• 제목/요약/키워드: Standard Reactor

검색결과 359건 처리시간 0.027초

NEW EVALUATION METHODS FOR RADIAL UNIFORMITY IN NEUTRON TRANSMUTATION DOPING

  • Kim, Hak-Sung;Lim, Jae-Yong;Pyeon, Cheol-Ho;Misawa, Tsuyoshi;Shiroya, Seiji;Park, Sang-Jun;Kim, Myong-Seop;Oh, Soo-Youl;Jun, Byung-Jin
    • Nuclear Engineering and Technology
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    • 제42권4호
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    • pp.442-449
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    • 2010
  • Recently, the neutron irradiation for large diameter silicon (Si)-ingots of more than 8" diameter is requested to satisfy the demand for the neutron transmutation doping silicon (NTD-Si). By increasing the Si-ingot diameter, the radial non-uniformity becomes larger due to the neutron attenuation effect, which results in a limit of the feasible diameter of the Si-ingot. The current evaluation method has a certain limit to precisely evaluate the radial uniformity of Si-ingot because the current evaluation method does not consider the effect of the Si-ingot diameter on the radial uniformity. The objective of this study is to propose a new evaluation method of radial uniformity by improving the conventional evaluation approach. To precisely predict the radial uniformity of a Si-ingot with large diameter, numerical verification is conducted through comparison with the measured data and introducing the new evaluation method. A new concept of a gradient is introduced as an alternative approach of radial uniformity evaluation instead of the radial resistivity gradient (RRG) interpretation. Using the new concept of gradient, the normalized reaction rate gradient (NRG) and the surface normalized reaction rate gradient (SNRG) are described. By introducing NRG, the radial uniformity can be evaluated with one certain standard regardless of the ingot diameter and irradiation condition. Furthermore, by introducing SNRG, the uniformity on the Si-ingot surface, which is ignored by RRG and NRG, can be evaluated successfully. Finally, the radial uniformity flattening methods are installed by the stainless steel thermal neutron filter and additional Si-pipe to reduce SNRG.

자동차 보호용 수계형 아크릴 점착제의 내성 (Resistant Properties of Water-Borne Acrylic Pressure Sensitive Adhesives for Automobile Protection)

  • 함현식;곽윤철;황재영;안성환;김명수;박홍수;윤철훈;성기천
    • 한국응용과학기술학회지
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    • 제22권3호
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    • pp.289-297
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    • 2005
  • In order to improve resistant properties of water-borne acrylic pressure sensitive adhesives(PSAs) for automobiles, this study was carried out. Removable PSAs for automobiles were synthesized by emulsion polymerization of monomers, n-butyl acrylate(BA), n-butyl methacrylate(BMA), acrylonitrile(AN), acrylic acid(AA) and 2-hydroxyethyl methacrylate(2-HEMA), and AA and 2-HEMA could act as functional monomers for crosslink. Emulsion polymerization was carried out in a semi-batch type reactor. Water resistance, heat resistance, acid resistance, alkali resistance and smoke resistance were examined. As a result, water resistance increased with the amount of BMA, however, the effect of BMA content on the water resistance was insignificant at a range of over 14 wt%. The water resistance also increased with the amount of functional monomers, AA and 2-HEMA. The prepared PSAs satisfied all the standard for automobiles except heat resistance. However, the heat resistance comes nearly up to the standard. Also, acid resistance, alkali resistance and smoke resistance of the prepared PSAs satisfied with the standard.

