• Title/Summary/Keyword: Gamma ray Spectrum

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Radioactive Concentrations in Chemical Fertilizers

  • Gwang-Ho Kim;Jae-Hwan Cho
    • Journal of Radiation Protection and Research
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    • v.47 no.4
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    • pp.195-203
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    • 2022
  • Background: The aim of the present study was to determine radioactive concentrations in fertilizers known to contain essential nutrients. Results of this study could be used as basic data to monitor the impact of chemical fertilizers on the environment and public health. Nitrogen fertilizers, calcium fertilizers, sulfur fertilizers, phosphate acid fertilizers, and potassium chloride fertilizers were used in this study. Materials and Methods: Five chemical fertilizers were pulverized, placed in polyethylene containers, and weighed. The time to measure each specimen was set to be 3,600 seconds for a scintillator-based gamma-ray spectroscopy system. Concentration of gamma radionuclide was analyzed based on obtained spectra. At the end of the measurement, the spectrum file was stored and used to calculate radioactive concentrations using a gamma-ray spectrometer software. Results and Discussion: In the nitrogen fertilizer, 3.49 ± 5.71 Bq/kg of 137Cs, 34.43 ± 7.61 Bq/kg of 134Cs, and 569.16 ± 91.15 of 40K were detected whereas 131I was not detected. In the calcium fertilizer, 5.74 ± 4.40 Bq/kg of 137Cs (the highest concentration among all fertilizers), 22.37 ± 5.39 Bq/kg of 134Cs, and 433.67 ± 64.24 Bq/kg of 40K were detected whereas 131I was not detected. In the sulfur fertilizer, 347.31 ± 55.73 Bq/kg of 40K, 19.42 ± 4.53 Bq/kg of 134Cs, 2.21 ± 3.49 of 137Cs, and 0.04 ± 0.22 Bq/Kg of 131I were detected. In the phosphoric acid fertilizer, 70,007.34 ± 844.18 Bq/kg of 40K (the highest concentration among all fertilizers) and 46.07 ± 70.40 Bq/kg of 134Cs were detected whereas neither 137Cs nor 131I was detected. In the potassium chloride fertilizer, 12,827.92 ± 1542.19 Bq/kg of 40K was and 94.76 ± 128.79 Bq/kg of 134Cs were detected whereas neither 137Cs nor 131I was detected. The present study examined inorganic fertilizers produced by a single manufacturer. There might be different results according to the country and area from which fertilizers are imported. Further studies about inorganic fertilizers in more detail are needed to create measures to reduce 40K. Conclusion: Measures are needed to reduce radiation exposure to 40K contained in fertilizers including phosphoric acid and potassium chloride fertilizers.

Quality Control of Tungsten-188/Rhenium-188 Generator (Tungsten-188/Rhenium-188 발생기의 정도관리)

  • Chang, Young-Soo;Jeong, Jae-Min;Lee, Dong-Soo;Chung, June-Key;Lee, Myung-Chul
    • The Korean Journal of Nuclear Medicine
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    • v.32 no.5
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    • pp.425-432
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    • 1998
  • Purpose: For the purpose of using Re-188 as a therapeutic radionuclide, we performed the quality control of the W-188/Re-188 generator system. Materials and Methods: Several quality control tests of the Re-188 eluate from generator were carried out for about 300 days. After elution of Re-188 with normal saline (20 ml), chromatogram and gamma-ray spectrum of Re-188 eluate were obtained. The presence of aluminum which was derived from the alumina bed of the generator was detected by using aluminum ion indicator kit. Re-188 eluate was allowed to decay for several days, and then W-188 breakthrough in the Re-188 eluate was measured by detecting gamma-ray at 227 keY and 290 keV. The pH and the pyrogenicity of the eluate were checked. The Re-188 bolus was concentrated with ion exchange columns. Results: The radioactivity of Re-188 eluate from the generator was $67.4{\pm}7.0%$ of W-188 during 270 days, and it was highest at third day after previous elution. Radiochemical purity of Re-188 eluate obtained from chromatogram was higher than 99%. Gamma-ray spectrum of Re-188 eluate showed a peak at 155 keV. Aluminum ion and W-188 contamination were not detected. The PH of Re-188 eluate was 3 and the concentration yield was 85%. Conclusion: Our experiments and results on quality control tests of Re-188 eluate from W-188/Re-188 generator may be useful for setting W-188/Re-188 generator in hospitals.

