Relevant bibliographies by topics / Neutron activation method

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Neutron activation method'

Author: Grafiati
Published: 5 June 2025
Last updated: 15 July 2025

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Journal articles on the topic "Neutron activation method"

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Namakonov, V., S. Andreyev, D. Gabbasov, A. Moseyeva, and D. Sergina. "MEASUREMENT OF 14 MEV NEUTRONS TRANSMISSION THROUGH LITHIUM HYDRIDE LAYERS WITH TIME-OF-FLIGHT METHOD." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2020, no. 4 (2020): 33–39. http://dx.doi.org/10.55176/2414-1038-2020-4-33-39.

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The results of experiments on transmission of 14 MeV neutrons through lithium hydride layers of thickness up to 25 cm are presented in the article. The measurements were performed with time-of-flight method on a pulse channel of neutron generator NG-12I. The operating mode of the neutron generator is pulse-periodic. Neutrons passing through the layers of Li hydrides were registered by detector based on a 70×70 mm stilbene crystal scintillator. NIM standard modules were used as measuring equipment. The neutron yield from the generator target was estimated by neutron monitor with a fluorine plas
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UEMINO, YOSHITOMO. "Neutron Spectrometry with Activation Method." RADIOISOTOPES 46, no. 9 (1997): 699–701. http://dx.doi.org/10.3769/radioisotopes.46.699.

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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 (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 acti
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Reyhancan, Iskender Atilla. "Measurements of activation cross sections by cyclic activation method for (n,2n) reaction on 144Sm isotope around 14 MeV neutron energy." Radiochimica Acta 107, no. 1 (2018): 33–37. http://dx.doi.org/10.1515/ract-2018-2983.

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Abstract Measurement of activation cross sections for the 144Sm(n,2n)143gSm reaction was performed by Cyclic Activation Method (CAM) around 14 MeV neutron energy. Natural samarium samples were irradiated by the neutrons produced by 3H(2H,n)4He reaction using a neutron generator. Delayed γ ray activities produced by fast neutrons in samples were measured by a high resolution γ ray spectrometer [high-purity Germanium (HpGe) detector]. The measured cross sections are compared with the results of model calculation (STAPRE code) and evaluated data (JEFF 3.0/A).
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Ivannikov, Sergei, Nikita Markin, and Veniamin Zheleznov. "Determination of uranium in solutions by the neutron activation analysis method with 252Cf radionuclide neutron source." Nuclear Technology and Radiation Protection 36, no. 1 (2021): 12–17. http://dx.doi.org/10.2298/ntrp201217005i.

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A determination option for 238U in solutions by the neutron activation analysis was investigated. A radionuclide treatment based on 252Cf was used as a neutron source. The limit for the determination of uranium using thermal neutrons of 0.1 mgL?1 was determined within the research framework. With the help of the preliminary concentration of the sample via the evaporation method, it is possible to further reduce the detection limit by 2-5 times. It is defined that the optimal time for measuring the induced activity of the sample when working with a short-life isotope of 239U, is 30 minutes. The
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Begun, S. V., N. R. Dzysiuk, I. M. Kadenko, V. K. Maidanyuk, and G. I. Primenko. "Cross sections of (n, p) nuclear reactions on zirconium isotopes." Nuclear Physics and Atomic Energy 8, no. 3 (2007): 42–46. https://doi.org/10.15407/jnpae2007.03.042.

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Cross sections of nuclear reactions 92Zr(n, p)92Y and 94Zr(n, p)94Y were measured in the neutron energy range 13.56 ÷ 14.53 MeV. Measurements have been carried out by neutron activation method. The samples in the form of foils of natural zirconium have been irradiated by DT- neutrons. Instrumental gamma-spectra of activation products have been measured by spectrometer with HPGe detector. The corrections on the instability of neutron flux, real geometry of the experiment, the effect of true coincidence summing of gamma-quanta during activation products spectra measurements and on effect of abso
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Salama, Tarek Mohamed Talaat, N. A. Mansour, and M. Fayez-Hassan. "Neutron Activation Analysis of Some Building Material." JOURNAL OF ADVANCES IN PHYSICS 14, no. 2 (2018): 5564–73. http://dx.doi.org/10.24297/jap.v14i2.7507.

