurements on two tholeiitic basalts and one alkali basalt associated with the Deccan volcanism. The ages of the tholeiitic basalts are 71±4 Ma and 65±4 Ma, respectively and that of the alkali basalt is 682 Ma. Apart from the low neutron flux requiring long irradiation times, the neutron fluence within the sample irradiation volume is somewhat anisotropic. The latter needs to be minimised to achieve the higher precision the method is capable
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35

Paul, Michael, Moshe Tessler, Shlomi Halfon, et al. "Study of Astrophysical s-Process Neutron Capture Reactions at the High-Intensity SARAF-LiLiT Neutron Source." EPJ Web of Conferences 232 (2020): 01003. http://dx.doi.org/10.1051/epjconf/202023201003.

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We report on recent experiments at the Soreq Applied Research Accelerator Facility Liquid-Lithium Target (SARAF-LiLiT) laboratory dedicated to the study of s-process neutron capture reactions. The kW-power proton beam at 1.92 MeV (1-2 mA) from SARAF Phase I yields high-intensity 30 keV quasi-Maxwellian neutrons (3-5×1010 n/s). The high neutron intensity enables Maxwellian averaged cross sections (MACS) measurements of low-abundance or radioactive targets. Neutron capture reactions on the important s-process branching points 147Pm and 171Tm were investigated by activation in the LiLiT neutron b
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36

Sycheva, Т. V., Е. А. Berendeev, G. D. Verkhovod, and S. Yu Taskaev. "A Neutron Beam Shaping Assembly for Boron Neutron Capture Therapy of Superficial Tumors." SIBERIAN JOURNAL OF PHYSICS 18, no. 3 (2024): 31–42. http://dx.doi.org/10.25205/2541-9447-2023-18-3-31-42.

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The Vacuum Insulated Tandem accelerator have been developed in Budker Institute of Nuclear Physics. Neutrons are generated in 7Li(p,n)7Be reaction. Neutron beam shaping assembly is used for therapeutic beam forming. It consists of the moderator, reflector and filter. Magnesium fluoride is considered optimal material for neutron slowing down because of noticeable cross section of inelastic neutron scattering. Previously, we showed that it is optimal to use proton beam at energy 2.3 MeV for neutron generation.As a result of a critical analysis of our earlier decisions on the methods used to form
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37

He, Liaoyuan, Liang Chen, Shaopeng Xia, and Yang Zou. "Minor Actinides Transmutation and 233U Breeding in a Closed Th-U Cycle Based on Molten Chloride Salt Fast Reactor." Energies 15, no. 24 (2022): 9472. http://dx.doi.org/10.3390/en15249472.

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Long-lived minor actinides (MAs) are one of the primary contributors to the long-term radiological hazards of nuclear waste, and the buildup of MAs is hampering the development of nuclear power. The transmutation of MAs in reactors is regarded as a potential way to replace direct disposal to reduce the impact of MA on the environment and improve the utilization of fuel. Due to its superior features, such as outstanding neutron economy, no fuel assembly fabrication, high neutron flux, and especially online refueling and reprocessing, the molten chloride salt fast reactor (MCFR) is regarded as o
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38

Shlenskii, Mikhail, and Boris Kuteev. "System Studies on the Fusion-Fission Hybrid Systems and Its Fuel Cycle." Applied Sciences 10, no. 23 (2020): 8417. http://dx.doi.org/10.3390/app10238417.

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This paper is devoted to applications of fusion-fission hybrid systems (FFHS) as a powerful neutron source implementing transmutation of minor actinides (MA: Np, Am, Cm) extracted from the spent nuclear fuel (SNF) of nuclear reactors. Calculations which simulated nuclide kinetics for the metallic fuel containing MA and neutron transport were performed for particular facilities. Three FFHS with fusion power equal to 40 MW are considered in this study: demo, pilot-industrial and industrial reactors. In addition, needs for a fleet of such reactors are assessed as well as future FFHSs’ impact on R
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39

Melatos, A., and E. S. Phinney. "Hydromagnetic Structure of a Neutron Star Accreting at Its Polar Caps." Publications of the Astronomical Society of Australia 18, no. 4 (2001): 421–30. http://dx.doi.org/10.1071/as01056.