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Cooling Time Determination of Spent Nuclear Fuel by Detection of Activity Ratio $^{l44}Ce /^{l37}Cs$ (방사능비 $^{l44}Ce /^{l37}Cs$ 검출에 의한 사용후핵연료 냉각기간 결정)

  • Lee, Young-Gil;Eom, Sung-Ho;Ro, Seung-Gy
    • Nuclear Engineering and Technology
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    • v.25 no.2
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    • pp.237-247
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    • 1993
  • Activity ratio of two radioactive primary fission products which had sufficiently different half-lives was expressed as functions of cooling time and irradiation histories in which average burnup, irradiation time, cycle interval time and the dominant fissile material of the spent fuel were included. The gamma-ray spectra of 36 samples from 6 spent PWR fuel assemblies irradiated in Kori unit-1 reactor were obtained by a spectrometric system equipped with a high purity germanium gamma-ray detector. Activity ratio $^{l44}$Ce $^{l37}$Cs, analyzed from each spectrum, was used for the calculation of cooling time. The results show that the radioactive fission products $^{l44}$Ce and $^{l37}$Cs are considered as useful monitors for cooling time determination because the estimated cooling time by detection of activity ratio $^{l44}$Ce $^{l37}$Cs agreed well with the operator declared cooling time within relative difference of $\pm$5 % despite the low counting rate of the gamma-ray of $^{l44}$Ce (about 10$^{-3}$ count per second). For the samples with several different irradiation histories, the determined cooling time by modeled irradiation history showed good agreement with that by known irradiation history within time difference of $\pm$0.5 year. From this result, it would be expected to be possible to estimate reliably the cooling time of spent nuclear fuel without the exact information about irradiation history. The feasibility study on identification of and/or sorting out spent nuclear fuel by applying the technique for cooling time determination was also performed and the result shows that the detection of activity ratio $^{l44}$Ce $^{l37}$Cs by gamma-ray spectrometry would be usefully applicable to certify spent nuclear fuel for the purpose of safeguards and management in a facility in which the samples dismantled or cut from spent fuel assemblies are treated, such as the post irradiation examination facility.mination facility.

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Scintillation properties of CsSrCl3 single crystal (CsSrCl3 단결정의 섬광특성)

  • Doh, Sih-Hong;Kim, Sung-Hwan;Ra, Se-Jin;Kim, Hong-Joo;Kang, Hee-Dong;Oh, Moon-Young
    • Journal of Sensor Science and Technology
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    • v.16 no.5
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    • pp.337-341
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    • 2007
  • $CsSrCl_{3}$ crystal was grown using Czochralski method from equimolar mixture of CsCl and $SrCl_{2}$. The spectrum range of the luminescence excited by 205 nm of wavelength was about $280{\sim}550$ nm, and its peak emission appeared at 343 nm. The luminescence decay curve of the $CsSrCl_{3}$ revealed two exponential components with time constants of 60 ns and 700 ns. The energy resolution for $^{137}Cs$ 662 keV ${\gamma}$-ray was 10.3 %. The pulse shape was linear at high energy, but some deviation existed in the low energy region.