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Neutron activation analysis (NAA), based on the comparator method, has the potential to fulfill the requirements of a primary ratio method as defined in 1998 by the Comité Consultatif pour la Quantité de Matière — Métrologie en Chimie (CCQM, Consultative Committee on Amount of Substance — Metrology in Chemistry Studies of Neutron Activation Analysis (NAA) have been carried out on different Egyptian building material samples. The technique of neutron activation analysis is based on the measurement of radiation released by the decay of radioactive nuclei formed by neutron irradiation of the mate
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Laszynska, Ewa, Slawomir Jednorog, Adam Ziolkowski, Michal Gierlik, and Jacek Rzadkiewicz. "Determination of the emission rate for the 14 MeV neutron generator with the use of radio-yttrium." Nukleonika 60, no. 2 (2015): 319–22. http://dx.doi.org/10.1515/nuka-2015-0040.

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Abstract The neutron emission rate is a crucial parameter for most of the radiation sources that emit neutrons. In the case of large fusion devices the determination of this parameter is necessary for a proper assessment of the power release and the prediction for the neutron budget. The 14 MeV neutron generator will be used for calibration of neutron diagnostics at JET and ITER facilities. The stability of the neutron generator working parameters like emission and angular homogeneity affects the accuracy of calibration other neutron diagnostics. The aim of our experiment was to confirm the us
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Kilim, S., E. Strugalska-Gola, M. Szuta, et al. "Am-241 incineration measurements with activation method in the QUINTA neutron field." EPJ Web of Conferences 204 (2019): 04004. http://dx.doi.org/10.1051/epjconf/201920404004.

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Am-241 sample was irradiated in spallation neutrons produced in ADS setup QUINTA at the JINR in Dubna. The energy was 660 MeV in the proton beam. The incineration study method was based on gamma-ray spectrometry. During the analysis of the spectra, several fission products were identified. Fission product activities yielded the number of fissions. Nevertheless, the lines are assumed to belong to the neutron capture product covered by parasitic Np-238 decay lines. The Np-238 lines as a result of neutron capture by Np-237 made impossible to determine the number of captures in Am-241.
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Dzysiuk, N. R., I. M. Kadenko, V. K. Maydanyuk, G. I. Primenko, and A. M. Berlizov. "Determination of cross sections for nuclear reactions (n, x) at germanium isotopes." Nuclear Physics and Atomic Energy 8, no. 4 (2007): 68–71. https://doi.org/10.15407/jnpae2007.04.068.

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The cross section values for nuclear reactions 74Ge(n, α)71mZn, 70Ge(n, p)70Ga, 76Ge(n,2n)75mGe, 70Ge(n,2n)69Ge have been measured for neutron energy 14.53 MeV, and of reaction 72Ge(n, 2n)71Ge for energies 13.32, 13.69, 14.35, 14.74 MeV as well. Measurements have been carried out with neutron activation method. The samples in the form of disks of natural germanium have been irradiated with DT-neutrons. Instrumental gamma-spectra of activation products have been measured with two HPGe spectrometers. The corrections for neutron flux instability, real geometry of the experiment, the effect of gam
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Dissertations / Theses on the topic "Neutron activation method"

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Negoita, Cezar Ciprian. "Measurement of neutron flux spectra in a Tungsten Benchmark by neutron foil activation method." Doctoral thesis, Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2004. http://nbn-resolving.de/urn:nbn:de:swb:14-1096547324156-18744.

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The nuclear design of fusion devices such as ITER (International Thermonuclear Experimental Reactor), which is an experimental fusion reactor based on the "tokamak" concept, rely on the results of neutron physical calculations. These depend on the knowledge of the neutron and photon flux spectra which is particularly important because it permits to anticipate the possible answers of the whole structure to phenomena such as nuclear heating, tritium breeding, atomic displacements, radiation shielding, power generation and material activation. The flux spectra can be calculated
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Negoita, Cezar C. [Verfasser]. "Measurement of Neutron Flux Spectra in a Tungsten Benchmark by Neutron Foil Activation Method / Cezar C Negoita." Aachen : Shaker, 2004. http://d-nb.info/1186575115/34.