APR+ 표준상세설계 개발단계에서의 경제성 평가 (An Economic Assessment for APR+ Standard Detailed Design Developing Phase)

  • 하각현;서용표;김만원;김성춘;박선응
    • 에너지공학
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    • 제21권3호
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    • pp.292-300
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    • 2012
  • 한수원 중앙연구원은 2007년부터 정부과제의 하나로 열출력 4361MWt GEN.III+ 원전인 APR+를 개발하고 있다. APR1400에 비해 보다 개선된 안전성과 경제성을 갖는 원전을 개발하기 위해 국내외 건설 중인 원전설계와 해외 개발 중인 ALWR(Advanced Light Water Reactor)의 설계내용 및 후쿠시마 원전사고로부터 도출된 개선사항을 반영하여 한국 실정에도 맞고, 해외 수출형 원전에도 부합되는 신개념원전 설계를 진행하고 있다. 기술개발 2단계인 표준상세설계에서 2회의 경제성 평가가 수행되었다. 2단계 표준상세설계 2차 경제성 평가결과 APR+ N-th호기는 국내석탄화력 1000MWe급 대비 24.6% 경쟁력우위와 해외원전 대비 충분한 경쟁력을 갖는 것으로 평가되었다.

물옥잠을 이용한 수중처리방법에 의한 농공단지 폐수처리에 관한 연구 (Study on the Wastewater Treatment by Floating Aquatic Plant System Using Water Hyacinth for the Industrial Complex in Rural Area)

  • 윤춘경;김형중;류재현;여운식
    • 한국농공학회지
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    • 제39권3호
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    • pp.64-71
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    • 1997
  • Floating aquatic plant system using water hyacinth was applied to examine feasibility as a wastewater treatment system for the industrial complex in rural area. The wastewater from the industrial complex does not likely contain toxic pollutants because the industries which generate wastewater with toxic compounds are not allowed to move in. Pilot plant was installed at Baeksuk Nongkong Danzi in Chunahn-City, Chunchungnam - Do , and field study was performed during summer and fall of 1996. Hydraulic loading rate was 0. $0.19m^3/m^2$.day. The effluent concentration of DO was higher than influent, and it implies that 0.6m depth reactor was reaerated enough to increase DO level. The influent concentration of BOD varied significantly from less than 30 to 120mg/${\ell}$ during the study period, however, effluent concentrations were generally lower than the water quality standard and removal efficiency was up to 85%. The influent concentration of COD also showed wide variation from less than 40 to 160mg/${\ell}$ and effluent concentration was higher than water quality standard when influent concentration was over l00mg/${\ell}$. The influent concentrations of T-N and T-P were lower than water quality standard and no further treatment was required, and these compounds were also removed in the system. Although some improvement and refinement are still required, overall* the floating aquatic plant system was proved to be feasible to apply to treat wastewater from industrial complex in rural area.

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EDS와 나노압입을 이용한 주조 스테인리스강의 열화특성 평가 (Evaluation of the Degradation Characteristics of CF-8A Cast Stainless Steel Using EDS and Nano-indentation)

  • 백승;구재민;석창성
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 추계학술대회
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    • pp.291-296
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    • 2004
  • Cast austenitic stainless steel piping pump, valve casings, and elbows are susceptible to reductions in toughness and ductility because of long term exposure at the operating temperatures in LWR(light water reactor). In this paper, we have measured the material properties of long term aged CF-8A cast stainless steel, accelerated aging at $400^{\circ}C$. These studies have been carried out using Indentation tests(automated ball indentation and nano-indentation) and EDS(energy dispersive spectroscopy). The fracture toughness of CF-8A cast stainless steel was also determined by using standard fracture toughness and Automated Ball Indentation.

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Study on the Adhesive Properties of Polyesters Reinforcing Materials

  • Krump, H.;Hudec, I.;Cernak, M.;Janypka, P.
    • Elastomers and Composites
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    • 제37권3호
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    • pp.192-194
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    • 2002
  • Polyester cord yarns have been treated in an atmospheric-pressure nitrogen plasma reactor in order to enhance their adhesion to rubber. A thin layer or the plasma was generated in the close vicinity of the yam surface using various types or surface discharge. To assess the effect of the plasma treatment on fiber surface properties, the cord thread/rubber matrix adhesion values measured using the untreated and threads cord threads were compared. The static and dynamic adhesion of the cord thread to rubber was characterized by using the standard Henley test. The dynamic adhesion values for the reference and plasma treated fiber were $7,3{\pm}1,2\;N$ and $83,5{\pm}3,5\;N$. The surface properties were investigated by scanning electron microscopy, infrared spectroscopy and electron spin resonance spectroscopy. It is concluded that both polar group interactions and increased surface area of the fibers are responsible for the improved adhesive strength.

