Готові списки джерел за темами / Neutrons

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Добірка наукової літератури з теми "Neutrons"

Автор: Grafiati
Опубліковано: 4 червня 2021
Оновлено: 23 листопада 2024

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Статті в журналах з теми "Neutrons"

1

SAHU, SARIRA. "MULTI-GeV NEUTRINOS DUE TO $n\bar n$ OSCILLATION IN GAMMA-RAY BURST FIREBALLS." Modern Physics Letters A 22, no. 40 (December 28, 2007): 3065–72. http://dx.doi.org/10.1142/s021773230702378x.

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The long and short gamma-ray bursts are believed to be produced due to collapse of massive stars and merger of compact binaries respectively. All these objects are rich in neutron and the jet outflow from these objects must have a neutron component in it. By postulating the [Formula: see text] oscillation in the gamma-ray burst fireball, we show that, 19–38 GeV neutrinos and anti-neutrinos can be produced due to annihilation of anti-neutrons with the background neutrons. These neutrinos and anti-neutrinos will be produced before the 5–10 GeV neutrinos due to dynamical decoupling of neutrons from the rest of the fireball. Observation of these neutrinos will shed more light on the nature of the GRB progenitors and also be a unique signature of physics beyond the standard model. A possible way of detecting these neutrinos in future is also discussed.
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2

Daywitt, William C. "The Neutrino Decay of the Free Neutron and the Neutrino Structure According to the Planck Vacuum Theory." European Journal of Engineering and Technology Research 6, no. 5 (July 27, 2021): 73–75. http://dx.doi.org/10.24018/ejers.2021.6.5.2524.

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The Planck vacuum (PV) theory derives equations for the neutrino and antineutrino, and relates them to the unstable free neutron and antineutron. Remarkably, these neu- trons and neutrinos share the same wavefunction solutions that describe the proton and electron and their antiparticle cores. The neutrino and antineutrino are chargeless and massless; so their propagation through matter goes unnoticed, making these neutrinos invisible. The equations to follow that describe these pseudo-particles are the theoretical embodiment of the circa 1930 Pauli neutrino hypothesis. Finally, depending on one’s perspective, the neutrons can be viewed as decaying meta-particles or as stable nuclear particles.
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Daywitt, William C. "The Neutrino Decay of the Free Neutron and the Neutrino Structure According to the Planck Vacuum Theory." European Journal of Engineering and Technology Research 6, no. 5 (July 27, 2021): 73–75. http://dx.doi.org/10.24018/ejeng.2021.6.5.2524.

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The Planck vacuum (PV) theory derives equations for the neutrino and antineutrino, and relates them to the unstable free neutron and antineutron. Remarkably, these neu- trons and neutrinos share the same wavefunction solutions that describe the proton and electron and their antiparticle cores. The neutrino and antineutrino are chargeless and massless; so their propagation through matter goes unnoticed, making these neutrinos invisible. The equations to follow that describe these pseudo-particles are the theoretical embodiment of the circa 1930 Pauli neutrino hypothesis. Finally, depending on one’s perspective, the neutrons can be viewed as decaying meta-particles or as stable nuclear particles.
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4

Bondar, Aleksandr, Alexey Buzulutskov, Aleksandr Burdakov, Evgeny Grishnyaev, Aleksandr Dolgov, Aleksandr Makarov, Sergey Polosatkin, Andrey Sokolov, Sergey Taskaev, and Lev Shekhtman. "Proposal for Neutron Scattering Systems for Calibration of Dark Matter Search and Low-Energy Neutrino Detectors." Siberian Journal of Physics 8, no. 3 (October 1, 2013): 27–38. http://dx.doi.org/10.54362/1818-7919-2013-8-3-27-38.

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The proposal of two neutron scattering systems for calibration of two-phase cryogenic avalanche detectors with high sensitivity being developed at Budker INP is presented. This kind of detectors is designed for the search of dark matter and low energy neutrino detection, in particular, coherent neutrino scattering on nuclei. Detector calibration is made with a measurement of ionization yield and scintillation quenching factor for low energy recoiling nuclei (in 0.5 to 100 keV range) originating from elastic scattering of neutrons. To provide wide range of recoiling nuclei energies two systems of neutron scattering are proposed. The first one is based on small-sized DD generator of fast (2.45 MeV) monoenergetic neutrons operating on sealed neutron tube. The second one is based on tandem proton accelerator and lithium target and capable of generation of monoenergetic epithermal neutrons with energy up to 100 keV
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5

Chakraborty, Sabyasachi, Aritra Gupta, and Miguel Vanvlasselaer. "Anomaly induced cooling of neutron stars: a Standard Model contribution." Journal of Cosmology and Astroparticle Physics 2023, no. 10 (October 1, 2023): 030. http://dx.doi.org/10.1088/1475-7516/2023/10/030.

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Abstract Young neutron stars cool via the emission of neutrinos from their core. A precise understanding of all the different processes producing neutrinos in the hot and degenerate matter is essential for assessing the cooling rate of such stars. The main Standard Model processes contributing to this effect are ν bremsstrahlung, mURCA among others. In this paper, we investigate another Standard Model process initiated by the Wess-Zumino-Witten term, leading to the emission of neutrino pairs via Nγ → Nνν̅. We find that for proto-neutron stars, such processes with degenerate neutrons can be comparable and even dominate over the typical and well-known cooling mechanisms.
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Aitkulov, M. T., D. S. Dyussambayev, N. K. Romanova, Sh H. Gizatulin, A. A. Shaimerdenov, Zh T. Bugybay, K. S. Kisselyov, and A. O. Beisebayev. "Measurement of the spatial-energy distribution of neutrons in the irradiation channel of the critical facility." Journal of Physics: Conference Series 2155, no. 1 (January 1, 2022): 012021. http://dx.doi.org/10.1088/1742-6596/2155/1/012021.