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Thompson, Diana. "A neutron activation method to determine contaminants in plastic packaging used for food." Thesis, Imperial College London, 1998. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.299431.

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Wang, Zhonglu. "Design of a Boron Neutron Capture Enhanced Fast Neutron Therapy Assembly." Diss., Georgia Institute of Technology, 2006. http://hdl.handle.net/1853/14100.

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A boron neutron capture enhanced fast neutron therapy assembly has been designed for the Fermilab Neutron Therapy Facility (NTF). This assembly uses a tungsten filter and collimator near the patient¡¯s head, with a graphite reflector surrounding the head to significantly increase the dose due to boron neutron capture reactions. The assembly was designed using Monte Carlo radiation transport code MCNP version 5 for a standard 20x20 cm2 treatment beam. The calculated boron dose enhancement at 5.7-cm depth in a water-filled head phantom in the assembly with a 5x5 cm2 collimation was 21.9% per 100
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Jang, Si Young. "Advanced neutron irradiation system using Texas A&M University Nuclear Science Center Reactor." Texas A&M University, 2004. http://hdl.handle.net/1969.1/2788.

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A heavily filtered fast neutron irradiation system (FNIS) was developed for a variety of applications, including the study of long-term health effects of fast neutrons by evaluating the biological mechanisms of damage in cultured cells and living animals such as rats or mice. This irradiation system includes an exposure cave made with a lead-bismuth alloy, a cave positioning system, a gamma and neutron monitoring system, a sample transfer system, and interchangeable filters. This system was installed in the irradiation cell of the Texas A&M University Nuclear Science Center Reactor (NSCR).
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Asif, Mohammad. "An improved and modified fire assay method for platinum group elements and gold using neutron activation analysis." Thesis, Imperial College London, 1990. http://hdl.handle.net/10044/1/47756.

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CARDOSO, VANDERLEI. "Estudo das covariâncias envolvidas no método ko de análise por ativação neutrônica." reponame:Repositório Institucional do IPEN, 2011. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10074.

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Made available in DSpace on 2014-10-09T12:34:27Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:09:41Z (GMT). No. of bitstreams: 0<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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NUNES, BEATRIZ G. "Determinação exerimental de razões espectrais e do espectro de energia dos nêutrons no combustível do reator nuclear IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10069.

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Made available in DSpace on 2014-10-09T12:34:24Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:09:44Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Evans, Robert James. "The development of a CsI(TI)-photodiode array for remote geochemical sensing." Thesis, University of Southampton, 1999. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.299369.

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Lima, Nicole Pereira de. "Validação do método de análise por ativação com nêutrons para determinação de urânio em amostras ambientais." Universidade de São Paulo, 2018. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-23112018-140537/.

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O urânio (U) é considerado um elemento poluente do ambiente devido à sua toxicidade química e radiológica, com propriedades cumulativas em seres humanos, podendo causar diversos tipos de doenças no organismo. Consequentemente, há um grande interesse na determinação de U em amostras ambientais devido às ações antrópicas como as emissões desse elemento na mineração, nas indústrias e em acidentes nucleares que ocasionam alterações dos seus teores no meio ambiente. Dentre as diversas metodologias analíticas para a determinação de U em amostras ambientais, destaca-se a análise por ativação com nêut
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Books on the topic "Neutron activation method"

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G, Cassapakis Costa, and United States. Defense Nuclear Agency., eds. Neutron field measurements in phantom with foil activation methods. Defense Nuclear Agency, 1986.

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National Council on Radiation Protection and Measurements., ed. Pulsed fast neutron analysis system used in security surveillance. National Council on Radiation Protection and Measurements, 2003.

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Ryabov, Vladimir. Oil and Gas Chemistry. INFRA-M Academic Publishing LLC., 2021. http://dx.doi.org/10.12737/1017513.