칡덩굴을 이용한 남은 음식물의 발효사료화 (Fermented Feeds Production of Garbages using Kudzu Creeper as a Bulking Material)

  • 박진식;장성호;김수생
    • 환경위생공학
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    • 제14권2호
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    • pp.90-95
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    • 1999
  • The study on the fermented feeds production of garbages have been conducted to determine the optimum operation condition. The process variables considered for this study were initial air flow rate and temperature control. The results showed that optimum air requirement was $4{\ell}-air/min{\cdot}kg-$ garbages on dry weight basis which is equal to $0.8{\ell}-air/min{\cdot}kg-$ garbages on the basis of 80% moisture content. The optimum initial temperature control in the reactor was $40^{\circ}C$. Crude fiber content of fermented final byproducts were higher than feedstuffs standard for pig breeding and consequently final byproducts had to mix with single-component feed.

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원전용 분산제어시스템을 이용한 차세대 원전 제어봉 구동장치제어시스템 원형 개발 (Development of KNGR-CEDMCS Prototype Using DCS for Nuclear Power Plant)

  • 천종민;이종무;김춘경;박민국;권순만;신종렬
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2004년도 하계학술대회 논문집 D
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    • pp.2275-2277
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    • 2004
  • Korea Next Generation Reactor(KNGR) is in the midst of being developed and will exceed Korea Standard Nuclear Power Plant(KSNP) economically. Domestic Instrumentation and Control(I&C) systems shall be applied to KNGR and the development of Control Element Drive Mechanism Control System(CEDMCS) considered as an essential part in nuclear I&C system will be dealt with in this paper. The newly developed CEDMCS has the control cabinet using the nuclear Distributed Control System(DCS) made in Korea and the power cabinet produced by our research institute and interfaced with the DCS control cabinet.

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국내 안전등급 배관에 대한 손상사례 분석 (Piping Failure Analysis In Domestic Nuclear Safety Piping System)

  • 최선영;최영환
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 춘계학술대회
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    • pp.617-621
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    • 2003
  • The purpose of this paper is to analyze piping failure trend of safety pipings In domestic nuclear power plants. First, database for the piping failure was constructed with 105 data fields. The database includes plant population data, event data, and service history data. 7 kinds of piping failures in domestic NPPs were investigated. Among the 7 cases, detailed root causes were investigated for 3 cases. The first one is pipe wall thinning in main feedwater pipings of Westinghouse 3 loop type plants. The root cause of the wall thinning was flow accelerated corrosion near welding area. The next one is leak event in chemical and volume control system(CVCS) due to vibration. Some cracks occurred in socket welding area. The events showed that the integrity or socket weld is very vulnerable to vibration. The last one is also a leak event in primary sampling line in Korean standard reactor due to thermal fatigue. Although the structural integrity was not maintained by the events, there was no effect on nuclear safety in the above 3 piping failure eases.

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Energy Calibration for Neutron Capture Resonance of Natural Sm by Using 46-MeV Electron Linear Accelerator

  • Lee, Jae-Hong;Lee, Sam-Yol
    • 한국방사선학회논문지
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    • 제1권2호
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    • pp.31-35
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    • 2007
  • Energy calibration is important to identify accurate neutron capture resonance energy in the neutron TOF (Time-of-Flight) experiment. In present study, the accurate neutron capture resonance energies of natural Sm were measured by using a 46-MeV electron linear accelerator (linac) at the Research Reactor Institute, Kyoto University(KURRI). The BGO spectrometer were adopted for measurement the prompt capture gamma-ray of the sample. To obtain energy calibration curve, resonance energy of a gold sample used as standard resonance energy Mughabghab's data (From neutron resonance parameters data). Previous data (by Mughabghab) of natural Sm sample have been compared with the present result.

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