• Title/Summary/Keyword: neutron measurement

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Crystallite Size Measurement of Uranium Oxide Fuel Powders by Neutron Diffraction (중성자 회절에 의한 산화우라늄 핵연료 분말의 결정크기 측정)

  • 류호진;강권호;문제선;송기찬;최용남
    • Journal of Powder Materials
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    • v.10 no.5
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    • pp.318-324
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    • 2003
  • The nano-scale crystallite sizes of uranium oxide powders in simulated spent fuel were measured by the neutron diffraction line broadening method in order to analyze the sintering behavior of the dry process fuel. The mixed $UO_2$ and fission product powders were dry-milled in an attritor for 30, 60, and 120 min. The diffraction patterns of the powders were obtained by using the high resolution powder diffractometer in the HANARO research reactor. Diffraction line broadening due to crystallite size was measured using various techniques such as the Stokes' deconvolution, profile fitting methods using Cauchy function, Gaussian function, and Voigt function, and the Warren-Averbach method. The non-uniform strain, stacking fault and twin probability were measured using the information from the diffraction pattern. The realistic crystallite size could be obtained after separation of the contribution from the non-uniform strain, stacking fault and twin.

Education and Training Program using HANARO

  • Seo, Kyung-Won;Han, Eun-Young
    • Journal of Radiation Protection and Research
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    • v.24 no.4
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    • pp.231-233
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    • 1999
  • This report will introduce the epitome about the subject, HANARO (Hi-flux Advanced Neutron Application Reactor designed by KAERI in early 1995) Utilization Education Training Program Development and Operation, which is one of the nuclear research basic expansion businesses executed from 1999. 12. to strengthen the usage of HANARO. This program consists of the basic reactor experiments program for university students who have specialty of nuclear and other engineering, and the special research education program for faculties from universities and researchers from industrial fields. Principle lessons are reactor operation, radioisotope production, neutron activation analysis, neutron radiography, radiation shield (health physics), nuclear fuel combustion measurement by gamma scanning arrangement, and CNS (Compact Nuclear Simulator) and so on.

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A Design on neutron absorber and moderator for the content measurement of Asphalt (아스팔트 함량 측정을 위한 중성자 흡수체 및 감속재 설계)

  • Kim Ki-Joon
    • Journal of the Korea Computer Industry Society
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    • v.7 no.1
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    • pp.7-14
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    • 2006
  • In Korea, under the influence of the jurisdiction, usage of radioisotopes are limited. The limitation is $100[{\mu}Ci]$ or less. Therefore, in this study, basic data were designed, and the following data are needed in order to improve content measuring instrument which is suitable for radioisotopes limitation. Owing to the source and detector's properties, measuring instrument was designed geometrically, neutron and photon's particle transportation was analysed by using the MCNP code which is in Monte Carlo Method, also the location of source and detectors, geometrical structure of neutron absorber and moderator was designed.

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Activation-Analysis of trace Thallium in Meteorites, Rocks, Minerals, Alloys, and Biological Samples using 4.2-Minute Thallium-206 (4.2分의 短壽命 Thallium-206의 放射化分析)

  • Kim, Chong-Kuk
    • Journal of the Korean Chemical Society
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    • v.5 no.1
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    • pp.26-28
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    • 1961
  • Microgram quantities of thallirum in meteorites, rocks, minerals, alloys and biological samples have been analyzed by rapid neutron activation analysis. A l0-minute radiochemical separation procedure coupled with a gas-flow proportional detector for 4.2-minute half life measurement and a gamma or beta scintillation detector placed in close proximity to the sample permitted detection of the 4.2-min Tl206. Samples were irradiated for 10-minutes at a thermal neutron flux of approximately $0.95{\times}10^{11}$ neutron-$cm^{-2}-sec^{-1}.$ The low limits of detection was about $10^{-7}$ gm of thallium.

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The Fabrication and Control Logic Design of Proto-type Drive System (시험용 구동시스템의 제작 및 제어로직 설계)

  • Kim, S.G.;Lee, E.W.
    • Proceedings of the KIEE Conference
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    • 2001.10a
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    • pp.36-38
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    • 2001
  • A neutron controls a nuclear fission in the core of a reactor. Drive system for in-core neutron detector is an equipment that drives the detector and cable to survey neutron flux in the reactor. The drive system introduced by this paper was designed for mock-up system and fabricated to drive two drivers that having a different function. The system consists of a driver assembly, a power transmission part, and cable storage part. And there is a control panel that contains PLC and inverter. This paper is going to introduce the design and certify the operation status of completed system by control panal. And we conducted the test for torque measurement.

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Precise Determination of Silicon in Ceramic Reference Materials by Prompt Gamma Activation Analysis at JRR-3

  • Miura, Tsutomu;Matsue, Hideaki
    • Nuclear Engineering and Technology
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    • v.48 no.2
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    • pp.299-303
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    • 2016
  • Prompt gamma activation analysis using a thermal neutron-guided beam at Japan Atomic Energy Agency JRR-3M was applied for the precise determination of Si in silicon nitride ceramic reference materials [Japan Ceramic Reference Material (JCRM) R 003]. In this study, the standard addition method coupled with internal standard was used for the nondestructive determination of Si in the sample. Cadmium was used as internal standard to obtain the linear calibration curves and to compensate for the neutron beam variability. The analytical result of determining Si in JCRM R 003 silicon nitride fine powder ceramic reference materials using prompt gamma activation analysis was in good agreement with that obtained by classical gravimetric analysis. The relative expanded measurement uncertainty (k = 2) associated with the determined value was 2.4%.

Plutonium mass estimation utilizing the (𝛼,n) signature in mixed electrochemical samples

  • Gilliam, Stephen N.;Coble, Jamie B.;Goddard, Braden
    • Nuclear Engineering and Technology
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    • v.54 no.6
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    • pp.2004-2010
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    • 2022
  • Quantification of sensitive material is of vital importance when it comes to the movement of nuclear fuel throughout its life cycle. Within the electrorefiner vessel of electrochemical separation facilities, the task of quantifying plutonium by neutron analysis is especially challenging due to it being in a constant mixture with curium. It is for this reason that current neutron multiplicity methods would prove ineffective as a safeguards measure. An alternative means of plutonium verification is investigated that utilizes the (𝛼,n) signature that comes as a result of the eutectic salt within the electrorefiner. This is done by utilizing the multiplicity variable a and breaking it down into its constituent components: spontaneous fission neutrons and (𝛼,n) yield. From there, the (𝛼,n) signature is related to the plutonium content of the fuel.

Prospects of the gravitational wave astronomy

  • Lee, Hyung Mok
    • The Bulletin of The Korean Astronomical Society
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    • v.46 no.1
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    • pp.27.4-28
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    • 2021
  • Since the first direct detection of the gravitational waves in 2015, more than 50 events coming from the merging of compact binaries composed of black holes and neutron stars have been observed. The simultaneous detection of gravitational waves and electromagnetics waves from the merging of neutron stars opened up multi-messenger astronomy. The forthcoming observations with better sensitivity by the network of ground based detectors will enrich the gravitational wave source populations and provide valuable information regarding stellar evolution, dynamics of dense stellar systems, and star formation history across the cosmic time. The precision of the Hubble constant from the distance measurement of gravitational sources will improve with more binary neutron star events are observed together with the aftweglows. I will also briefly cover the expected scientiic outcomes from the future detectors that are sensitive to much lower frequenies than current detectors.

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