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Abstract One of the basic installations of the Republican State Enterprise “Institute of Nuclear Physics” of the Ministry of Energy of the Republic of Kazakhstan is a critical assembly, which is a zero-power reactor. Desalinated water and beryllium serve as moderators and neutrons reflectors. The energy spectrum of neutrons in the core is thermal. The main purpose and area of application is the modeling and study of the neutronic characteristics of the cores of water-moderated research reactors of various types. The paper presents the results of experimental measurements of the spatial-energy distribution of neutrons in the dry, central channel of the critical assembly. Measurements of the neutron flux were carried out using activation foils for three energy groups of neutrons: thermal, epithermal, and fast. The measured thermal neutrons flux in the irradiation channel is ~ 3·108 cm‒2s‒1, and fast neutrons flux (with energies above 0.7 MeV) is ~ 8·108 cm‒2s‒1. The fraction of thermal neutrons in the integral flux was 0.23%, and the fraction of fast neutrons was 0.62%. In the axial distribution of thermal and fast neutrons, the maximum value of the neutron flux is 50 mm below the midplane of the core.
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7

Hargrove, C. K., and D. J. Paterson. "Solar-neutrino neutral-current detection methods in the Sudbury neutrino observatory." Canadian Journal of Physics 69, no. 11 (November 1, 1991): 1309–16. http://dx.doi.org/10.1139/p91-196.

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The Sudbury Neutrino Observatory will study the solar-neutrino problem through the detection of charged-current (CC), neutral-current (NC), and elastic-scattering (ES) interactions of solar neutrinos with heavy water. The measurement of the NC rate relative to the CC rate provides a nearly model-independent method of observing neutrino oscillations. The NC interaction breaks up the deuteron producing a neutron and a proton. The interaction rate in the original design is measured by observing Čerenkov light from showers produced by neutron-capture γ rays from the capture of the NC neutrons by a selected additive to the heavy water. These signals overlap the CC and ES signals, so that the measurement of the NC rate requires the subtraction of two signals obtained at different times. This paper describes our investigation of an alternate detection method in which the thermalized neutrons are captured by (n, α) or (n, p) reactions on light nuclei. The resulting charged-particle products are uniquely detected by scintillators or proportional counters, completely separating this NC signal from the CC and ES Čerenkov signals, thus simplifying its measurement, improving its significance, and allowing observation of otherwise unobservable short-term NC fluctuations. Although background rates for the new techniques have not yet been determined, the experimental advantages justify further development work.
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8

Mangan, M. A., C. L. Ruiz, G. W. Cooper, G. A. Chandler, and D. J. Ampleford. "Inferring neutron yields using indium activation samples for small fractions of tritium added to deuterium fuel in inertial confinement fusion (ICF) experiments." Review of Scientific Instruments 93, no. 10 (October 1, 2022): 103514. http://dx.doi.org/10.1063/5.0101823.

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In inertial confinement fusion experiments, the neutron yield is an important metric for thermonuclear fusion performance. Neutron activation diagnostics can be used to infer neutron yields. The material used for neutron activation diagnostic undergoes a threshold reaction so that only neutrons having energies above the threshold energy are observed. For thermonuclear experiments using deuterium (D) and tritium (T) fuel constituents, neutrons arising from D + D reactions (DD-neutrons) and neutrons resulting from D + T reactions (DT-neutrons) are of primary interest. Indium has two neutron activation reactions that can be used to infer yields of DD-neutrons and DT-neutrons. One threshold is high enough that only DT-neutrons can induce activation, the second reaction can be activated by both DD-neutrons and DT-neutrons. Thus, to obtain the DD-neutron yield, the contribution made by DT-neutrons to the total induced activity must be extracted. In DD-fuel experiments, DT-neutrons arise from secondary reactions, which are significantly lower in number than primary DD-neutrons, and their contribution to the inferred DD-neutron yield can be ignored. When the DD- and DT-neutron yields become comparable, such as when low tritium fractions are added to DD-fuel, the contribution of DT-neutrons must be extracted to obtain accurate yields. A general method is described for this correction to DD-neutron yields.
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9

Shinoki, Masataka. "Measurement of cosmogenic neutron production in SK-Gd." Journal of Physics: Conference Series 2156, no. 1 (December 1, 2021): 012187. http://dx.doi.org/10.1088/1742-6596/2156/1/012187.