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AbstractThe hydromagnetic structure of a neutron star accreting symmetrically at both magnetic poles is calculated as a function of accreted mass, Ma, starting from a polytropic sphere plus central magnetic dipole (Ma =0) and evolving the configuration through a quasistatic sequence of twodimensional, Grad–Shafranov equilibria as Ma increases. It is found that the accreted material spreads equatorward under its own weight, compressing the magnetic field into a thin boundary layer and burying it everywhere except in a narrow, equatorial belt. The magnetic dipole moment of the star is given by µ
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40

Onischuk, H. A., Yu A. Kurachenko, and Yu G. Zabaryansky. "Photoneutrons for Radiation Therapy and Radionuclide Production." KnE Engineering 3, no. 3 (2018): 41. http://dx.doi.org/10.18502/keg.v3i3.1605.

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The possibility of organizing neutron therapy with a photoneutron beam produced by the electron accelerator target, and ensuring the required dose at the tumor at a reasonable exposure time and with minimal impact on patients investigated. Generation of neutrons from the target of electron accelerator takes place in two stages: e- ® γ ® n, and in the selected electron energy range of 20-100 MeV, the bremsstrahlung gamma radiation in many times (~ 3 orders of magnitude) offers more than “useful” neutron yield. This raises the problem of the selective control of the “harmful” for radiotherapy se
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41

Welton, R. F., B. X. Han, M. P. Stockli, et al. "Recent H- ion source research and development at the Oak Ridge National Laboratory*." Journal of Instrumentation 18, no. 12 (2023): C12011. http://dx.doi.org/10.1088/1748-0221/18/12/c12011.

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Abstract The U.S. Spallation Neutron Source (SNS) is a state-of-the-art neutron scattering facility delivering the world's most intense pulsed neutron beams to a wide array of instruments which are used to conduct investigations in many fields of science and engineering. Neutrons are produced from spallation of liquid Hg by bombardment of short (∼1 μs), intense (∼35 A) pulses of protons delivered at 60 Hz by a storage ring which is fed by a high-intensity, ∼1 GeV H- LINAC. This facility has operated almost continuously since 2006, with ion source performance increasing over those years, and cu
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42

Itoh, Keiji, Masakatsu Misawa, and Toshiharu Fukunaga. "Neutron Diffraction of Amorphous Se-Te Prepared by MA." Journal of the Japan Society of Powder and Powder Metallurgy 48, no. 9 (2001): 806–9. http://dx.doi.org/10.2497/jjspm.48.806.

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43

Bakr, M., T. Sakabe, J. P. Wulfkühler, et al. "Influence of electrodes' geometrical properties on the neutron production rate of a discharge fusion neutron source." Physics of Plasmas 30, no. 3 (2023): 032701. http://dx.doi.org/10.1063/5.0134631.

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Trapping ions, such as deuterium and tritium, inside a potential well to generate neutrons is a well-established technology through electric and magnetic fields via the inertial electrostatic confinement fusion (IECF) and the tokamak, respectively. In the IECF, the straightforward configuration is a concentric cathode connected to a negative bias, surrounded by a grounded anode that serves as a vacuum vessel. Theoretically, neutrons are generated inside the vessel through fusion between ions that are accelerated by applying several tens kV voltage and tens mA current. Many parameters affect th
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44

Cordelli, M., E. Diociaiuti, A. Ferrari, et al. "An induced annealing technique for SiPMs neutron radiation damage." Journal of Instrumentation 16, no. 12 (2021): T12012. http://dx.doi.org/10.1088/1748-0221/16/12/t12012.

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Abstract The use of Silicon Photo-Multipliers (SiPMs) has become popular in the design of High Energy Physics experimental apparatus with a growing interest for their application in detector area where a significant amount of non-ionising dose is delivered. For these devices, the main effect caused by the neutron fluence is a linear increase of the leakage current. In this paper, we present a technique that provides a partial recovery of the neutron damage on SiPMs by means of an Electrical Induced Annealing. Tests were performed, at the temperature of 20°C, on a sample of three SiPM arrays (2
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45

Tang, Jian, Meng Liu, Penghui Gao, Rui Qiu, Xinpeng Zhou, and Jie Yan. "Experimental study on pulse characteristics of smaller diameter Penning ion source." Journal of Instrumentation 20, no. 03 (2025): P03006. https://doi.org/10.1088/1748-0221/20/03/p03006.

