• 제목/요약/키워드: Radiation Protection Product

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Analysis of University Student Awareness of Radiation Exposures from Consumer Products

  • Kim, SeungHwan;Cho, Kunwoo
    • Journal of Radiation Protection and Research
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    • 제41권1호
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    • pp.57-70
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    • 2016
  • Background: Since the terminology 'radioactive consumer product' is not quite familiar to the public and is often considered as negative and detrimental things, the educational curriculum is essential for establishing reliability of nuclear energy related and for the development of better communication strategy of radiation risk with the public. To provide base data which is valuable for establishing efficient curriculum of education and training about radiation safety, it is necessary to apprehend the different level of awareness of radiation exposures classified by various consumer products. Materials and Methods: On November 2014, a question investigation about asking awareness level of radiation exposure from various consumer products was done for university students who are highly educated. The object students are studied at a four-year-course universities which is located at Daejeon City. Results and Discussion: Although the average awareness level is comparatively low, the awareness of senior students, who major in radiation, nuclear related departments and male students are relatively high. On the other hand, the awareness of freshman, sophomore, junior students, who do not major in radiation, nuclear related departments and female students are relatively low. It is necessary to provide various information to avoid unnecessary concerns and misconceptions about radiation exposure. Conclusion: This paper will be an instrument for efficient establishment of curriculum of education and training related with radiation safety.

방사능 방호 제품에 대한 KOLAS 인증 방안 연구 - 마스크를 중심으로 (Study on KOLAS Certification Approach for Radiation Protection Products - Focusing on Masks)

  • 박남희;여욱현;홍성진
    • 한국재난정보학회 논문집
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    • 제19권4호
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    • pp.815-825
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    • 2023
  • 연구목적: 본 논문은 방사선비상계획구역 내 거주하는 주민의 방사능재난 발생시 대피과정에서 사용할 수 있는 방호제품으로서 마스크를 개발하는 과정에서 KOLAS 인증을 받을 수 있는 방안을 연구하는 것이다. 연구방법: 각종 보고서와 논문, KOLAS 인정기구 및 각종 마스크 홈페이지 자료를 조사하여 연구하였다. 연구결과: 국내 방사능재난방재대책을 수립하여 주민보호조치를 강화하고 있으나 방호제품 보급은 갑상샘방호약품이 유일하다. 방사능재난에 대비하여 마스크와 같은 보조적인 지원용품 보급이 필요하다. 방호마스크를 공인인증할 수 있는 KOLAS 인정 공인기관이 없는 실정이다. 결론: 성능 인증 기준이 있는 마스크의 경우 산업용 방진마스크로 공인시험성적서를 발급받고 인증을 받은 후에 자체 기준으로 일반성적서를 받는 이중 과정을 거쳐서 마스크의 KOLAS 인증이 가능하다.

QUALITY MANAGEMENT SYSTEM FOR NUCLEAR EDUCATION CENTRES

  • Sadagopan, Geetha;Kim, Hyunkee;Son, Miyeon
    • Journal of Radiation Protection and Research
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    • 제37권4호
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    • pp.173-176
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    • 2012
  • Quality Management is a recent phenomenon. This is applied to products or services, with an objective to deliver high quality, reliable, worthy, enduring, product or service. The process is considered to have four main components: quality planning, quality control, quality assurance and quality improvement. Focusing on quality control and quality assurance leads to achieving quality management or ensures that an organization or product is consistent. In this paper, the applicable international standard for learning services and for the organization for education and training (learning service provider) is discussed and also the procedure to implement the management system.

ICRP 기준팬텀 기반의 천연방사성핵종이 포함된 가공제품 사용으로 인한 피폭선량 특성 평가 (Characteristic Evaluation of Exposed Dose with NORM added Consumer Product based on ICRP Reference Phantom)

