• 제목/요약/키워드: 베타-선

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Development of ZnS(Ag)/plastic dual scintillator sheet for simultaneous alpha- and beta-ray counting (알파 및 베타선 동시측정용 ZnS(Ag)/플라스틱 이중섬광체 검출센서 개발)

  • Seo, Bum-Kyoung;Woo, Zu-Hee;Kim, Gye-Hong;Lee, Kune-Woo;Lee, Dong-Gyu;jung, Chong-Hun
    • Analytical Science and Technology
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    • v.21 no.2
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    • pp.117-122
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    • 2008
  • Dual scintillator for simultaneous alpha- and beta-ray counting used by detection materials of a surface contamination monitor was developed. In this study, preparation method was not a heat melting method but a solvent method, by which the counting material was manufactured by dissolving the polymer materials with solvent. It was simplified the preparation process. Plastic scintillator for beta-ray counting was prepared by solidifying the casting solution mixed with organic scintillator, polymer, and solvent. ZnS(Ag) scintillator layer was prepared by screen printing the paste solution mixed with ZnS(Ag), paste, and solvent onto the plastic layer. The good counting ability for alpha- and beta-ray using the ZnS(Ag)/plastic dual scintillator prepared and possibility for the counting material of surface contamination monitor was confirmed.

The Response Correction Function of TL Dosimeter for Shallow Dose Assessment in Tl-204 Beta Fields (Tl-204 베타선장에서의 피부선량평가를 위한 열형광선량계의 베타보정함수)

  • Lee, Sang-Yoon;Kim, Jang-Lyul;Seo, Kyung-Won
    • Nuclear Engineering and Technology
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    • v.26 no.3
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    • pp.381-388
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    • 1994
  • Recently, the American National Standards Institute (ANSI) had made some changes in the radiation sources specified from those in the original performance test criteria ANSI N13. 11-1983. In case or beta category, in addition to the high-energy $^{90}$ Sr/$^{90}$ Y beta source, the $^{204}$ Tl source was added because many workplaces have significant levels of lower energy betas. In this study, the performance or the Teledyne PB-3 personnel dosimetry system in the fields of $^{204}$ Tl and $^{90}$ Sr/ $^{90}$ Y beta was investigated using the PTB beta secondary standard sources. The new beta correction function of PB-3 personnel dosimetry system for $^{204}$ Tl beta was also developed in this response experiment. The results show that the Teledyne PB-3 personnel dosimetry system is very effective for $^{90}$ Sr/ $^{90}$ Y beta dose assessment. In case of $^{204}$ Tl beta radiation, however, the results of simple performance test indicated that the use of beta correction factor(=2.088) which was recommanded by manufacturer may result in unexpectable overestimation of delivered dose by about 60%, while the use of developed beta correction function could measure the delivered doses in errors of 15%.

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Development of the ZnS(Ag)/BC-408 phoswich detector for monitoring radioactive contamination inside pipes (배관 내부 방사능 오염도 측정용 ZnS(Ag)/BC-408 phoswich 검출기 개발)

  • Kim, Gye-Hong;Park, Chan-Hee;Jung, Chong-Hun;Lee, Kune-Woo;Seo, Bum-Kyoung
    • Journal of Radiation Protection and Research
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    • v.31 no.3
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    • pp.123-128
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    • 2006
  • A small radiation detection system is necessary for the direct characterization of alpha/beta-ray contamination inside pipes generated during the decommission of a nuclear facility. In this work, the new type phoswich detector consisting of the ZnS(Ag) and plastic scintillator for ${\alpha}/{\beta}$ simultaneous counting was designed as part of a development of a equipment capable of monitoring radiological contamination inside pipes. The optimum counting conditions in dimensions of scintillator and a detection system were experimentally confirmed and a performance of alpha/beta-ray discrimination was evaluated. As a result, optimum conditions of a detector suitable for monitoring radiological contamination inside pipes and a feasibility of application to pipe-inside were confirmed.

Radioassay of Multiple Beta-Labeled Mixtures using Least-Square Method (최소자승법을 이용한 다수 베타 방출 핵종 혼합물의 방사능 분석)

  • Seon, Kwang-Il;Nam, Uk-Won;Kong, Kyoung-Nam;Kim, Chang-Kyu;Lee, Dong-Myung;Lee, Sang-Kook
    • Journal of Radiation Protection and Research
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    • v.26 no.4
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    • pp.375-384
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    • 2001
  • It is possible to count and perform quench correction on two ${\beta}$ -label samples so long as the maximum ${\beta}$-energies are sufficiently different. However, when 4he conventional technique is applied to the radioassay of a mixture of more than three nuclides, the reliability of the activities determined is considerably reduced, resulting from the large overlapping of liquid scintillation pulse height distributions of each nuclide. A technique that allows the activities of multiple ${\beta}$-labeled samples to be radioassayed was proposed by using the least square method. The technique was applied to mixture samples of $^3H,\;^{14}C,\;^{36}Cl$, and $^{90}Sr$. The analytical values were in good agreement with the reference values within 7% relative error.

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Development of Prototype Liquid Scintillator System for Monitoring Liquid Radioactive Waste (배수 모니터링 액체섬광검출시스템의 프로토 타입 개발)

  • Nam, Uk-Won;Seon, Kwang-Il;Kong, Kyoung-Nam;Kim, Chang-Kyu;Lee, Dong-Myung;Lee, Sang-Kook
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.173-182
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    • 2003
  • A prototype liquid scillatillator system for measurement of multiple beta-labeled mixtures was developed and its characteristic was investigated. The signal processing system consists of two photomultiplier tubes and the coincident count circuit. The characteristic of the system was analyzed using 4 beta-labeled samples $(^3H,\;^{14}C,\;^{36}Cl\;and\;^{90}Sr)$. Beta spectra from the samples were obtained without radiation shielding, and the detection limits for each nuclides were estimated based on the spectra. The estimated detection limits were compared to the legal regulation values. It is found that the liquid radioactive nuclides are detectable well below the legal regulation values.

Measurement of Absorbed Dose at the Tissue Surface from a Plain $^{90}Sr+^{90}Y$ Beta Sources (조직 표면에서의 베타선 흡수선량 측정)

  • Hah, Suck-Ho;Kim, Jeong-Mook;Yook, Chong-Chul
    • Journal of Radiation Protection and Research
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    • v.16 no.2
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    • pp.17-26
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    • 1991
  • Beta ray $(^{90}Sr+^{90}Y)$ absorbed dose at tissue surface was measured from the distance of 30cm by use of extrapolation chamber. In the measurement, following factors were considered: effective area of collecting electrode, polarity effect, ion recombination and window attenuation. The measured absorbed dose rate at tissue surface was $1.493{\mu}Gy/sec$ with ${\pm}2.9%$.

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