• Title/Summary/Keyword: Radiation work

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Web-based QA Workflow System for Radioactive Waste Disposal (방사성 폐기물 처분연구의 QA절차에 따른 웹기반 문서처리 워크플로우 시스템 개발)

  • 김태운;고창성;서대희;이광욱;강철형;황용수;이연명
    • The Journal of Information Systems
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    • v.12 no.1
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    • pp.159-175
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    • 2003
  • During the early stage of radioactive disposal programs, important issues related with quality assurance of data sets, methodologies, R&D procedures are recognized as important ones. This paper focused on the development of web-based workflow standards for the QA procedures of the radioactive waste disposal programs. The flow of process was analyzed based on workflow concepts proposed by the Workflow Management Coalition (WfMC). QA system is based on the principles of T2R3. T2R3 Workflow was used to standardize and restructure the business and/or work process in the industry or organization. The WfMC has identified five functional interfaces to a workflow service as part of its standardization program. They are composed of process definition interface, worklist handler, application program interface, interface between workflows, and system management. The task flow and QA program were defined based on the workflow ideas. QA procedures for the R&D results of radiation disoposal were analyzed following the reference model of workflow. In addition, six program run list were created and implemented. The creation, revision, and approval of the test data were designed to be inplemented on the web environment. Through this system, R&D procedures such as planning, research, documentation, internal review and future independent peer review processes could be well organized and stored more systematically on the database and knowledge base. This will encourage the usage and data sharing between interested parties through it's clear and transparent workflow standards.

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The development of cultural products and textile designs with the patterns of Jeju Choga (제주 초가(草家) 형태를 직물 문양으로 활용한 텍스타일 디자인 및 지역패션문화상품 개발)

  • Yoon, Seong-Hee;Hong, Heesook
    • The Research Journal of the Costume Culture
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    • v.23 no.1
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    • pp.45-62
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    • 2015
  • This study is to develop cultural products based on 'Jeju Choga', which means the traditional houses in Jeju. For the product development, old literature review, field surveys, and consumer surveys were employed. Through old literatures and field surveys, the unique and visual characteristics of Jeju Choga were confirmed: A thatched roof with lattice pattern, a side wall and fences with porous stones, a 'Jungnang' serving as a gate, and a 'Pungchai' preventing strong sola radiation and 'Ollai' meaning a narrow street in front of the Choga. As a results of consumer survey conducted before the development of products, consumers highly recognized and associated Jeju Choga as Jeju representative image. The six basic patterns of Jeju Choga were drawn and eight textile designs were created through the repeated arrangements of the basic patterns. Using the created textile designs and digital printing method, the eleven new fabrics with the patterns of Jeju Choga were developed. The various kinds of ten bags and tow wallets made with the new fabrics. As a result of consumer evaluation for the twelve products made in this study, the scores of preference and purchase intention were above the average work for the most products of them. In particular, the preference and purchase intention of the square shoulder bag, the big-size shopper bag, and the small-size cross bag were very positively evaluated. Therefore, it is confirmed that Jeju Choga could be very useful as a motif for the development of cultural products focusing on Jeju tourism souvenir market.

Development of Monte Carlo Simulation Code for the Dose Calculation of the Stereotactic Radiosurgery (뇌 정위 방사선수술의 선량 계산을 위한 몬테카를로 시뮬레이션 코드 개발)

  • Kang, Jeongku;Lee, Dong Joon
    • Progress in Medical Physics
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    • v.23 no.4
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    • pp.303-308
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    • 2012
  • The Geant4 based Monte Carlo code for the application of stereotactic radiosurgery was developed. The probability density function and cumulative density function to determine the incident photon energy were calculated from pre-calculated energy spectrum for the linac by multiplying the weighting factors corresponding to the energy bins. The messenger class to transfer the various MLC fields generated by the planning system was used. The rotation matrix of rotateX and rotateY were used for simulating gantry and table rotation respectively. We construct accelerator world and phantom world in the main world coordinate to rotate accelerator and phantom world independently. We used dicomHandler class object to convert from the dicom binary file to the text file which contains the matrix number, pixel size, pixel's HU, bit size, padding value and high bits order. We reconstruct this class object to work fine. We also reconstruct the PrimaryGeneratorAction class to speed up the calculation time. because of the huge calculation time we discard search process of the ThitsMap and used direct access method from the first to the last element to produce the result files.

The Construction Status of Fuel Test Loop Facility (핵연료 노내조사시험설비의 시공 현황)

  • Park, Kook-Nam;Lee, Chung-Young;Kim, Hark-Rho;Yoo, Hyun-Jae;Yoo, Seong-Yeon
    • Proceedings of the SAREK Conference
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    • 2007.11a
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    • pp.305-309
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    • 2007
  • FTL(Fuel Test Loop) is a facility that confirms performance of nuclear fuel at a similar irradiation condition with that of nuclear power plant. FTL construction work began on August, 2006 and ended on March, 2007. During Construction, ensuring the worker's safety was the top priority and installation of the FTL without hampering the integrity of the HANARO was the next one. The installation works were done successfully overcoming the difficulties such as on the limited space, on the radiation hazard inside the reactor pool, and finally on the shortening of the shut down period of the HANARO. The Commissioning of the FTL is to check the function and the performance of the equipment and the overall system as well. The FTL shall start operation with high burn up test fuels in early 2008 if the commissioning and licensing progress on schedule.