Data intercomparison and determination of toxic and trace elements in Algae using Instrumental Neutron Activation Analysis (중성자방사화분석에 의한 Algae중의 독성미량원소의 정량 및 실험실간 비교검증)

  • Chung, Yong-Sam;Moon, Jong-Hwa;Park, Kwang-Won;Lee, KiI-Yong;Yoon, Yoon-Yeol
    • Analytical Science and Technology
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    • v.12 no.4
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    • pp.346-353
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    • 1999
  • For the non-destructive multi-elemental analysis of environmental and biological materials, instrumental neutron activation analysis (INAA) was applied for the determination of toxic and trace elements in a set of three Algae samples provided by the International Atomic Energy Agency (IAEA). The analytical quality control was evaluated by comparing the analytical results of two standard reference materials of the National Institute of Standards and Technology (NIST); Oyster Tissue (SRM 1566a) and Citrus Leaves (SRM 1572). According to given analytical procedure, the concentration of 15-25 elements including spiked elements such as As, Cd, Cr and Hg in Algae samples were determined. To identify and validate these results, a data intercomparison program using more than 35 analytical methods in 150 laboratories was carried out and the estimated statistical data are summarized. Result of INAA is favorable, therefore, it is illustrated that can be applied for routine analysis of essential and toxic elements in algae samples as well as analytical quality assurance.

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Effects of Plasticizer to Polyvinylchloride on Radio-resistance of Organic Stabilizer,Dielectric and Mechanical Characteristics under the Influence of Radiation (Polyvinylchloride에 있어 가소제의 첨가가 유기안정제의 내 방사성 및 유전, 기계적 특성에 미치는 영향)

  • 김봉흡;강도열;이재인
    • 전기의세계
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    • v.26 no.2
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    • pp.89-94
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    • 1977
  • In order to investigate the properties of radiation resistance together with dielectric, and mechanical relaxation behaviors of polyvinylcholoride exposed to several different doses under the .gamma.-ray of Co$^{60}$ source, several observations were carried out on the exposed specimens propared by mixing dibutyl-tin-dilaulate and dibutyl-tin-dimaleate as stabilizer with or without adding dioctyl-phthalate as plasticizer. Conclusions obtained from the study are as follows: The origin of the absorption band at 1,540-1,640$cm^{-1}$ / on I.R. spectrum seems to be RCOO- ion originated from ionization of the stabilizer, and this peak can be useful as a measure of radiation resistance on polyvinylchloride. Addition of increasing plasticizer to polyvinylchloride exhibits increasing radiation resistance and the reason for this result may be attributed to aromatic resonance absorption of radiation energy by diotylphthalate. On dose dependent dielectric characteristics, nonplastized specimen shows a peak at about 10 Mrad and that this peak disappears on the plastification of specimens. Those phenomena may be explainable in considering the statistical distribution of scissored chain molecular segments as well as the plastification process of plasticizer to polyvinylchloride chain molecules.

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SHOCK ACCELERATION MODEL WITH POSTSHOCK TURBULENCE FOR GIANT RADIO RELICS

  • Kang, Hyesung
    • Journal of The Korean Astronomical Society
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    • v.50 no.4
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    • pp.93-103
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    • 2017
  • We explore the shock acceleration model for giant radio relics, in which relativistic electrons are accelerated via diffusive shock acceleration (DSA) by merger-driven shocks in the outskirts of galaxy clusters. In addition to DSA, turbulent acceleration by compressive MHD modes downstream of the shock are included as well as energy losses of postshock electrons due to Coulomb scattering, synchrotron emission, and inverse Compton scattering off the cosmic background radiation. Considering that only a small fraction of merging clusters host radio relics, we favor a reacceleration scenario in which radio relics are generated preferentially by shocks encountering the regions containing low-energy (${\gamma}_e{\leq}300$) cosmic ray electrons (CRe). We perform time-dependent DSA simulations of spherically expanding shocks with physical parameters relevant for the Sausage radio relic, and calculate the radio synchrotron emission from the accelerated CRe. We find that significant level of postshock turbulent acceleration is required in order to reproduce broad profiles of the observed radio flux densities of the Sausage relic. Moreover, the spectral curvature in the observed integrated radio spectrum can be explained, if the putative shock should have swept up and exited out of the preshock region of fossil CRe about 10 Myr ago.

