• Title/Summary/Keyword: KAERI

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Determination of Personnel Exposures in the Lower Energy Ranges of X-Ray by Photographic Dosimeter (저(低)에너지 X-선장(線場)에서 필름배지에 의한 개인피폭선량(個人被曝線量)의 결정(決定))

  • Ha, C.W.;Kim, J.R.;Suh, K.W.
    • Journal of Radiation Protection and Research
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    • v.11 no.1
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    • pp.57-64
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    • 1986
  • This paper described an improved technical method required for proper evaluation of personnel exposures by means of the photographic dosimeter developed by KAERI in lower gamma or X-ray energy regions, with which response of the dosimeter varies significantly. With calibration of the dosimeter in the energy range from 30 to 300 keV, the beam spectrum was carefully selected and specified it adequately. The absorber combinations and absorber thickness used to obtain the specified X-ray spectra from a constant potential X-ray machine were determined theoretically and also experimentally. A correlation between the density and exposure for the four separate energies, such as $49\;keV_{eff},\;154\;keV_{eff}\;250\;keV_{eff}\;and\;662\;keV$, is experimentally determined. As a result, it can be directly evaluated the exposure from the measured response of dosimeter.

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Establishment of the Monoenergetic Fluorescent X-ray Radiation Fields (교정용 단일에너지 형광 X-선장의 제작)

  • Kim, Jang-Lyul;Kim, Bong-Hwan;Chang, Si-Young;Lee, Jae-Ki
    • Journal of Radiation Protection and Research
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    • v.23 no.1
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    • pp.33-47
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    • 1998
  • Using a combination of an X-ray generator Installed in radiation calibration laboratory of Korea Atomic Energy Research Institute (KAERI) and a series of 8 radiators and filters described in ISO-4037, monoenergetic fluorescent X-rays from 8.6 keV to 75 keV were produced. This fluorescent X-rays generated by primary X-rays from radiator were discriminated $K_{\beta}$ lines with the aid of filter material and the only $K_{\alpha}$ X-rays were analyzed with the high purity Ge detector and portable MCA. The air kerma rates were measured with the 35 co ionization chamber and compared with the calculational results, and the beam uniformity and the scattered effects of radiation fields were also measured. The beam purities were more than 90 % for the energy range of 8.6 keV to 75 keV and the air kerma rates were from 1.91 mGy/h (radiator : Au, filter : W) to 54.2 mGy (radiator : Mo, filter : Zr) at 43 cm from center of the radiator. The effective area of beam at the measurement point of air kerma rates was 12 cm ${\times}$ 12 cm and the influence of scattered radiation was less than 3 %. The fluorescent X-rays established in this study could be used for the determination of energy response of the radiation measurement devices and the personal dosemeters in low photon energy regions.

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Studies ell the Ecological Characteristics of Beanfly (Melanagromyza sp.) in Soybean (파종시기별 콩줄기굴파리 (Melanagromyza sp.)의 발생 및 피해조사)

  • Kwon S.H.;Chung K.H.;Lee Y.I.;Ryu J.
    • Korean journal of applied entomology
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    • v.20 no.2 s.47
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    • pp.98-102
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    • 1981
  • For the investigation of seasonal fluctuation of immature (lavae and pupae) beanfly, infestation rates, and habit, several soybean-cultivars were planted at Kumgok Experiment Farm of KAERI by three different planting times at 25-day intervals. Infestation rates of beanflies were ranged from $85\%\;to\;100\%$ in accordance. with the planting dates, where an increase in infestation rate was found with delay in planting dates. Immature beanflies were already observed from lune 20 by plant dissection counts. Three peaks of the seasonal fluctuation of lava were shown by occurring on July 10, August 10 and 50 during the soybean cultivation, while two peaks of pupal appearances were found. The most high peaks of lavae and pupae occurred on August 10 and 30, respectively. The lava were habitable in the pith or cortex tissue of soybean stem. They prepared tiny hole on the axilla as well as the internode of stem, and then they pupated in the holes from which the adults are able to escape. Immature beanfly seemed to prefer invading to the underground part of the stem when the soybean plants were in young stage.

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A Revisit to the Recent Human Error Events in Nuclear Power Plants Focused to the Organizational and Safety Culture