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The textbook provides up-to-date data on the composition and properties of hydrocarbons and other oil and gas compounds, on the physical and chemical methods and methods for separating and identifying oil components (molecular spectroscopy, mass spectrometry, NMR spectroscopy, electron paramagnetic resonance, atomic adsorption spectroscopy, neutron activation analysis). The chemistry and mechanism of thermal and catalytic transformations of oil components in the main processes of oil raw materials processing, as well as the problems of the origin of oil and the transformation of oil in the env
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Neutron Activation Analysis: Physical Methods in Chemistry and Nano Science. Independently Published, 2019.

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YUNUS, Saheed O., Kayode J. OYEWUMI, and Mutiu K. AMOSA. Analytical Methods Using Instrumental Neutron Activation Analysis: Determining the Radionuclides, Concentrations and Differential Factors of Biological Samples. VDM Verlag Dr. Müller, 2010.

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Book chapters on the topic "Neutron activation method"

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Pyeon, Cheol Ho. "Neutron Spectrum." In Accelerator-Driven System at Kyoto University Critical Assembly. 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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Malainey, Mary E. "Instrumental Neutron Activation Analysis (INAA or NAA)." In Manuals in Archaeological Method, Theory and Technique. Springer New York, 2010. http://dx.doi.org/10.1007/978-1-4419-5704-7_32.

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Pyeon, Cheol Ho, Go Chiba, Tomohiro Endo, and Kenichi Watanabe. "Measurements of Reaction Rates." In Reactor Laboratory Experiments at Kyoto University Critical Assembly. Springer Nature Singapore, 2024. http://dx.doi.org/10.1007/978-981-97-8070-9_5.

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AbstractNeutron flux plays a significant role in the theory of reactor physics, while neutron flux is indirectly measured through the interaction between the neutron and the material used as the neutron detector in experiments. The physical quantity that is measured throughout the experiment is the “reaction rate.” To obtain the neutron flux from the measured reaction rate, various information involving cross sections of the material used as the detector is necessary, in addition to experimental devices. At the same time, it is necessary to consider the theory of reactor physics related to the specific reactions between neutrons and materials in the irradiation field. This chapter introduces methodologies for measuring the reaction rate by the activation foil method before determining the neutron flux.
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Wen, Xingjian, Zian Zhai, Songqian Tang, Chao Tian, and Zhouyu Liu. "Development and Verification of a New Depletion, Activation and Radiation Source Term Calculation Code." In Springer Proceedings in Physics. Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-99-1023-6_46.

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AbstractExisting depletion and source term calculation codes lack flexible interfaces, which is difficult to meet the actual engineering design needs. Based on the Chebyshev rational approximation method, a new depletion, activation and source term calculation code TIST is developed and verified. Full-fidelity depletion library based on ENDF-VII.0 and EAF2010 contains 3837 isotopes is generated. Flexible interfaces are built-in to support cross sections from different sources for depletion and activation calculations. The EAF2010 library and the cross sections from the high-fidelity code NECP-X are adopted by TIST for the verification in this work. Based on the nuclide inventory of the depletion and activation calculation, the radiation source term calculation capability of TIST is developed, including the radioactivity, the decay heat, the neutron source and the photon source. The comparison results with NECP-X and FISPACT demonstrate good accuracy of TIST.
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Carmo Freitas, M. "Instrumental Neutron Activation Analysis of Geological and Biological Reference Materials Using the ko-Standardization Method." In Nuclear Analytical Methods in the Life Sciences. Humana Press, 1990. http://dx.doi.org/10.1007/978-1-4612-0473-2_21.

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Hancock, Ron. "Neutron Activation Analysis." In Encyclopedia of Scientific Dating Methods. Springer Netherlands, 2015. http://dx.doi.org/10.1007/978-94-007-6304-3_234.

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Hancock, Ron. "Neutron Activation Analysis." In Encyclopedia of Scientific Dating Methods. Springer Netherlands, 2013. http://dx.doi.org/10.1007/978-94-007-6326-5_234-2.

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Wright, John R., Wayne A. Hendrickson, Shigemasa Osaki, and Gordon T. James. "Neutron Activation Analysis." In Physical Methods for Inorganic Biochemistry. Springer US, 1986. http://dx.doi.org/10.1007/978-1-4684-4997-6_12.