  • 유도현;이현철;신욱근;최현준;민철희
    • Journal of Radiation Protection and Research
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    • 제39권4호
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    • pp.159-167
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    • 2014
  • 국내에서는 2012년 천연방사성핵종이 포함된 가공제품의 규제를 위해 생활주변방사선 안전관리법이 시행되었지만, 해당 가공제품 사용에 대한 인체 피폭선량을 평가할 수 있는 기초자료나 피폭선량 평가기술이 미비하다. 따라서 본 연구는 사용자 피폭선량을 정량적으로 평가하기 위한 방법을 제안하고, 방사선의 종류 및 에너지에 따른 피폭선량 특성의 확인을 목적으로 한다. 피폭선량 평가를 위해서 몬테칼로 방법을 사용한 Monte Carlo N-Particle Extended (MCNPX) 코드를 통해 International Commission on Radiological Protection (ICRP)의 기준팬텀이 전산모사 되었으며, 대표적 천연방사성핵종인 우라늄 계열에서 발생되는 알파선, 베타선, 감마선의 최소, 중간, 최대 에너지가 선원항으로 사용되었다. 연간 유효선량은 가공제품 사용시간 및 사용위치를 고려한 피폭시나리오를 기반으로 평가되었다. 짧은 비정의 알파선 및 베타선은 대부분의 선량을 피부에 전달한 반면, 감마선은 대부분의 장기에 유사한 선량을 전달하였다. 방사능이 $1Bq{\cdot}g^{-1}$ 인 돌침대에 포함된 천연방사성핵종의 함유율이 10%라고 가정하고 한국인 평균 수면시간인 7시간 50분간 돌침대를 사용하였을 때 최대 연간 유효선량은 알파선, 베타선, 감마선에 대해서 각각 0.0222, 0.0836, $0.0101mSv{\cdot}y^{-1}$로 평가되었다.

RADIOPROTECTIVE EFFECT OF ALGIN-OLIGOSACCHARIDE THROUGH MEASURING CASPASE-3 AND CASPASE-9 IN MICE

  • Choi, Seong-Kwan;Jung, Woon-Kwan;Lee, Kyu-Soo;Jang, Young-Il;Dong, Kyeong-Rae
    • Journal of Radiation Protection and Research
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    • 제32권4호
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    • pp.134-139
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    • 2007
  • In order to find out the Radioprotective effect of algin-oligosaccharide(AOS), this study, with a mouse of which whole frame irradiated by 3 Gy radiation once, measured caspase-3 and caspase-9 amid cell signaling connected to apoptosis in order to observe cell activation. In Caspase-3 and Caspase-9 test for observing cell activation, both of Caspase-3 and Caspase-9 showed highly increased O.D. value in the irradiation control group, while the whole groups treated with algin-oligosaccharide before or after irradiation indicated lower O.D. value than the irradiation control group, especially showed big difference in 7 day's treatment group of before irradiation (P<0.001). It confirmed that Caspase generation was restrained in AOS treatment group. Consequently, this study inquired into the fact that algin-oligosaccharide with superior antioxidant activity performed radiation protection by inducing restraint of Caspase generation and confirmed that natural product with less chemical toxicity was able to be applied as radioprotector.

Development of a Fission Product Transport Module Predicting the Behavior of Radiological Materials during Severe Accidents in a Nuclear Power Plant

  • Kang, Hyung Seok;Rhee, Bo Wook;Kim, Dong Ha
    • Journal of Radiation Protection and Research
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    • 제41권3호
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    • pp.237-244
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    • 2016
  • Background: Korea Atomic Energy Research Institute is developing a fission product transport module for predicting the behavior of radioactive materials in the primary cooling system of a nuclear power plant as a separate module, which will be connected to a severe accident analysis code, Core Meltdown Progression Accident Simulation Software (COMPASS). Materials and Methods: This fission product transport (COMPASS-FP) module consists of a fission product release model, an aerosol generation model, and an aerosol transport model. In the fission product release model there are three submodels based on empirical correlations, and they are used to simulate the fission product gases release from the reactor core. In the aerosol generation model, the mass conservation law and Raoult's law are applied to the mixture of vapors and droplets of the fission products in a specified control volume to find the generation of the aerosol droplet. In the aerosol transport model, empirical correlations available from the open literature are used to simulate the aerosol removal processes owing to the gravitational settling, inertia impaction, diffusiophoresis, and thermophoresis. Results and Discussion: The COMPASS-FP module was validated against Aerosol Behavior Code Validation and Evaluation (ABCOVE-5) test performed by Hanford Engineering Development Laboratory for comparing the prediction and test data. The comparison results assuming a non-spherical aerosol shape for the suspended aerosol mass concentration showed a good agreement with an error range of about ${\pm}6%$. Conclusion: It was found that the COMPASS-FP module produced the reasonable results of the fission product gases release, the aerosol generation, and the gravitational settling in the aerosol removal processes for ABCOVE-5. However, more validation for other aerosol removal models needs to be performed.