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Abstract The Super-Kamiokande-Gd (SK-Gd) experiment has started after adding the gadolinium (Gd) into ultra-pure water in the SK detector. SK-Gd dramatically improves the sensitivity to supernova relic neutrino searches by tagging neutrons. Cosmic-ray muons penetrating into the SK detector induce hadronic showers. Such muon often break oxygen nuclei in water and produce unstable radioactive isotopes and neutrons, which are major background sources for supernova relic neutrino searches. On the other hand, the cosmogenic neutrons produced by muons can be used for the detector calibration source. Since cosmic-ray muons penetrate into the SK detector continuously with the rate of 2 event/s, the cosmogenic neutrons can be used to monitor the stability and uniformity of the Gd concentration in water. In this proceeding, we report the progress of cosmogenic neutron measurement in SK-Gd.
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10

Biekert, A., C. Chang, L. Chaplinsky, C. W. Fink, W. D. Frey, M. Garcia-Sciveres, W. Guo, et al. "A portable and monoenergetic 24 keV neutron source based on 124Sb-9Be photoneutrons and an iron filter." Journal of Instrumentation 18, no. 07 (July 1, 2023): P07018. http://dx.doi.org/10.1088/1748-0221/18/07/p07018.

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Abstract A portable monoenergetic 24 keV neutron source based on the 124Sb-9Be photoneutron reaction and an iron filter has been constructed and characterized. The coincidence of the neutron energy from SbBe and the low interaction cross-section with iron (mean free path up to 29 cm) makes pure iron specially suited to shield against gamma rays from 124Sb decays while letting through the neutrons. To increase the 124Sb activity and thus the neutron flux, a >1 GBq 124Sb source was produced by irradiating a natural Sb metal pellet with a high flux of thermal neutrons in a nuclear reactor. The design of the source shielding structure makes for easy transportation and deployment. A hydrogen gas proportional counter is used to characterize the neutrons emitted by the source and a NaI detector is used for gamma background characterization. At the exit opening of the neutron beam, the characterization determined the neutron flux in the energy range 20–25 keV to be 6.00±0.30 neutrons per cm2 per second and the total gamma flux to be 245±8 gammas per cm2 per second (numbers scaled to 1 GBq activity of the 124Sb source). A liquid scintillator detector is demonstrated to be sensitive to neutrons with incident kinetic energies from 8 to 17 keV, so it can be paired with the source as a backing detector for neutron scattering calibration experiments. This photoneutron source provides a good tool for in-situ low energy nuclear recoil calibration for dark matter experiments and coherent elastic neutrino-nucleus scattering experiments.
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Дисертації з теми "Neutrons"

1

Moore, Brian Randolph. "A neutronic study of an intense epithermal neutron source based on the ⁹BE(P,N) ⁹B reaction for neutron capture therapy." Thesis, Georgia Institute of Technology, 1992. http://hdl.handle.net/1853/16364.

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Heinrich, Aaron David. "Delayed neutrons from the neutron irradiation of ²³⁵U." Texas A&M University, 2008. http://hdl.handle.net/1969.1/85943.

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A series of experiments was performed with the Texas A&M University Nuclear Science Center Reactor (NSCR) to verify ²³⁵U delayed neutron emission rates. A custom device was created to accurately measure a sample's pneumatic flight time and the Nuclear Science Center's (NSC's) pneumatic transfer system (PTS) was redesigned to reduce a sample's pneumatic flight time from over 1,600 milliseconds to less than 450 milliseconds. Four saturation irradiations were performed at reactor powers of 100 and 200 kW for 300 seconds and one burst irradiation was performed using a $1.61 pulse producing 19.11 MW-s of energy. Experimental results agreed extremely well with those of Keepin. By comparing the first ten seconds of collected data, the first saturation irradiation deviated ~1.869% with a dead time of 2 microseconds, while the burst irradiation deviated ~0.303% with a dead time of 5 microseconds. Saturation irradiations one, three and four were normalized to the initial count rate of saturation irradiation two to determine the system reproducibility, and deviated ~0.449%, ~0.343% and ~0.389%, respectively.
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3

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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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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4

Schoen, Keary. "Neutron interferometry experiments at NIST : a study of few body forces /." free to MU campus, to others for purchase, 2004. http://wwwlib.umi.com/cr/mo/fullcit?p3137746.

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5

LIMA, RUY B. de. "Avaliacao experimental do fluxo de neutrons de um irradiador com fontes de AmBe e sua possibilidade de uso em analise de materiais." reponame:Repositório Institucional do IPEN, 2003. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11127.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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6

Criswell, Leah. "Neutron diffraction and quasielastic neutron scattering studies of films of N-alkanes and a branched alkane absorbed on graphite." Diss., Columbia, Mo. : University of Missouri-Columbia, 2007. http://hdl.handle.net/10355/6010.

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Thesis (Ph. D.)--University of Missouri-Columbia, 2007.
The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on March 11, 2008) Includes bibliographical references.
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ANGIOLETTO, ELCIO. "Medidas e calculos de espectro de neutrons emergentes de dutos em blindagens." reponame:Repositório Institucional do IPEN, 2000. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10794.

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Dissertacao [Mestrado]
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo
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8

Han, Sang-Wook. "Spin-polarized neutron reflectivity and x-ray scattering studies on thin film superconductors /." free to MU campus, to others for purchase, 1999. http://wwwlib.umi.com/cr/mo/fullcit?p9962527.

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9

McNamara, Steven. "Fusion for neutrons." Thesis, Imperial College London, 2016. http://hdl.handle.net/10044/1/44108.

