• Title/Summary/Keyword: KAERI

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Real-time Environmental Radiation Monitoring System with Automatic Restoration of Backup Data in Site Detector via Communication using Radio Frequency (현장검출기에 저장된 백업데이터를 무선통신방식으로 자동 복원하는 실시간 환경선량 감시 시스템)

  • Lee, Wan-No;Kim, Eun-Han;Chung, Kun-Ho;Cho, Young-Hyun;Choi, Geun-Sik;Lee, Chang-Woo;Park, Ki-Hyun;Kim, Yun-Goo
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.255-261
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    • 2003
  • An environmental radiation monitoring system based on high pressurized ionization chamber has been used for on-line gamma monitoring surrounding the KAERI (Korea Atomic Energy Research Institute), which transmits the dose data measured from ion chamber on the site via radio frequency to a central processing computer and stores the transmitted real-time data. Although communication using radio frequency has several advantages such as effective and economical transmission, storage, and data process, there is one main disadvantage that data loss during transmission often happens because of unexpected communication problems. It is possible to restore the loss data by off-line such as floppy disk but the simultaneous process and display of current data as well as the backup data are very difficult in the present on-line system. In this work, a new electronic circuit board and the operation software applicable to the conventional environmental radiation monitoring system are developed and the automatical synchronization of the ion chamber unit and the central processing computer is carried out every day. This system is automatically able to restore the backup data within 34 hours without additional equipments and also display together the current data as well as the transmitted backup data after checking time flag.

The Effect of Bu-Zhong-Yi-Qi-Tang on Epidermal Melanocytes in Ultraviolet B-irradiated Mice (마우스에서 보중익기탕이 자외선 B 조사에 의한 표피멜라닌세포 변화에 미치는 영향)

  • Lee, Hae-June;Kim, Hwan-Sung;Park, Young-Jong;Kim, Joong-Sun;Moon, Chang-Jong;Kim, Jong-Choon;Bae, Chun-Sik;Jo, Sung-Kee;Kim, Sung-Ho
    • Journal of Radiation Protection and Research
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    • v.33 no.3
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    • pp.87-91
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    • 2008
  • We induced the activation of melanocytes in the epidermis of C57BL/6 mice by ultraviolet B (UVB) irradiation and observed the effect of Bu-Zhong-Yi-Qi-Tang (BZYQT) on the formation, and decrease of UVB-induced epidermal melanocytes. C57BL/6 mice were irradiated by UVB $80\;mJ/cm^2$ (0.5 mW/sec) daily for 7 days, and BZYQT was intraperitoneally or topically applied pre- or post-irradiation. For the estimation of change of epidermal melanocytes, light microscopic observation with dihydroxyphenylalanine (DOPA) stain was performed. Split epidermal sheets prepared from the ear of untreated mice exhibited 11-16 melanocytes/$mm^2$, and one week after UV irradiation, the applied areas show an increased number of strongly DOPA-positive melanocytes with stout dendrites. But intraperitoneal or topical treatment with BZYQT before each irradiation interrupted UVB-induced pigmentation and resulted in a marked reduction in the number of epidermal melanocytes as compared to radiation control skin. The number and size of DOPA-positive epidermal melanocytes were also significantly decreased in intraperitoneally injected or topically applicated group after irradiation with BZYQT at 3rd and 6th weeks after irradiation. The present study suggests the BZYQT as inhibitor of UVB-induced pigmentation and depigmenting agent.

Monitoring System of Rock Mass Displacement and Temperature Variation for KURT using Optical Sensor Cable (광섬유센서케이블을 이용한 지하연구시설의 지반변위 및 온도변화 감시시스템 구축)

  • Kim, Kyung-Su;Bae, Dae-Seok;Koh, Yong-Kwon;Kim, Jung-Yul
    • The Journal of Engineering Geology
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    • v.19 no.1
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    • pp.63-70
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    • 2009
  • The optical fiber cable acting as a sensor was embedded in the underground research tunnel and portal area in order to monitor their stability and the spatial temperature variation. This system includes two types of sensing function to monitor the distributed strain and temperature along the line, where sensor cable is installed, not a point sensing. According to the results of one year monitoring around the KURT, there is no significant displacement or movement at the tunnel wall and portal slope. However, it would be able to aware of some phenomena as an advance notice at the tunnel wall which indicates the fracturing in rockmass and shotcrete fragmentation before rock falls accidently as well as movement of earth slope. The measurement resolution for rock mass displacement is 1 mm per 1 m and it covers 30 km length with every 1m interval in minimum. In temperature, the cable measures the range of $-160{\sim}600^{\circ}C$ with $0.01^{\circ}C$ resolution according to the cable types. This means that it would be applicable to monitoring system for the safe operation of various kinds of facilities having static and/or dynamic characteristics, such as chemical plant, pipeline, rail, huge building, long and slim structures, bridge, subway and marine vessel. etc.