Di- and Triorganotin(IV) Complexes of Sulfur-containing Ylidenemalonates

  • Jung, Ok-Sang;Lee, Young-A;Hong, Jong-Ki;Jeong, Jong-Hwa;Sohn, Youn-Soo
    • Bulletin of the Korean Chemical Society
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    • v.14 no.6
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    • pp.722-726
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    • 1993
  • Organotin(IV) complexes of ylidenemalonates $(R_xSn)_{x-1}(O_2C)_2C=C(SR')_2\;(R=n-C_4H_9,\;C_6H_5,\;cyclo-C_6H_{11},\;CH_3OOCCH_2CH_2;\;x=2,3;\;R'=CH_3,\;R_2'=-CHCH-,\;-CH_2CH_{2^-})$ have been synthesized and characterized by means of various spectroscopic methods. The X-ray crystal structure of $(Ph_3Sn)_2(O_2C)_2C=C(SCH_3)_2$ has been determined (Pi; a= 9.704(2) ${\AA}$, b= 14.412(1) ${\AA}$, c= 14.760(3) ${\AA}$, ${alpha}$=74.26(1)$^{\circ}$, ${beta}$=99.38(l)$^{\circ}$, ${\gamma}$=79.09(1)$^{\circ}$, $V= 1950.7(7){\AA}^3$) and refined to R= 0.045. The crystal structure discloses a discrete molecule with bidentate-like carboxylate ligand. For diorganotin analogues, the structures are discussed in terms of IR, $^1H-NMR,\;^{13}C-NMR$, and FAB mass spectrometry. The mass spectrum indicates that the diorganotin complexes of ylidenemalonates are dimeric.

Soil Radioactivity in Urban Parks of Incheon (인천지역 근린공원의 토양 방사능 농도)

  • Jun-Su, Jang;Sang-Bok, Lee;Ga-Eun, Baek;Hee-Cheol, Shin;Gyeong-Jae, Lee;Do-Hwa, Lee;Sungchul, Kim
    • Journal of radiological science and technology
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    • v.46 no.1
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    • pp.37-42
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    • 2023
  • Most of research on environmental radioactivity is conducted in areas near nuclear power plants, so basic data about the distribution of environmental radioactivity in soil in other areas are insufficient. Therefore, in this study, divide into four categories by the land development characteristics of Incheon and the purpose of development, and confirm the stability of the Incheon through soil sample collection and gamma-ray analysis based on 40K, 137Cs and 226Ra (214Pb, 214Bi). The spectrum obtained by measuring for 80,000 seconds by using the HPGe detector was analyzed by Genie 2000 program. Soil radioactivity concentrations in urban parks of Incheon area are generally within a safe range compared to the results of the Nuclear safety and security commission. However, as 137Cs was detected in one park, which will require continuous monitoring.

Comparison of Environmental Radiation Survey Analysis Results in a High Dose Rate Environment Using CZT, NaI(Tl), and LaBr3(Ce) Detectors

  • Sungyeop Joung;Wanook Ji;Eunjung Lee;Young-Yong Ji;Yoomi Choi
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.21 no.4
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    • pp.543-558
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    • 2023
  • Currently, Japan is undertaking a nationwide project to measure and map radioactive contamination around Fukushima, as part of the efforts to restore normalcy following the nuclear accident. The Japan Atomic Energy Agency (JAEA) manages the Fukushima Environmental Safety Center, located approximately 20 km north of the Fukushima Daiichi nuclear power plant in Minamisōma City, Fukushima Prefecture. In collaboration with the JAEA, this study involved conducting comparison experiments and analyses with radiation detectors in high radiation environments, a challenging task in Korean environments. Environmental radiation surveys were conducted using three types of detectors: CZT, NaI(Tl), and LaBr3(Ce), across two contaminated areas. Dose rate values were converted using dose rate conversion factors for each detector type, and dose rate maps were subsequently created and compared. The detectors yielded similar results, demonstrating their feasibility and reliability in high radiation environments. The findings of this study are expected to be a crucial reference for enhancing the verification and supplementation of procedures and methods in future radiation measurements and mobile surveys in high-radiation environments, using these three types of radiation instruments.