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This thesis addresses the application of fusion as a powerful source of energetic neutrons. The conditions for maximising fusion power density, Pf, in a neutral beam fuelled plasma are determined and used to inform a high Pf device optimisation procedure. Restrictions on the externally applied power, not previously considered, are shown to be a crucial factor in determining the optimum plasma and reactor conditions. Two distinct regimes of operation exist, separated by a discontinuity in the optimum conditions. In one regime, beam-on-target reactions dominate and Pf is maximised when operating with a pure tritium target plasma. The optimum confinement is lower than that required for high gain operation but the energy multiplication is limited to Qf~1. Fast alpha particles, if confined, reduce Pf by a factor (1+0.2Qf)^-1, but leave Qf unchanged. In the second regime, thermonuclear reactions make a significant contribution to Pf, allowing for higher energy gain but requiring improved confinement. Alpha particle heating reduces Pf by around 20% but increases Qf. By considering established tokamak stability constraints the optimum plasma conditions are used to inform a high Pf device design. The model provides a framework for simplifying and informing what would otherwise be a perplexing search for the optimal reactor configuration and allows areas of particular interest to high Pf operation to be identified. A novel tokamak operating regime - the isothermal tokamak - is investigated. An analytic equilibrium is derived and the resulting density and current profiles found to be notably different from those of a conventional device. A model of the anomalous transport due to the trapped electron mode instability is derived. Simultaneous solutions to the MHD and transport equilibria are shown to only exist for relatively shallow density profiles.
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Conti, V. "Neutrons for medicine." Doctoral thesis, Università degli Studi di Milano, 2011. http://hdl.handle.net/2434/172333.

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There are a lot of definitions of cancer: in a few words one could say that it represents a group of diseases characterized by the growth and uncontrolled diffusion of abnormal cells. Considering the number of deaths at the world level in 2005 (50 millions), cancer is responsible of 7.6 millions (that is 13%) with an expected increase to 11.4 millions in 2030. The innovations in the field of radiotherapy, chemotherapy, surgery and their combined applications have allowed to maintain these numbers under control. Radiation therapy has been used for the treatment of cancer and other diseases for approximately 100 years. As early as 1897, two years after the discovery by Wilhelm Conrad Rontgen, it was concluded that X-rays could be used for therapeutic as well as diagnostic purposes. But nearly 30 years were necessary to make radiotherapy world wide diffused: in fact, X-rays moved into clinical therapeutic routine only in the early 1920s. Since the first uses of radiation to treat cancer, important changes have been made in this field and several developments have been accomplished, both from the instrumental (new types of linear accelerators to generate higher energy radiation beams) and medical (different types of ionizing radiation and progress in treatment planning) points of view. On the other hand there is a series of tumours whose survival curve has not varied in time both in absolute and incremental terms: extended tumours (such as the ones of stomach, liver and lung), tumours localized near or in vital organs (such as the glioblastoma multiforme (GBM) in the brain), radioresistant tumours (such as melanoma). The research for new ways of treatment, together with the discovery of neutrons in 1932 and the studies concerning their properties, inspired in the American biophysicist G. L. Locher in 1936 the attempt to use neutron beams in radiotherapy in the so-called NCT (Neutron Capture Therapy) first and BNCT (Boron Neutron Capture Therapy) then. BNCT could (and the conditional is a must) represent a hope for all the cases still lacking a survival improvement. BNCT is a technique that in principle joins the localization capability of radiotherapy and the specificity of chemotherapy, allowing a selective release of the dose only to cancer cells, without damaging the surrounding healthy tissues. This technique is based on the irradiation with thermal and epithermal neutrons of a boronated compound (the so called carrier) selectively concentrated in tumor cells. Following the capture of a neutron, the 10B isotope emits high LET particles (an and a 7Li ion) that release their whole energy in the cell where the boron atom was present at the moment of the irradiation. The first BNCT experimental treatments were performed during the '50s. Since then, BNCT has met ups and downs in its history because of a physical and a biological reason: from the physical point of view, the features of the neutron beam (a flux >5 X 108 n cm-2 s-1 with an energy <10 keV) identify nuclear reactors as the only adequate sources; from the biological point of view, the carriers that bring the 10B inside the cell are not selective but exploit the greater metabolism of the cancer cells with respect to the healthy ones. BNCT has been performed in nuclear reactors in the United States (MIT, WSU), in Japan (KURRI, JRR-4), in Argentina (RA-6), in Europe (JRC - the Netherlands, Medical AB - Sweden, FiR1 - Finland) for activities of Phase I (toxicity) and of Phase II (ef_cacy); no center has started a Phase III protocol (BNCT tests randomized with respect to the standard techniques). Possible patients for BNCT treatments have to submit the request for the therapy to the International Ethic Committee who analyzes all the other possibilities before agreeing to a non standard treatment, a fact which limits the number of patients and thus the available statistics. To understand completely the impact and the advantages of BNCT with respect to other techniques, it is necessary to study the boron concentration, its sub-cellular distribution, its fixation molecular sites, its transport and its exchange dynamics in several biological samples, possibly in a user friendly environment, easily accessible and with a low photon or particle background. In other words, one of the main tasks for the BNCT development in terms of clinical treatments is the study of the pharmacokinetics of the carrier. This requires the development of reliable methods for monitoring the boron concentration in healthy and tumour cells. This study has to proceed in parallel with the design of in-hospital radiation sources. The project of a treatment plan involves the work of medical doctors, oncologists, biology and chemistry experts, physicists; the work of such a pool of people is not easy to organize outside the hospital in a complicated environment such as the one of a nuclear reactor. Moreover, also the test of new carriers or the trials on new organs have to be inserted in the schedule of a reactor increasing times and costs. This thesis locates itself in the field of BNCT facing both the problems that still limit its becoming a standard therapy. The work has been performed both at a nuclear reactor and in a hospital environment collaborating with some of the most important groups in Italy involved with BNCT. The first chapter focuses on what cancer is, how it develops and how it can be cured summarizing the three main treatment modalities (surgery, chemotherapy and radiotherapy) and analyzing the brain cancer as an example of an illness still without hope. The last part of the chapter concerns the rationale of BNCT, whose ingredients are described in detail in chapter 2, which focuses both on the boron carrier and the neutron beam. Chapter 3 summarizes the features of a nuclear reactor neutron beam for BNCT, describing the instruments and the procedure to characterize such a beam. In particular, the chapter focuses on the measurements performed on the epithermal column of the TAPIRO reactor (ENEA, Casaccia, Italy) with thermoluminescent detectors. The data taking and analysis procedure are described in detail in order to give an idea of the pros and cons of such non real time detectors. Chapter 4 moves in the opposite direction, considering the development of a hospital based BNCT beam both from the industrial point of view (presenting as an example the proton + Li target accelerator proposed by IBA) and the completely different approach of the PhoNeS (ProtoNeutron Source) project, which exploits a standard radiotherapy linac producing neutrons via the Giant Dipole Resonance. The chapter describes in detail the PhoNeS prototype and the measurements to characterize the beam, presenting real time and innovative systems that can be used thanks to the pulsed nature of the linac beam which allows to work in a background free environment. The last part of the chapter is dedicated to the application of this beam to the study of the boron concentration in biological samples (urine and blood) to obtain the kinetic curves (that is the boron concentration as a function of the time from the administration) for patients undergoing BNCT treatments. This same .imaging system. has been applied to the study of another possible organ that could bene_t of BNCT, that is the lung.
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Книги з теми "Neutrons"