A Study on the Sediment Transport using Radioisotope Tracer (방사성동위원소 추적자를 이용한 표사이동 추적실험)

  • Choi Byung-Jong;Jung Sung-Hee;Kim Jong-Bum;Lee Jong-Sup
    • Journal of Korean Society of Coastal and Ocean Engineers
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    • v.16 no.3
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    • pp.162-170
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    • 2004
  • On the basis of the radiotracer technology and the related equipments which have been developed for its industrial application through the nuclear long-term research project, a radiotracer study on sediment transport was carried out as a part of the development of the radiotracer technology for a coastal environment. The crystalline material doped with iridium having a similar composition and specific gravity as those of the bedload sand collected from the research area was produced by the oxide-route method. A radioisotope container was specially designed to inject the radiotracer from 1 m above the sea bedload without radioactive contamination during the transport from the nuclear reactor at KAERI. The position data from the DGPS and the radiation measurement data were collected concurrently and stored by means of the application software programmed with the LabVIEW of the National Instrument. The position data was reprocessed to represent the real position of the radiation probe under water and not that of the DGPS antenna on board. The time dependency of the spatial distribution of the sediment was studied in the area through three tracking measurements after the iridium glass was injected. This trial application showed the potential of the radiotracer technology as an important role for maintaining and developing the coastal environment in the future.

Structural Safety Analysis Of Rear Door in ACP Hotcell Facility for Spent Fuel Treatment (사용후핵연료 차세대관리 종합공정 실증시설내 후면 차폐문의 구조적 안전성 평가)

  • Kwon, Kie-Chan;Ku, Jeong-Hoe;Lee, Eun-Pyo;Choung, Won-Myung;You, Gil-Sung;Lee, Won-Kyung;Kuk, Dong-Hak;Cho, Il-Je
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.1
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    • pp.77-85
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    • 2006
  • A demonstration facility for an advanced spent fuel conditioning process (ACP) is under construction at KAERI. In this hotcell facility, the rear door is frequently used since all process equipment and materials are taken in and out only through the rear door. Therefore , both the structural safety and stability of the door are essentially required for the safety of ACP facility. In this paper, the finite element analysis has been performed to investigate the structural safety under the impact condition between the rear door and the door frame. Also the possibility of the rear door being tumbled over by the impact force or the inertia force under a sudden stop conditon has been evaluated. The analysis results demonstrate that the structural safety and stability of the rear door are sufficiently assured for both the impact and the accidential stop conditions.

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Building Transparency on the Total System Performance Assessment of Radioactive Repository through the Development of the Cyber R&D Platform; Application for Development of Scenario and Input of TSPA Data through QA Procedures (Cyber R&D Platform개발을 통한 방사성폐기물 처분종합성능평가(TSPA) 투명성 증진에 관한 연구; 시나리오 도출 과정과 TSPA 데이터 입력에서의 품질보증 적용 사례)

  • Seo, Eun-Jin;Hwang, Yong-Soo;Kang, Chul-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.1
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    • pp.65-75
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    • 2006
  • Transparency on the Total System Performance Assessment (TSPA) is the key issue to enhance the public acceptance for a radioactive repository. To approve it, all performances on TSPA through Quality Assurance is necessary. The integrated Cyber R&D Platform is developed by KAERI using the T2R3 principles applicable for five major steps : planning, research work, documentation, and internal & external audits in R&D's. The proposed system is implemented in the web-based system so that all participants in TSPA are able to access the system. It is composed of three sub-systems; FEAS (FEp to Assessment through Scenario development) showing systematic approach from the FEPs to Assessment methods flow chart, PAID (Performance Assessment Input Databases) being designed to easily search and review field data for TSPA and QA system containing the administrative system for QA on five key steps in R&D's in addition to approval and disapproval processes, corrective actions, and permanent record keeping. All information being recorded in QA system through T2R3 principles is integrated into Cyber R&D Platform so that every data in the system can be checked whenever necessary. Throughout the next phase R&D, Cyber R&D Platform will be connected with the assessment tool for TSPA so that it will be expected to search the whole information in one unified system.

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Structural Safety Analysis of Openable Working Table in ACP Hot Cell for Spent Fuel Treatment (사용후핵연료 처리를 위한 ACP 실증시설내 개폐형 작업대의 구조적 안전성 평가)

  • Kwon, Kie-Chan;Ku, Jeong-Hoe;Lee, Eun-Pyo;Choung, Won-Myung;You, Gil-Sung;Lee, Won-Kyung;Cho, Il-Je;Kuk, Dong-Hak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.1
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    • pp.17-24
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    • 2006
  • A demonstration facility for advanced spent fuel conditioning process (ACP) is under construction in KAERI. In this hot cell facility, all process equipments and materials are taken in and out only through the rear door. The working table in front of the process rear door is specially designed to be openable for the efficient use of the space. This paper presents the structural safety analysis of the openable working table, for the normal operational load condition and accidential drop condition of heavy object. Both cases are investigated through static and dynamic finite element analyses. The analysis results show that structural safety of the working table is sufficiently assured and the working table is not collapsed even when an object of 500 kg is dropped from the height of 50 cm.