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Abstract For logging pulsed neutron tube with diameter less than 25 mm, a smaller diameter Penning ion source with a cylindrical plasma volume of Φ8 mm × 9 mm was designed to investigate the pulse characteristics of anode current. The pulse time and amplitude characteristics of anode current as a function of deuterium pressure and anode voltage were studied experimentally. The preferred working parameters for this smaller diameter Penning ion source were suggested, then obtained the pulse amplitude of anode current in the range of 1 mA∼ 3.5 mA, with the shortest pulse delay time of anode curre
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46

Syarifah, Ratna Dewi, Fajri Prasetya, Ahmad Muzaki Mabruri, Artoto Arkundato, and Nuri Trianti. "The Effect of Adding Minor Actinide Fuel Rods on GFR Reactor in Radiopharmaceutical Waste Production Using OpenMC Program." Science and Technology Indonesia 9, no. 4 (2024): 857–65. http://dx.doi.org/10.26554/sti.2024.9.4.857-865.

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GFR is a generation IV reactor based on helium gas refrigeration capable of working at very high temperatures. The fast spectrum in this reactor makes it possible to use nitride-based fuel, namely Uranium Plutonium Nitride (UN-PuN). Adding minor actinide (MA) material to the primary fuel, UN-PuN can maximize reactor performance to near critical from the beginning to the end of burn-up. This study aims to analyze the effect of adding MA fuel rods to the heterogeneous core of 5 fuel variations (F1, F2, F3, F4, F5) on the probability of radiopharmaceutical waste production. The method in this res
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47

Kashirsky, Andrey A., Vladimir M. Solomatin, Sergey A. Panov, et al. "Analysis of radwaste accumulation in various scenarios of NP development." Nuclear Energy and Technology 10, no. (1) (2024): 73–80. https://doi.org/10.3897/nucet.10.118046.

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Within the framework of "Proryv" project a radiation-equivalent approach to radioactive waste management is being envisioned with U and Pu recycling and MA transmutation. Successful industry-wide implementation of the design approaches should be planned in order to avoid considerable financial and radiological encumbrances caused by the NFC final stage for two-component nuclear power system (NPS) under formation on the basis of thermal and fast reactors. In order to ensure a successful industry-wide implementation of the approaches being developed, the back-end of the NFC should not constitute
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48

Lee, Dong Won, Kihyun Lee, Bongki Jung, et al. "Development status of 30 MeV cyclotron-based neutron source in Korea." EPJ Web of Conferences 298 (2024): 05004. http://dx.doi.org/10.1051/epjconf/202429805004.

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KAERI has developed plasma heating systems and fusion engineering technologies such as blanket first wall and breeding blanket for nuclear fusion reactor development, as well as nuclear data production. Based on these technologies, we have successfully developed various ion sources-based D-D compact neutron generators and are developing a 30 MeV cyclotron-based neutron source for on-site neutron radiography service. Final construction and phase-1 licensing have been completed, and preliminary tests have demonstrated neutron yield of a 1.6x1012 n/s at 30 MeV and 0.01 mA. Under these conditions,
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49

Chahidi, Hassan, Hamid Bounouira, Hamid Amsil, et al. "Comparison of relative and k0 neutron activation analysis methods at MA-R1 TRIGA MARK II Research Reactor of CNESTEN (Morocco)." E3S Web of Conferences 336 (2022): 00054. http://dx.doi.org/10.1051/e3sconf/202233600054.

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Since the installation of the TRIGA MARK II reactors in the National Centre for Nuclear Energy, Science and Technology (CNESTEN), Neutron Activation Data Analysis software (NADA) for neutron activation analysis (NAA) based on the relative method was the first software used; Over the years, the neutron activation analysis laboratory has been seeking to develop other softwares based on k0-INAA standardization namely the K0-IAEA software and the k0 software for Windows. In this paper we will focus on the comparison between the performance of k0 software for Windows and NADA. We compared the resul
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50

Shuai, H., G. Anda, E. Dian, et al. "Progress of the first accelerator-based compact neutron source in Hungary." EPJ Web of Conferences 298 (2024): 05005. http://dx.doi.org/10.1051/epjconf/202429805005.

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The first compact accelerator-based neutron source (CANS) for industrial and healthcare use in Hungary, the ‘LvB’ project, is being installed at the premises of Mirrotron Ltd. at Martonvásár. In the first phase of the operation, a fast neutron spectrum with energies up to 1 MeV is generated by the impact of a 2.5 MeV and 1 mA time-average intensity pulsed proton beam on a Li target. This target is surrounded by a lead reflector and the beam extraction opening faces of a bi-spectral para-H2 and H2O quasi-one-dimensional moderator, to provide cold and thermal neutron beams primarily for applied
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