1

Sevastʹi︠a︡nov, V. D. Kharakteristiki poleĭ neĭtronov: Istochniki mgnovennykh neĭtronov delenii︠a︡, generatory 14 MėV neĭtronov, issledovatelʹskie i ėnergeticheskie reaktory, ustroĭstva, konvertirui︠u︡shchie neĭtronnoe izluchenie : spravochnik. Mendeleevo: VNIIFTRI, 2007.

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2

B, Pal P., ed. Massive neutrinos in physics and astrophysics. Singapore: World Scientific, 1991.

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3

B, Pal P., ed. Massive neutrinos in physics and astrophysics. 3rd ed. River Edge, N.J: World Scientific, 2004.

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4

Williams, W. Gavin. Polarized neutrons. Oxford [England]: Clarendon Press, 1988.

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5

International Collaboration on Advanced Neutron Sources. Meeting. Advanced neutron sources, 1988: Proceedings of the 10th Meeting of the International Collaboration on Advanced Neutron Sources (ICANS X) held at Los Alamos, 3-7 October 1988. Bristol, England: Institute of Physics, 1989.

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6

F, Mezei, Pappas C. 1955-, and Gutberlet T. 1958-, eds. Neutron spin echo spectroscopy: Basics, trends, and applications. Berlin: Springer, 2003.

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7

Csikai, Julius. A gyors-neutron-adatok és a fúziós reaktorok: Akadémiai székfoglaló, 1986. január 29. Budapest: Akadémiai Kiadó, 1987.

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8

Kirʹi͡anov, G. I. Generatory bystrykh neĭtronov. Moskva: Ėnergoatomizdat, 1990.

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9

Sears, Varley F. Neutron optics: An introduction to the theory of neutron optical phenomena and theit applications. Oxford: Oxford University Press, 1989.

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10

M, Raby T., NIST Center for Neutron Research, and Materials Science and Engineering Laboratory (U.S.), eds. NIST Center for Neutron Research: Technical activities 1997. [Gaithersburg, MD]: U.S. Dept. of Commerce, Technology Administration, National Institute of Standards and Technology, 1997.

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Частини книг з теми "Neutrons"

1

Pyeon, Cheol Ho. "Introduction." In Accelerator-Driven System at Kyoto University Critical Assembly, 1–12. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_1.

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AbstractAt the Kyoto University Critical Assembly (KUCA), the accelerator-driven system (ADS) is composed of a solid-moderated and solid-reflected core (A-core) and a pulsed-neutron generator (14 MeV neutrons) or the fixed-filed alternating gradient (FFAG) accelerator (100 MeV protons). At KUCA, two external neutron sources, including 14 MeV neutrons and 100 MeV protons, are separately injected into the A-core, and employed for carrying out the ADS experiments. With the combined use of the A-core and two external neutron sources, basic and feasibility studies of ADS have been engaged in the examination of neutronics of ADS, through the measurements of statics and kinetics parameters of reactor physics, including subcritical multiplication factor, subcriticality, prompt neutron decay constant, effective delayed neutron fraction, neutron spectrum, and reaction rates.
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2

Swinhoe, M. T., and N. Ensslin. "The Origin of Neutron Radiation." In Nondestructive Assay of Nuclear Materials for Safeguards and Security, 289–306. Cham: Springer International Publishing, 2024. http://dx.doi.org/10.1007/978-3-031-58277-6_13.