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Increasing of Thermal Conductivity from Mixing of Additive on a Domestic Compacted Bentonite Buffer (국산 압축벤토나이트 완충재의 첨가제 혼합을 통한 열전도도 향상)

  • Lee, Jong-Pyo;Choi, Heui-Joo;Choi, Jong-Won;Lee, Minsoo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.11 no.1
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    • pp.11-21
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    • 2013
  • The Geyoungju Ca-bentonite with dry density of 1.6 g/$cm^3$ has been considered as a standard buffer material for the disposal of high level waste in KAERI disposal system design. But it had relatively lower thermal conductivity compared with other surrounding materials, that was one of key parameters to limit the increase of the disposal density in the disposal system. In this study, various additives were selected and mixed with the Ca-bentonite in different mixing methods in order to increase the thermal conductivity from 0.8 W/mK to 1.0 W/mK. As an additive, CNT (Cabon Nano Tube), graphite, alumina, CuO, and $Fe_2O_3$ were selected, which are chemically stable and have good thermal conductivity. As mixing methods, dry hand-mixer mixing, wet milling and dry ball mill mixing were applied for the mixing. Above all, the ball mill mixing was proved to be most effective since the produced mixture was most homogeneous and showed higher increase in the thermal conductivity. From this study, it was confirmed that the thermal conductivity for the Geyoungju Ca-bentonite could be improved by adding small amount of highly thermal conductive material to 1.0 W/mk. In conclusion, it was believed that the experimental results will be valuable in the disposal system design if the additive effects on the swelling and permeability on the compact bentonite are also approved in further studies.

An Assessment of Air Sampling Location for Stack Monitoring in Nuclear Facility (원자력시설 굴뚝 내 공기시료채취 위치의 적절성 평가)

  • Lee, JungBok;Kim, TaeHyoung;Lee, JongIl;Kim, BongHwan
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.2
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    • pp.173-180
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    • 2017
  • In this study, air sampling locations in the stack of the Advanced Fuel Science Building (AFSB) at the Korea Atomic Energy Research Institute (KAERI) were assessed according to the ANSI/HPS N13.1-1999 specification. The velocity profile, flow angle and $10{\mu}m$ aerosol particle profile at the cross-section as functions of stack height L and stack diameter D (L/D) were assessed according to the sampling location criteria using COMSOL. The criteria for the velocity profile were found to be met at 5 L/D or more for the height, and the criteria for the average flow angle were met at all locations through this assessment. The criteria for the particle profile were met at 5 L/D and 9 L/D. However, the particle profile at the cross-section of each sampling location was found to be non-uniform. In order to establish uniformity of the particle profile, a static mixer and a perimeter ring were modeled, after which the degrees of effectiveness of these components were compared. Modeling using the static mixer indicated that the sampling locations that met the criteria for the particle profile were 5-10 L/D. When modeling using the perimeter ring, the sampling locations that met the criteria for particle profile were 5 L/D and 7-10 L/D. The criteria for the velocity profile and the average flow angle were also met at the sampling locations that met the criteria for the particle profile. The methodologies used in this study can also be applied during assessments of air sampling locations when monitoring stacks at new nuclear facilities as well as existing nuclear facilities.

The Development and Performance Evaluation of a Cyclone to Remove Hot Particulate from a Contaminated Hot Cell (Hot Cell 내에 오염된 고방사능분진 제거를 위한 사이클론 개발 및 성능평가)

  • Kim Gye-Nam;Won Hui-Jun;Choi Wang-Kyu;Jung Chong-Hun;Oh Won-Zin;Park Jin-Ho
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.3
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    • pp.217-226
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    • 2006
  • The structural and contamination characteristics of hot cells at KAERI were investigated. The SEM results showed that the size of the hot particulate on the inner surface of the hot cell ranged from 0.2 to $10{\mu}m$. It was found that an inlet flow rate of 15 m/sec was suitable for this developed cyclone with a 49 mm optimum vortex finder length. The results showed that the collection efficiency was about 85% for $3{\mu}m$ particles. The collection efficiency didn't show a sharp increase when the inlet flow rate was faster than 15m/sec. When the temperature of the inlet flow gas was increased, the collection efficiency of the cyclone was slightly decreased. The larger the vortex finder length was, the higher the pressure drop in the cyclone was. The cut size diameter decreased with an increment of the Reynolds number. It was established that the flow in the cyclone was a turbulent flow on the basis of the Reynolds number and this turbulent flow caused a pressure drop in the cyclone. $Stk^{1/2}_{50}$ decreased with increasing values of the Reynolds number and it gradually approached a constant value at a higher value of the Reynolds number Namely, $Stk^{1/2}_{50}$ approached approximately 0.045 between 6000 and 8000 of the Reynolds number.

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