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Skin photoaging in reconstituted skin culture models (3D 피부세포 배양계를 이용한 피부광노화 연구)

  • 강상진
    • Journal of the Society of Cosmetic Scientists of Korea
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    • v.25 no.2
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    • pp.59-75
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    • 1999
  • Skin is continuously exposed to external stimuli including ultraviolet radiation, which is a major cause of skin photoaging. According to recent discoveries, UVA with a lower energy but deep-penetrating properties, compared to UVB, is likely to play a major part in causing skin photoaging. The clinical and histochemical changes of photoaging are well characterized, but the biochemical mechanisms are poorly understood partly due to the lack of suitable experimental systems. In this work, three-dimensional, reconstituted skin culture models were prepared. After certain period of maturation, the equivalent models were shown to be similar in structure and biochemical characteristics to normal skin. Mature dermal and skin equivalent models were exposed to sub-lethal doses of UVA, and the effects of UVA relevant to dermal photoaging were monitored, including the production of elastin, collagen, collagenase(MMP-1), and tissue inhibitor of metalloproteinases-1 (TIMP-1). Interestingly, dermal and skin equivalents reacted differently to acute and chronic exposure to UVA. Elastin production was increased as soon as one week after commencing UVA irradiation by chronic exposure, although a single exposure failed to do so. This early response could be an important advantage of equivalent models in studying elastosis in photoaged skin. Collagenase activity was increased by acute UVA irradiation, but returned to control levels after repeated exposure. On the other hand, collagen biosynthesis, which was increased by a single exposure, decreased slightly during 5 weeks of prolonged UVA exposure. Collagenase has been thought to be responsible for collagen degeneration in dermal photoaging. However, according to the results obtained in this study, elevated collagenase activity is not likely to be responsible for the degeneration of collagen in dermal photoagig, while reduced production of collagen may be the main reason. It can be concluded that reconstituted skin culture models can serve as useful experimental tools for the study of skin photoaging. These culture models are relatively simple to construct, easy to handle, and are reproducible Moreover the changes of dermal photoaging can be observed within 1-4 weeks of exposure to ultraviolet light compared to 4 months to 2 years for human or animal studies. These models will be useful for biochemical and mechanistic studies in a large number of fields including dermatology, toxicology, and pharmacology.

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Design of a Compact Antenna Array for Satellite Navigation System Using Hybrid Matching Network

  • Lee, Juneseok;Cho, Jeahoon;Ha, Sang-Gyu;Choo, Hosung;Jung, Kyung-Young
    • Journal of Electrical Engineering and Technology
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    • v.13 no.5
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    • pp.2045-2049
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    • 2018
  • An antenna arrays for a satellite navigation systems require more antenna elements to mitigate multiple jamming signals. In order to maintain the small array size while increasing the number of antenna elements, miniaturization technique is essential for antenna design. In this work, an electrically small circular microstrip patch antenna with a 3 dB hybrid coupler is designed as an element antenna, where the 3 dB hybrid coupler can yield the circularly polarized radiation characteristic. The miniaturized element antenna typically has too large capacitance in GPS L1 and GLONASS G1 bands, making it difficult to match with a single stand-alone non-Foster matching circuit (NFMC) in a stable state. Therefore, we propose a new matching technique, referred to as the hybrid matching method, which consists of a NFMC and a passive circuit. This passive tuning circuit manages reactance of antenna elements at an appropriate capacitance without a pole in the operating frequency range. The antenna array is fabricated, and the measured results show a reflection coefficient of less than -10 dB and an isolation of greater than 50 dB. In addition, peak gain of the proposed antenna is increased by 22.3 dB compared to the antenna without the hybrid matching network.

The training system based on virtual environments to protect workers and to prevent incidents and accidents during decommissioning of nuclear facilities (원자력시설 해체 작업자 보호 및 사고 예방을 위한 가상현실 기반의 훈련 시스템)

  • Jeong, KwanSeong;Moon, Jei-Kwon;Choi, Byung-Seon;Yoon, TaeMan
    • Proceedings of the Korean Society of Disaster Information Conference
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    • 2015.11a
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    • pp.294-297
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    • 2015
  • Decommissioning of nuclear facilities should be accomplished by assuring the safety of workers because decommissioning activities of nuclear facilities are under high radioactivity and work difficulty. It is necessary that before decommissioning, the radiation exposure dose of workers has to be evaluated and assessed under the principle of ALARA (as low as reasonably achievable). Furthermore, to improve the proficiency of decommissioning environments, method and system need to be developed. The legacy methods of exposure dose measurement and assessment had the limitations to modify and simulate the exposure dose to workers prior to practical activities because those should be accomplished without changes of working routes under predetermined scenarios. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. It can be concluded that this system is able to protect from accidents and enable workers to improve his familiarization about working environments. It is expected that this system can reduce human errors because workers are able to improve the proficiency of hazardous working environments due to virtual training like real decommissioning situations. In the end, the safety during decommissioning of nuclear facilities will be guaranteed under the principle of ALARA.