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AbstractThis chapter presents the various sources of neutrons that are important in nondestructive measurements. These sources include the key mechanisms of spontaneous fission, neutrons from alpha particle reactions on light elements, and induced fission. The characteristics of neutrons resulting from typical sources are presented. A brief discussion of other neutrons sources, such as those from less common nuclear reactions, cosmic rays, and neutron generators, is included.
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3

Pyeon, Cheol Ho. "Neutron Spectrum." In Accelerator-Driven System at Kyoto University Critical Assembly, 125–56. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_5.

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AbstractThe subcritical multiplication factor is considered an important index for recognizing, in the core, the number of fission neutrons induced by an external neutron source. In this study, the influences of different external neutron sources on core characteristics are carefully monitored. Here, the high-energy neutrons generated by the neutron yield at the location of the target are attained by the injection of 100 MeV protons onto these targets. In actual ADS cores, liquid Pb–Bi has been selected as a material for the target that generates spallation neutrons and for the coolant in fast neutron spectrum cores. The neutron spectrum information is acquired by the foil activation method in the 235U-fueled and Pb–Bi-zoned fuel region of the core, modeling the Pb–Bi coolant core locally around the central region. The neutron spectrum is considered an important parameter for recognizing information on neutron energy at the target. Also, the neutron spectrum evaluated by reliable methodologies could contribute to the accurate prediction of reactor physics parameters in the core through numerical simulations of desired precision. In the present chapter, experimental analyses of high-energy neutrons over 20 MeV are conducted after adequate preparation of experimental settings.
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4

Swinhoe, M. T., J. D. Hutchinson, and P. M. Rinard. "Neutron Interactions with Matter." In Nondestructive Assay of Nuclear Materials for Safeguards and Security, 307–23. Cham: Springer International Publishing, 2024. http://dx.doi.org/10.1007/978-3-031-58277-6_14.

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AbstractThis chapter describes the interactions that neutrons have with matter. There is a description of microscopic interactions, such as fission, scattering and absorption, using the concept of cross-section. The idea of individual neutron interactions is extended to the macroscopic behavior of neutrons, giving rise to the calculation of reaction rates and mean free paths. The important quantities of moderation and neutron multiplication are introduced. There is a brief discussion of neutron shielding and transport calculational techniques.
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5

Ramirez-Cuesta, A. J., and Philip C. H. Mitchell. "Neutrons and Neutron Spectroscopy." In Local Structural Characterisation, 173–224. Chichester, UK: John Wiley & Sons, Ltd, 2013. http://dx.doi.org/10.1002/9781118681909.ch3.

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6

Raven, Will. "Isotope Shifts, Radioactive Decay, and the Nuclear Forces." In Atomic Physics for Everyone, 197–223. Cham: Springer Nature Switzerland, 2024. http://dx.doi.org/10.1007/978-3-031-69507-0_10.

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AbstractIn this chapter, we explore the nucleus, focusing on how the number of neutrons in a nucleus influences transition frequencies and the stability of atoms. We begin by examining the effect of neutrons on transition frequencies, then shift into detailed discussions of the nuclear forces and principles governing atomic stability and radioactive decay. Various modes of radioactive decay, including neutron and proton emission, $$\alpha $$ α decay, spontaneous fission, $$\beta ^-$$ β − decay, $$\beta ^+$$ β + decay, and electron capture, are investigated, with an emphasis on the conditions under which each occurs. Additionally, we explore the nuclear shell model to understand the energetics behind different types of decays and the stability of isotopes.
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7

Ignatovich, V. K. "Enigmatic Neutrons." In The Present Status of the Quantum Theory of Light, 293–303. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5682-0_29.

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8

Gooch, Jan W. "Thermal Neutrons." In Encyclopedic Dictionary of Polymers, 742. New York, NY: Springer New York, 2011. http://dx.doi.org/10.1007/978-1-4419-6247-8_11758.

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9

Pyeon, Cheol Ho. "Reactor Kinetics." In Accelerator-Driven System at Kyoto University Critical Assembly, 51–81. Singapore: 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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10

Kornilov, Nikolay. "Introduction." In Fission Neutrons, 1–5. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-07133-6_1.

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Тези доповідей конференцій з теми "Neutrons"

1

Khan, Nafisah, Rachid Machrafi, and Vitali Kovaltchouk. "Response Functions of a Cs2LiYCl6 Scintillator to Neutron and Gamma Radiation." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15249.

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A new scintillator, CLYC, has been investigated for possible use in neutron spectrometry. This sensor provides neutron detection for both thermal and fast neutrons from the reactions 6Li(n,α) and 35Cl(n,p), respectively. This work primarily focuses on the detection of fast neutrons since there is currently no sensor that can accurately and efficiently provide information about their incident neutron energy. Conventional methods of fast neutron detection have been based on utilizing materials that use the elastic scattering process of neutrons on 1H to create recoil protons or by thermalizing and capturing these neutrons at thermal energies. Both approaches have drawbacks and are complex in deriving the energy spectrum through the unfolding process. The CLYC scintillator uses a distinct proton peak, whereby the position on the spectrum is proportional to the energy of the incident neutron. The response function of this detector has been simulated using Monte Carlo N-Particle eXtended code (MCNPX) for gamma-rays and neutrons of different energies. The obtained data has been discussed and analyzed.
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2

Wang, Dong, Bin He, and Quanhu Zhang. "Neutron-Gamma Discrimination Using Zero-Crossing Method for BC454 Boron Loaded Plastic Scintillator." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29223.