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Balla, M., G. KeÖmley, and Zs Molnár. "Neutron Activation Analysis." In Nuclear Methods in Mineralogy and Geology. Springer US, 1998. http://dx.doi.org/10.1007/978-1-4615-5363-2_2.

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Denker, A., N. Kardjilov, and B. Schröder-Smeibidl. "Neutron Activation Autoradiography." In Neutron Methods for Archaeology and Cultural Heritage. Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-33163-8_15.

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Conference papers on the topic "Neutron activation method"

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Rajabi Moghadam, Sahar, Fereydoon Abbasi Davani, and Babak Shirani Bidabadi. "Calibration of Activation Counter by a 2.48 kJ Plasma Focus Device." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30323.

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A silver activation counter has been constructed by plastic scintillator plates along with silver foils for determination the neutron yield of a 2.48kJ plasma focus device, SBUPF1. This counter was calibrated by source removal method with an Am-Be 5 Ci neutron source which was placed above the anode of plasma focus device. Deuterium gas up to 8mbar pressure was injected to this device, and the neutron yield produced by pulsed D-D fusion of plasma focus device was measured by the counter. the neutron yield of SBUPF1 in 8mbar pressure was obtained 3.71±0.32×107 neutrons per shot. This result has
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Sudac, D., S. Majetic, R. Kollar, K. Nad, J. Obhodas, and V. Valkovic. "Inspecting the minefield and residual explosives by fast neutron activation method." In 2011 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA). IEEE, 2011. http://dx.doi.org/10.1109/animma.2011.6172940.

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PYEON, CHEOL HO, HIROSHI SHIGA, KAZUAKI ABE, et al. "NEUTRON SPECTRUM ANALYSES BY FOIL ACTIVATION METHOD FOR HIGH-ENERGY PROTON BEAMS." In Proceedings of the 13th International Symposium. WORLD SCIENTIFIC, 2009. http://dx.doi.org/10.1142/9789814271110_0076.

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Zhong, Yunhong, Xinbiao Jiang, Qingyu Yu, and Wenshou Zhang. "Measurement of Thermal Neutron Energy Spectrum and Fluence of the Thermal Column in Xi’an Pulse Reactor." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29479.

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Neutron energy spectrum and fluence of the devices in a reactor are important parameters for the users. In this paper, the thermal neutron spectrum of the thermal column in Xi’an pulse reactor were measurement by the method of time of flight (TOF), and the peak of the energy spectrum is 0.0248±0.0006eV and the neutrons average energy is 0.048±0.001eV. With the spectrum results, the average cross section of 235U(n,f) and 197Au(n,γ) were calculated are respectively 92.08barn and 538.86barn. With the average cross sections, we measured the neutron fluence with the fission chamber and 197Au(n, γ)
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Wu, Linchun, and George H. Miley. "IEC-Based Neutron Generator for Security Inspection System." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22696.

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Large nuclear reactors are widely employed for electricity power generation, but small nuclear radiation sources can also be used for a variety of industrial/government applications. In this paper we will discuss the use of a small neutron source based on Inertial Electrostatic Confinement (IEC) of accelerated deuterium ions. There is an urgent need of highly effective detection systems for explosives, especially in airports. While current airport inspection systems are strongly based on X-ray technique, neutron activation including Thermal Neutron Analysis (TNA) and Fast Neutron Analysis (FNA
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Mehboob, Khurram, Xinrong Cao, and Majid Ali. "Application of Coincidence Technique for Neutron Flux Mapping in Boron Concentrated Paraffin Wax." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15585.

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In this paper, Neutron Activation Technique (NAT) is used for neutron flux mapping in homogenous boron concentrated paraffin wax. For this purpose, activator detectors were prepared by irradiating process in an Americium-Beryllium (241Am–9Be) neutron field for the required time period to induce approximate saturation activity. After this, the induced activity was measured by time coincidence method using a Sodium iodide (thallium) NaI (Tl) crystal detector and organic scintillation “Anthracene” detector for gamma ray and beta particle detection respectively. The activator detectors were activa
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Dodona, A. "The Determination of Vanadium in the Geological Samples through the Method of Neutron Activation." In 7th Congress of the Balkan Geophysical Society. EAGE Publications BV, 2013. http://dx.doi.org/10.3997/2214-4609.20131719.