The Development of Gamma Energy Identifying Algorithm for Compact Radiation Sensors Using Stepwise Refinement Technique

  • Yoo, Hyunjun;Kim, Yewon;Kim, Hyunduk;Yi, Yun;Cho, Gyuseong
    • Journal of Radiation Protection and Research
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    • 제42권2호
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    • pp.91-97
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    • 2017
  • Background: A gamma energy identifying algorithm using spectral decomposition combined with smoothing method was suggested to confirm the existence of the artificial radio isotopes. The algorithm is composed by original pattern recognition method and smoothing method to enhance the performance to identify gamma energy of radiation sensors that have low energy resolution. Materials and Methods: The gamma energy identifying algorithm for the compact radiation sensor is a three-step of refinement process. Firstly, the magnitude set is calculated by the original spectral decomposition. Secondly, the magnitude of modeling error in the magnitude set is reduced by the smoothing method. Thirdly, the expected gamma energy is finally decided based on the enhanced magnitude set as a result of the spectral decomposition with the smoothing method. The algorithm was optimized for the designed radiation sensor composed of a CsI (Tl) scintillator and a silicon pin diode. Results and Discussion: The two performance parameters used to estimate the algorithm are the accuracy of expected gamma energy and the number of repeated calculations. The original gamma energy was accurately identified with the single energy of gamma radiation by adapting this modeling error reduction method. Also the average error decreased by half with the multi energies of gamma radiation in comparison to the original spectral decomposition. In addition, the number of repeated calculations also decreased by half even in low fluence conditions under $10^4$ ($/0.09cm^2$ of the scintillator surface). Conclusion: Through the development of this algorithm, we have confirmed the possibility of developing a product that can identify artificial radionuclides nearby using inexpensive radiation sensors that are easy to use by the public. Therefore, it can contribute to reduce the anxiety of the public exposure by determining the presence of artificial radionuclides in the vicinity.

Studies on the Physico-chemical Properties of Mixed Radioactive Waste Glass

  • Kim, C.W.;Choi, J.R.;Ji, P.K.;Park, J.K.;Shin, S.W.;Ha, J.H.;Song, M.J.;Hwang, T.W.;Park, S.J.
    • Journal of Radiation Protection and Research
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    • 제29권1호
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    • pp.33-39
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    • 2004
  • In order to vitrify the W1 waste (ion-exchange resin(IER), zeolite, and dry active waste(DAW)) generated from Korean Nuclear Power Plants, a glass formulation development based on waste compositions and production rates was performed. A aluminoborosilicate glass, AG8W1, was formulated to vitrify the W1 waste in an induction cold crucible melter(CCM). The processability, product performance, and economics of the candidate glass were calculated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product quality of the glass such as chemical durability, phase stability, etc. was satisfactory. The vitrification process using the candidate glass was also evaluated to be operated as economically as possible.

STUDY ON THE ELECTRON GENERATION BY A MICRO-CHANNEL PLATE BASED ON EGS4 CALCULATIONS AND THE UNIVERSAL YIELD CURVE

  • Moon, B.S.;Han, S.H.;Kim, Y.K.;Chung, C.E.
    • Journal of Radiation Protection and Research
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    • 제26권3호
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    • pp.177-181
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    • 2001
  • The conversion efficiency of a cesium iodine coated micro-channel plate is studied. We use the EGS4 code to transport photons and generated electrons until their energies become less than 1keV and 10keV respectively. Among the generated electrons, the emission from the secondary electrons located within the escape depth of 56nm from the photo-converter boundary is estimated by integrating the product of the secondary electrons with a probability depending only on their geometric locations. The secondary electron emission from the generated electrons of energy higher than 100eV is estimated by the 'universal yield curve'. The sum of these provides an estimate for the secondary electron yield and we show that results of applying this algorithm agree with known experimental results. Using this algorithm, we computed secondary electron emissions from a micro-channel plate used in a gas electron multiplier detector that is currently being developed at Korea Atomic Energy Research Institute.

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Radio-protective Effects of the Extracts of Various Medicinal Plants against Human Normal Lung Cells

  • Lee, Ke-Yong;Kim, Chang-Han;Cho, Choa-Hyung
    • Natural Product Sciences
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    • 제8권4호
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    • pp.144-146
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    • 2002
  • Rhapontica uniflora, Platycodon grandiflorum and Solanum tuberosum extracts affected the recovery of radiation-induced damage at all tested doses $(15.6,\;31.3,\;62.5\;and\;125\;{\mu}g/ml)$. The survival rate of pretreatment with extracts was increased by 2 times more than its compared with untreated cells. All tested extracts protected the growh-delay of normal cells and haematological parameters from their radiation-induced fall. In tested extracts, Solanum tuberosum was significantly superior to Platycodon grandiflorum and Rhapontica uniflora in radio-protection activity.