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Boron loaded plastic scintillator could detect both fast neutrons (thanks to hydrogen) and slow neutrons (thanks to 10B). The large cross sections of both reactions lead to high detection efficiency of incident neutrons. However, gamma rays must be rejected first as the scintillator is also sensitive to them. In the present research zero crossing method was used to test neutron-gamma discrimination performance of BC454 boron loaded plastic scintillator. Three contrast experiments were carried out and different thermalization degrees lead to different time spectra in the MCA. Further analysis proved that three Gaussian curves could be used to fit the spectra; they corresponded to gamma rays, fast neutrons and slow neutrons respectively. The slow neutron curve could be clearly separated from the gamma curve. Discrimination performance for fast neutrons became poor, but their peaks could also be separated.
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3

VANHOEFER, Laura. "Neutron Shielding Simulations and Muon-induced Neutrons." In XVI International Workshop on Neutrino Telescopes. Trieste, Italy: Sissa Medialab, 2016. http://dx.doi.org/10.22323/1.244.0085.

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4

Baleanu, Dumitru, and Abdelouahab Kadem. "About the FN Approximation to Fractional Neutron Transport Equation in Slab Geometry." In ASME 2011 International Design Engineering Technical Conferences and Computers and Information in Engineering Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/detc2011-47731.

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The neutron transport denotes the study of the motions and interactions of neutrons with materials. In given applications we need to know where neutrons are in an apparatus, what direction they are moving, and how fast they are going. In this manuscript the Legendre polynomial approximation method FN was applied to the one dimensional slab geometry neutron transport equation.
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5

Wang, Peng, and Suizheng Qiu. "Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75868.

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The new concept Molten Salt Reactor is the only liquid-fuel reactor of the six Generation IV advanced nuclear energy systems. The liquid molten salt serves as the fuel and coolant simultaneously and causes one important feature: the delayed neutrons precursors are drifted by the fuel flow, which leads the spread of delayed neutrons distribution to non-core parts of the primary circuit, and it also can result in a reactivity variation depending on the flow condition of the fuel salt. Therefore, the neutronic and thermal-hydraulic characteristics of the Molten Salt Reactor is quite different from the conventional nuclear reactors using solid fissile materials, and no other reactor design theory and safety analysis methodologies can be used for reference. The neutronic model is derived based on the conservation of particle considering the flow effect of the fuel salt in the Molten Salt Reactor, while the thermal-hydraulic model uses the fundamental conservation laws: the mass, momentum and energy conservation equations. Then the neutronic and thermal-hydraulic calculations were coupled and the influences of inflow temperature and flow velocity on the reactor physical properties were obtained. The calculated results show that the flow effect on the distributions of thermal and fast neutron fluxes is very weak, as well as on the effective multiplication factor keff. While the flow effect on the distribution of delayed neutron precursors is much stronger. The inflow temperature influences the distribution of neutron flux and delayed neutron precursors slightly, and makes significant negative reactivity. Coupled calculation also reveals that the flow velocity of molten salt has little effect on the distribution of neutron fluxes in the steady state, but affects the delayed neutron precursors’ distribution significantly.
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6

Hillebrandt, Wolfgang. "Neutrons, neutrinos, and the physics of supernovas." In 4th International Conference on Applications of Nuclear Techniques: Neutrons and their Applications, edited by George Vourvopoulos and Themis Paradellis. SPIE, 1995. http://dx.doi.org/10.1117/12.204141.

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7

Sykes, A., M. P. Gryaznevich, G. Voss, D. Kingham, and B. Kuteev. "Fusion for neutrons: A realisable fusion neutron source." In 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052205.

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8

Finlay, Roger W. "Neutron scattering above 25 MeV with monoenergetic neutrons." In AIP Conference Proceedings Volume 124. AIP, 1985. http://dx.doi.org/10.1063/1.34996.

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9

Young, Christian, Michael Liesenfelt, Chloe Browning, Ryan Thurber, Jason Hayward, and Jeff Preston. "Proton Recoil Event Localization for Fast Neutron Radiography." In ASNT Research Symposium 2023. The American Society for Nondestructive Testing Inc., 2023. http://dx.doi.org/10.32548/rs.2023.077.

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Neutron radiography is an important tool for the imaging of dense, metallic objects for a wide range of applications. Many systems currently in operation either require large-scale user facilities to produce neutrons [1, 2] or low-efficiency thin-film converters to detect neutrons [3]. These drawbacks lead to neutron radiography seeing limited use in the field. To compensate for these drawbacks, a system has been developed using a scatter-based plastic scintillator, a scalable readout module, and a D-T neutron generator. This system has been developed for use as a field-deployable neutron radiography system.
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10

Miley, George H., Hiromu Momota, Hugo Leon, Ben Ulmen, Guilherme Amadio, Atanu Khan, George Chen, William Matisiak, Ali Azeem, and Paul Keutelian. "Cylindrical IEC Fusion Neutron Source for Broad Area NAA." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30368.