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Analysis of Property for White and RGB Multichip LED Luminaire (백색 LED와 RGB 멀티칩 LED 조명장치의 특성 분석)

  • Jeong, Byeong-Ho;Kim, Nam-Oh;Kim, Deog-Goo;Oh, Geum-Gon;Cho, Geum-Bae;Lee, Kang-Yoen
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.23 no.12
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    • pp.23-30
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    • 2009
  • LEDs are increasingly used for many applications including automotive, aviation, display, transportation and special lighting applications. Generally, the RGB multichip LED luminaire applied to signboard, emotional lighting system and display device and the white LED luminaire applied to general lighting system. white LED spectra for general lighting should be designed for high luminous efficacy as well as good color rendering. This paper describes characteristics of LED luminaire white LED and RGB multichip LED. Two type of LED luminaire prototype used experiment physical, electrical and optic test and performance analyzed. RGB multi-chip and phosphor-type white LED luminaire were analyzed by experiment on their color characteristics and luminous efficacy of radiation, distribution curve, and electrical characteristics. Research work is in progress to develop an improved performance for optic and electrical works well for two type of LED luminaires.

LOCAL BURNUP CHARACTERISTICS OF PWR SPENT NUCLEAR FUELS DISCHARGED FROM YEONGGWANG-2 NUCLEAR POWER PLANT

  • Ha, Yeong-Keong;Kim, Jung-Suck;Jeon, Young-Shin;Han, Sun-Ho;Seo, Hang-Seok;Song, Kyu-Seok
    • Nuclear Engineering and Technology
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    • v.42 no.1
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    • pp.79-88
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    • 2010
  • Spent $UO_2$ nuclear fuel discharged from a nuclear power plant (NPP) contains fission products, U, Pu, and other actinides. Due to neutron capture by $^{238}U$ in the rim region and a temperature gradient between the center and the rim of a fuel pellet, a considerable increase in the concentration of fission products, Pu, and other actinides are expected in the pellet periphery of high burnup fuel. The characterization of the radial profiles of the various isotopic concentrations is our main concern. For an analysis, spent nuclear fuels originating from the Yeonggwang-2 pressurized water reactor (PWR) were chosen as the test specimens. In this work, the distributions of some actinide isotopes were measured from center to rim of the spent fuel specimens by a radiation shielded laser ablation inductively coupled plasma mass spectrometer (LA-ICP-MS) system. Sampling was performed along the diameter of the specimen by reducing the sampling intervals from 500 ${\mu}m$ in the center to 100 ${\mu}m$ in the pellet periphery region. It was observed that the isotopic concentration ratios for minor actinides in the center of the specimen remain almost constant and increase near the pellet periphery due to the rim effect apart from the $^{236}U$ to $^{235}U$ ratio, which remains approximately constant. In addition, the distributions of local burnup were derived from the measured isotope ratios by applying the relationship between burnup and isotopic ratio for plutonium and minor actinides calculated by the ORIGEN2 code.

Computational and experimental forensics characterization of weapons-grade plutonium produced in a thermal neutron environment

  • Osborn, Jeremy M.;Glennon, Kevin J.;Kitcher, Evans D.;Burns, Jonathan D.;Folden, Charles M.III;Chirayath, Sunil S.
    • Nuclear Engineering and Technology
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    • v.50 no.6
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    • pp.820-828
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    • 2018
  • The growing nuclear threat has amplified the need for developing diverse and accurate nuclear forensics analysis techniques to strengthen nuclear security measures. The work presented here is part of a research effort focused on developing a methodology for reactor-type discrimination of weapons-grade plutonium. To verify the developed methodology, natural $UO_2$ fuel samples were irradiated in a thermal neutron spectrum at the University of Missouri Research Reactor (MURR) and produced approximately $20{\mu}g$ of weapons-grade plutonium test material. Radiation transport simulations of common thermal reactor types that can produce weapons-grade plutonium were performed, and the results are presented here. These simulations were needed to verify whether the plutonium produced in the natural $UO_2$ fuel samples during the experimental irradiation at MURR was a suitable representative to plutonium produced in common thermal reactor types. Also presented are comparisons of fission product and plutonium concentrations obtained from computational simulations of the experimental irradiation at MURR to the nondestructive and destructive measurements of the irradiated natural $UO_2$ fuel samples. Gamma spectroscopy measurements of radioactive fission products were mostly within 10%, mass spectroscopy measurements of the total plutonium mass were within 4%, and mass spectroscopy measurements of stable fission products were mostly within 5%.