  • Lee, Yong-Hee
    • Journal of the Ergonomics Society of Korea
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    • v.32 no.1
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    • pp.117-124
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    • 2013
  • Objective: This paper presents additional considerations related to organization and safety culture extracted from recent human error incidents in Korea, such as station blackout(i.e., SBO) in Kori#1. Background: Safety culture has been already highlighted as a major cause of human errors after 1986 Chernobyl accident. After Fukushima accident in Japan, the public acceptance for nuclear energy has taken its toll. Organizational characteristics and culture became elucidated as a major contributor again. Therefore many nuclear countries are re-evaluating their safety culture, and discussing any preparedness and its improvement. On top of that, there was an SBO in 2012 in the Kori#1. Korean public feels frustrated due to the similar human errors causing to a catastrophe like Fukushima accident. Method: This paper reassesses Japan's incidents, and revisits Korea's recent incidents. It focuses on the analysis of the hazards rather than the causes of human errors, the derivation of countermeasures, and their implementation. The preceding incidents and conclusions from Japanese experience are also re-analyzed. The Fukushima accident was an SBO due to the natural disaster such as earthquakes and a successive tsunami. Unlike the Fukushima accident, the Kori#1 incident itself was simple and restored without any loss and radioactive release. However, the fact that the incident was deliberately concealed led to massive distrust. Moreover, the continued violation of rules and organized concealment of the accident are serious signs of a new distorted type of human errors, blatantly revealing the cultural and fundamental weakness of the current organization. Result: We should learn from Japanese experiences who had taken pride in its safety technology and fairly high confidence in safety culture. Japan's first criticality accident in JCO facility splashed cold water on that confidence. It has turned out to be a typical case revealing the problems in the organization and safety culture. Since Japan has failed to gain lessons and countermeasure, the issue persists to the Fukushima incident. Conclusion: Safety culture is not a specific independent element, which makes it difficult to either evaluate it properly or establish countermeasures from the lessons. It may continue to expose similar human errors such as concealment of incident and manipulation of bad data. Application: Not only will this work establish the course of research for organization and safety culture, but this work will also contribute to the revitalization of Korea's nuclear industry from the disappointment after the export contract to UAE.

Acceleration Test Method for Failure Prediction of the End Cap Contact Region of Sodium Cooled Fast Reactor Fuel Rod (소듐냉각 고속로 연료봉단의 접촉부 손상예측을 위한 가속시험 방법)

  • Kim, Hyung-Kyu;Lee, Young-Ho;Lee, Hyun-Seung;Lee, Kang-Hee
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.41 no.5
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    • pp.375-380
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    • 2017
  • This paper reports the results of an acceleration test to predict the contact-induced failure that could occur at the cylinder-to-hole joint for the fuel rod of a sodium-cooled fast reactor (SFR). To incorporate the fuel life of the SFR currently under development at KAERI (around 35,000 h), the acceleration test method of reliability engineering was adopted in this work. A finite element method was used to evaluate the flow-induced vibration frequency and amplitude for the test parameter values. Five specimens were tested. The failure criterion during the life of the SFR fuel was applied. The S-N curve of the HT-9, the material of concern, was used to obtain the acceleration factor. As a result, a test time of 16.5 h was obtained for each specimen. It was concluded that the $B_{0.004}$ life would be guaranteed for the SFR fuel rods with 99% confidence if no failure was observed at any of the contact surfaces of the five specimens.

Development of $^{192}Ir$ Small-Focal Source for Non-Destructive Testing Application by Using Enriched Target Material (고농축 표적을 이용한 비파괴검사용 $^{192}Ir$ 미세초점선원 개발)

  • Son, K.J;Hong, S.B.;Jang, K.D.;Han, H.S.;Park, U.J.;Lee, J.S.;Kim, D.H.;Han, K.D.;Park, C.D.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.27 no.1
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    • pp.31-37
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    • 2007
  • A $^{192}Ir$ small-focal source has been developed by using the HANARO reactor and the radioisotope production facility at the Korea Atomic Energy Research Institute (KAERI). The small-focal source with the dimension of 0.5 mm in diameter and 0.5 mm in length was fabricated as an aluminum-encapsulated form by a specially designed pressing equipment. For the estimation of the radioactivity, neutron self-shielding and ${\gamma}-ray$ self-absorption effects on the measured activity was considered. From this estimation, it is realized that $^{192}Ir$ small-focal sources over 3 Ci activities can be produced from the HANARO. Field performance tests were performed by using a conventional source and the developed source to take images of a computer CPU and a piece of a carbon steel. The small-focal source showed better penetration sensitivity and geometrical sharpness than the conventional source does. It is concluded from the tests that the focal dimension of this source is small enough to maximize geometrical sharpness in the image taking for the close proximity shots, pipeline crawler applications and contact radiography.

Evaluation of Residual Radiation and Radioactivity Level of TRIGA Mark-II, III Research Reactor Facilities for Safe Decommissioning (TRIGA Mark-II, III 연구로 시절의 폐로를 위한 시설의 잔류 방사선/능 평가)

  • Lee, B.J.;Chang, S.Y.;Park, S.K.;Jung, W.S.;Jung, K.J.
    • Journal of Radiation Protection and Research
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    • v.24 no.2
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    • pp.109-120
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    • 1999
  • Residual radiation and radioactivity level in TRIGA Mark-II, III research reactors and facilities at the KAERI Seoul site, which are to be decommissioned, have been measured, analyzed and evaluated to know the current status of radiation and radioactivity level and to establish and to provide the technical requirements for the safe decommissioning of the facilities which shall be applied in minimizing the radiation exposure for workers and in preventing the release of the radioactive materials to the environment. Radiation dose rate and surface radioactivity contamination level on the experimental equipments, floors, walls of the facilities, and the surface of the activated materials within the reactor pool structure were measured and evaluated. Radioactivity and radionuclides in the pool and cooling water were also analyzed. In case of the activated reactor pool structures which are very difficult to measure the radiation and radioactivity level, a computer code Fispin was additionally used for estimation of the residual radioactivity and radionuclides. The radiation and radioactivity data obtained in this study were effectively used as basic data for decontamination and dismantling plan for safe decommissioning of TRIGA Mark-II, III facilities.