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The development of a unique long cylindrical neutron source for broad area neutron activation analysis (NAA) is presented. This source uses inertial electrostatic confinement (IEC) to produce 2.54 MeV D-D or 14.1 MeV D-T fusion neutrons for applications ranging from security inspection stations to driven-subcritical research assemblies. This design uses a biased grid to initial in a unique “star” mode plasma discharge forming beam-background gas (target) fusion. In spherical geometry it routinely produces ∼108 2.54-MeV D-D fusion neutrons/s at steady-state. Pulsed operation has achieved up to 109 neutrons/sec. (equivalent to 1011 n/s using D-T fill). Indeed, a version of the spherical IEC has been produced commercially as a portable neutron source for industrial NAA applications. Recently a cylindrical (2-dimensional version) design based on the spherical unit has been developed. This provides a unique long “line-like” neutron source for use in broad area NAA. This IEC forms ion beams in the volume between the grounded wall and the concentric cylindrical grid. Those beams converge in the center, much like in the star mode spherical IEC. To date, neutron yields of up to 108 D-D neutrons/sec have been achieved with the cylindrical device. A sealed-off unit using getters for gas storage-control has been developed to simplify use in practical applications such as a luggage inspection station. Such units would be filled with deuterium at a central fueling facility, and sent out to the field. After extended operation, they would be returned to this facility for refilling.
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Звіти організацій з теми "Neutrons"

1

Haight, Robert C. Scission Neutrons in Spontaneous and Neutron-Induced Fission: Effect on Prompt Fission Neutron Spectra. IAEA Nuclear Data Section, February 2020. http://dx.doi.org/10.61092/iaea.6fxg-n58v.

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This consultant was asked to look into the possibility of so-called “scission neutrons”, that is neutrons emitted in the fission process before full acceleration of the two large fragments. Results of new measurements that measure neutron emission relative to the direction of the fragments are available, and the quantification of scission neutron has been derived from these data. More detailed models of the fission process are also new. It is however the conclusion of this consultant that the existence of scission neutrons has not been proven from experimental data. Further, the possibility of some pre-equilibrium process producing high energy neutrons in spontaneous fission or in fission induced by low energy neutrons is also not confirmed. Recommendations are made, with a principal one being that detailed modelling of neutron scattering in the analysis of experimental data is of utmost importance. The data base that pertains to scission neutrons and pre-equilibrium neutrons from the fission process is limited, although the recent experimental data could be mined for more information .
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2

Vorobyev, A. S., and O. A. Shcherbakov. Scission Neutrons from Thermal Neutron induced Fission of 239-Pu and Spontaneous Fission of 252-Cf. IAEA Nuclear Data Section, February 2020. http://dx.doi.org/10.61092/iaea.8t4w-essq.

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Анотація:
The properties of “scission” neutrons from thermal-neutron induced fission of 239Pu(nth,f) and spontaneous fission of 252Cf(sf) were obtained by comparing experimental angular and energy distributions of the prompt fission neutrons measured recently at PNPI with model distributions calculated under the assumption that all prompt fission neutrons are emitted from fully accelerated fragments.
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3

Egorov, A. S., V. M. Piksaikin, D. E. Gremyachkin, K. V. Mitrofanov, and V. F. Mitrofanov. 8-Group Model Energy Spectra of Delayed Neutrons from Thermal Fission of 235U. IAEA Nuclear Data Section, May 2022. http://dx.doi.org/10.61092/iaea.h7h2-d6g0.

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Анотація:
The energy spectra of delayed neutrons from neutron-induced fission of 235U are estimated in the 8-group model using the Kalman filtering method. The spectra are available for viewing and downloading on the IAEA Reference database for beta-delayed neutrons.
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4

Vorobyev, A. S., and O. A. Shcherbakov. Experimental Investigation of the Properties of Scission Neutrons In Thermal-Neutron Induced Fission of 233U and 235U. IAEA Nuclear Data Section, February 2020. http://dx.doi.org/10.61092/iaea.7zgq-zwwx.

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The properties of “scission” neutrons from thermal neutron induced fission of 233U and 235U were obtained by comparing experimental angular and energy distributions of the prompt fission neutrons measured recently at PNPI with model distributions calculated under the assumption that all prompt fission neutrons are emitted from fully accelerated fragments. To obtain model distributions, it is assumed to use the spectra of prompt fission neutrons measured at small angles relative to the preferential direction of movement of light and heavy fragments because it is expected that just for these angles the contribution of non-primary mechanism is minimal while a contribution of neutrons emitted by complementary fragment can be taken into account correctly. It is also very important that in this approach it is possible to obtain the model distributions practically unlimited in low-energy range.
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5

Smith, A. B., and A. Fessler. Neutrons and antimony neutronic evaluations. Office of Scientific and Technical Information (OSTI), May 2000. http://dx.doi.org/10.2172/761284.

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6

Goeler, S. von, A. L. Roquemore, L. C. Johnson, M. Bitter, M. Diesso, E. Fredrickson, D. Long, and J. Strachan. Fast detection of 14 MeV neutrons on the TFTR neutron collimator. Office of Scientific and Technical Information (OSTI), December 1995. http://dx.doi.org/10.2172/206578.

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7

Courant, Ernest D. Polarized Neutrons in RHIC. Office of Scientific and Technical Information (OSTI), May 1998. http://dx.doi.org/10.2172/1119396.

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8

Broussard, Leah J. Ultracold Neutrons at LANSCE. Office of Scientific and Technical Information (OSTI), April 2014. http://dx.doi.org/10.2172/1130510.

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9

Plaster, Bradley. Neutrons and Fundamental Symmetries. Office of Scientific and Technical Information (OSTI), January 2016. http://dx.doi.org/10.2172/1235013.

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10

Srdoc, D., and S. A. Marino. Microdosimetry of monoenergetic neutrons. Office of Scientific and Technical Information (OSTI), December 1993. http://dx.doi.org/10.2172/10129437.

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