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Miletic´, Marija. "Measurement of Neutron and Gamma Spatial Distribution in Radial Channel at VR1 Reactor." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29099.

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This work gives the theoretical description with a practical measurement of neutron and gamma spatial distributions in a radial experimental channel (RC) at VR1 research reactor. For providing the measurements an “off-line” and “on-line” methods were used. The “on-line” measurement of neutron spatial distribution was performed with a 3He gas filled detector. From the “off-line” measurements Neutron Activation method (for neutron detection) and Thermoluminescent method (for gamma radiation detection) were chosen. Results obtained from experiments were compared with the results from MCNP code.
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Chen, Xiaoliang, Zhendong Fan, Xiaoxian Chen, and Dingsheng Hu. "Measurement of Reaction Rate Distribution and Neutron Spectrum in China Experimental Fast Reactor." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16413.

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China Experimental Fast Reactor (CEFR) has completed physics start-up tests in 2010 and connected the grid on 40%FP in 2011. The reaction rate distribution, neutron spectrum are some important parameters for CEFR neutron field. In order to measure these parameters some low power irradiation tests using foil activation method have been done in CEFR core. Two kinds of special irradiation test subassemblies have been developed and fabricated for irradiation in CEFR core. And a digital high purity Germanium gamma-ray spectrometer system has been established for foil activity measurement. After doz
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Kin, T., Y. Sanzen, M. Kamida, K. Aoki, N. Araki, and Y. Watanabe. "Artificial Neural Network for Unfolding Accelerator-based Neutron Spectrum by Means of Multiple-foil Activation Method." In 2017 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC). IEEE, 2017. http://dx.doi.org/10.1109/nssmic.2017.8532892.

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Reports on the topic "Neutron activation method"

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Lee, Dongwon, Brian M. Bucher, Kenneth M. Krebs, Edward H. Seabury, and Jayson Wharton. Determination of the Deuterium-Tritium (D-T) Generator Neutron Flux using Multi-foil Neutron Activation Analysis Method. Office of Scientific and Technical Information (OSTI), 2019. http://dx.doi.org/10.2172/1524045.

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Kelly, J. G., and D. W. Vehar. Measurement of neutron spectra in varied environments by the foil-activation method with arbitrary trials. Office of Scientific and Technical Information (OSTI), 1987. http://dx.doi.org/10.2172/5327365.

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Bourdeau, J. E., and R. D. Dyer. Regional-scale lake-sediment sampling and analytical protocols with examples from the Geological Survey of Canada. Natural Resources Canada/CMSS/Information Management, 2023. http://dx.doi.org/10.4095/331911.

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Abstract:
Regional-scale lake sediment surveys have been successfully used since the 1970s as a means for reconnaissance geochemical exploration. Lake sediment sampling is typically performed in areas with a lack of streams and an overabundance of small-sized (=5 km across) lakes. Lake sediments are known to have major, minor and trace element concentrations that reflect the local geology. Overall, lake sediment surveys are planned and conducted following four distinct stages: 1) background research, 2) orientation survey, 3) regional survey, and 4) detailed survey. At the Geological Survey of Canada, s
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Carpita, Nicholas C., Ruth Ben-Arie, and Amnon Lers. Pectin Cross-Linking Dynamics and Wall Softening during Fruit Ripening. United States Department of Agriculture, 2002. http://dx.doi.org/10.32747/2002.7585197.bard.

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Our study was designed to elucidate the chemical determinants of pectin cross-linking in developing fruits of apple and peach and to evaluate the role of breakage cross-linkages in swelling, softening, and cell separation during the ripening. Peaches cell walls soften and swell considerably during the ripening, whereas apples fruit cells maintain wall firmness but cells separate during late stages of ripening. We used a "double-reduction" technique to show that levels of non-methyl esters of polyuronic acid molecules were constant during the development and ripening and decreased only in overr
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