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Thermoluminescent Response of Thin LiF:Mg,Cu,Na,Si Detectors to Beta Radiation (얇은 LiF:Mg,Cu,Na,Si 검출기의 베타선장에 대한 TL 반응)

  • Nam, Y.M.;Kim, J.L.;Chang, S.Y.;Cho, H.W.;Kim, H.J.
    • Journal of Radiation Protection and Research
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    • v.24 no.1
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    • pp.39-43
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    • 1999
  • Thermoluminescent (TL) response characteristics of a thin LiF:Mg,Cu,Na,Si Teflon detectors have been studied for use in beta radiation detection. The detectors were fabricated from a mixture of LiF:Mg,Cu,Na,Si phosphor and Teflon powder which was molded into a thin disk form of $50mg/cm^2$ thickness. These detectors were irradiated to beta fields of $^{147}Pm,\;^{204}Tl\;and\;^{90}Sr/^{90}Y$ sources with a covering of Kapton foil ($2mg/cm^2$) and photon irradiation was carried out with a $^{137}Cs$ source at the Korea Atomic Energy Research Institute (KAERI). Batch uniformity was estimated to be 4.7% and the beta dose response presented linear relationship from 0.1 mGy to 100 Gy. The beta energy responses of thin detectors normalized to $^{137}Cs$ were presented as 0.46, 1.09 and 1.06 for $^{147}Pm,\;^{204}Tl\;and\;^{90}Sr/^{90}Y$ beta rays, respectively. The evaluated values for angular responses were $0.93{\pm}0.03\;(^{147}Pm),\;0.94{\pm}0.04\;(^{204}Tl),\;and\;0.92{\pm}0.05\;(^{90}Sr/^{90}Y)$. The results satisfied well a proposed ISO Standard for beta ray dosimeters.

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Cell cycle evaluation of granulosa cells in the $\gamma$-irradiated mouse ovarian follicles (감마선에 조사된 생쥐 난포 과립세포의 세포주기 분석)

  • Kim, Jin-Kyu;Lee, Chang-Joo;Lee, Young-Keun;Song, Kang-Won;Yoon, Yong-Dal
    • Journal of Radiation Protection and Research
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    • v.24 no.1
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    • pp.17-22
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    • 1999
  • This study was carried out to evaluate the biochemical and morphological effects of ionizing radiation on mouse ovarian follicles. Immature mice (ICR, 3 week-old) were irradiated with a dose of $LD_{80(30)}$ at KAERI. The ovaries were collected after 6 hours, 12 hours, 1 day, and 2 days post irradiation. With the morphological basis of the histological staining with hematoxylin-eosin, immunohistochemical preparation using in situ 3'-end labeling was evaluated. Flowcytometric evaluation of DNA extracted from the whole ovary was performed. The percentage of $A_0$ (subpopulation of cells with degraded DNA and with lower DNA fluorescence than $G_0/G_1$ cells), apoptotic, cells in the cell cycle was significantly higher in the irradiated group than in the control group. The number of in situ 3'-end labeled follicles increased at 6 hours post irradiation. All the analyses represented that the ionizing radiation-induced follicular atresia was taken place via an apoptotic degeneration. Such a degeneration underwent very fast and acutely. Therefore, it is concluded that the radiation-induced follicular degeneration is, like the spontaneous atresia, mediated by an acute apoptosis of follicular granulosa cells. Flowcytometric evaluation of cell cycles can make the role for quantifying the atretic follicles and understanding the mechanism of the radiation-induced cell death.

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Development of Phantom for Evaluate the Suitability of Ir-192 HDR Source with Brachytherapy Tools (근접치료용 하나로 생산 Ir-192 선원의 임상기기 적합성평가용 팬톰개발)

  • Shin, Kyo Chul;Choi, Sang Gyu;Kim, Ki Hwan;Son, Kwang Jae;Jeong, Dong Hyeok;Kim, Jeung Kee
    • Progress in Medical Physics
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    • v.24 no.3
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    • pp.171-175
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    • 2013
  • Applicator of various kind of number ten kinds is used to raise from efficiency of brachytherapy to maximum. The compatibility of radiation source and applicator is very important subject for safety brachytherapy. Developed high dose rate brachytherapy source through Hanaro nuclear reactor in Korea Atomic Energy Research Institute and improve compatibility with using equipment in present. In this research, we wished to evaluate stability mechanical safety of radiation source and we developed phantom for evaluate several quality about Ir-192 sealed source that improve newly in Korea Atomic Energy Research Institute and is improved. The result for suitability of Ir-192 HDR source with brachytherapy tools that did normal operation in 2.2~2.7 cm extent about change of equal curvature and consider change of sudden curvature that did normal operation in radius 1.5~1.8 cm extent.