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Development and Application of the Visual Test Instrument for Spent CANDU Fuel Bundle Serial Number Identification (CANDU형 사용후 핵연료 다발 일련번호 확인을 위한 육안검사 장치 개발 및 적용)

  • Na, Won-Woo;Lee, Young-Gil;Yoon, Wan-Ki;Kwack, Eun-Ho;Park, Seung-Sik
    • Journal of the Korean Society for Nondestructive Testing
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    • v.19 no.2
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    • pp.93-99
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    • 1999
  • SCAI(spent CANDU fuel bundle serial number identifier) was developed to read serial numbers of spent fuel bundles in the spent fuel storage. For the purpose of effectively identifying the serial number of fuel bundle. SCAI was composed of underwater camera & light part. guiding & supporting part and control & monitor part. So it is easy to assemble and disassemble, and operate. It was tested to read serial numbers of spent fuel bundles loaded in basket during the recent spent fuel transfer campaign at Wolsong Unit 1. And it was also applied to read serial numbers of spent fuel bundles discharging from the initial core at Wolsong Unit 3 by slight change of camera and light. Inspectors could easily operate SCAI after several practices in the storage pond, which was a user friendly. And SCAI provided clear and immediate picture for identification of serial numbers of spent fuel bundles. It was interally evaluated that SCAI greatly contributed to cut inspection efforts for national and international safeguards at Wolsong power plant.

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Effect of Vanadium Oxide Loading on SCR Activity and $SO_2$ Resistance over $TiO_2$-Supported $V_2O_5/TiO_2$ Commercial De-NOx Catalysts (상용 $V_2O_5/TiO_2$ 촉매의 바나듐 함량이 SCR 반응성과 $SO_2$ 내구성에 미치는 영향)

  • Park, Kwang Hee;Cha, Wang Seog
    • Applied Chemistry for Engineering
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    • v.23 no.5
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    • pp.485-489
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    • 2012
  • We investigated vanadium (V) loading effects on selective catalytic reduction (SCR) activity and $SO_2$ resistance using commercial SCR catalysts applied on a power plant and incinerator with different amounts of V loading. These catalysts were characterized using XRD, Raman, ICP, BET analysis and found to contain $TiO_2$ (anatase) supported $V_2O_5$ added $WO_3$ and $SiO_2$. The SCR activity of the catalysts increased by increasing either the $V_2O_5$ or the $WO_3$ loading amounts; the SCR activity of the catalysts added $WO_3$ is higher than that of $WO_3$-free catalysts. As the V loading amount in the catalyst increased, the $SO_2$ durability decreased. The $V_2O_5$ supported $TiO_2$ catalyst added $WO_3$ and $SiO_2$ inhibits the deactivation process by $SO_2$. The $SO_2$ resistance of catalysts added $SiO_2$ is higher than that of catalysts added $WO_3$.

Gasification Characteristics to $^{14}CO_2\;of\;^{14}C$ Radionuclide Desorbed from Spent Resin by Phosphate Solutions (월성 원전발생 폐수지로부터 제거된 $^{14}C$ 핵종의 인산용액을 이용한 $^{14}CO_2$로의 기체화 특성)

  • Yang, Ho-Yeon;Won, Jang-Sik;Choi, Young-Ku;Park, Geun-Il;Kim, In-Tae;Kim, Kwang-Wook;Song, Kee-Chan;Park, Hwan-Seo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.4
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    • pp.311-320
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    • 2006
  • Removal characteristics of $H^{14}CO_3$ ion from IRN-150 mixed resin contaminated with $^{14}C$ radionuclide and a gasification behavior of $^{14}C$ radionuclide to $^{14}CO_2$ were investigated. The stripping solutions used for the removal of $^{14}C$ from spent resin were $NaNO_3,\;Na_3PO_4,\;NH_4H_2PO_4,\;H_3PO_4$. The influence of stripping solution concentration on the desorption characteristics of inactive $HCO_3$ ion into stripping solution from IRN-150 mixed resin and the gasification of this ion to $CO_2$ was analyzed. The gasification behavior to $CO_2$ by using NaOH, $HNO_3$, HCl was also compared to that of phosphate solution. Real spent resin stored in Wolsung nuclear power plant was used to evaluate the gasification characteristics of $^{14}C$ radionuclide to $^{14}CO_2$. Gamma radionuclides such as $^{137}Cs,\;^{60}Co$ in residual striping solutions after desorption experiment were analyzed.

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Consideration of Carbon dioxide Capture and Geological Storage (CCS) as Clean Development Mechanism (CDM) Project Activities: Key Issues Related with Geological Storage and Response Strategies (이산화탄소 포집 및 지중저장(CCS) 기술의 청정개발체제(CDM)로의 수용 여부에 대한 정책적 고찰: 지중저장과 관련된 이슈 및 대응방안)

  • Huh, Cheol;Kang, Seong-Gil;Ju, Hyun-Hee
    • Journal of the Korean Society for Marine Environment & Energy
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    • v.14 no.1
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    • pp.51-64
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    • 2011
  • Carbon dioxide Capture and Storage (CCS) is one of the key players in greenhouse gas (GHG) reduction portfolio for mitigating climate change. CCS makes simultaneously it possible not only to reduce a huge amount of carbon dioxide directly from the emission sources (e.g., coal power plant) but also to maintain the carbon concentrated-energy and/or industry infrastructure. Internationally, the United Nations Framework Convention on Climate Change (UNFCCC) is dealing the agenda for considering the possibility of including CCS project as one of Clean Development Mechanism (CDM) projects. Despite its usefulness, however, there are the controversies in including CCS as the CDM project, whose issues include i) non-permanence, including long-term permanence, ii) measuring, reporting and verification (MRV), iii) environmental impacts, iv) project activity boundaries, v) international law, vi) liability, vii) the potential for perverse outcomes, viii) safety, and ix) insurance coverage and compensation for damages caused due to seepage or leakage. In this paper, those issues in considering CCS as CDM are summarized and analyzed in order to suggest some considerations to policy makers in realizing the CCS project in Korea in the future.

The Survey of High School Students' Concern Levels on Decision-making Problems based on Biology (생물영역에서 고등학생의 의사결정 문제에 대한 관심도 조사)

  • Hong, Jung-Lim;Chang, Nam-Kee
    • Journal of The Korean Association For Science Education
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    • v.19 no.1
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    • pp.1-7
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    • 1999
  • The purpose of this study was to survey the high school students' concern levels on decision-making problems based on biology, This study is a exploratory research to develop teaching strategies and curriculum of the common science for the enhancement of the students' decision-making ability in problems involved biological knowledges. The survey subjects were 101 first graders of the high school in Seoul area. The survey instrument developed was 5-point scale of Likert type consisted of 24 question items. The survey results showed that the concern level on selection of method for learning was the highest. The concern levels on selection of method for sports or diet which are the individual faced problems were high, and concern levels on the problems social issued such as decisions about standard for noise, pros and cons of approval for brain death or artificial abortion were high, too. The students' concern levels on problems individual context were significantly higher than concern levels on problems social context (p<0.01). The males' concern levels were higher than females' on 'AIDS', 'incinerator for rubbish', 'atomic power plant', 'protection policy for decreasing species', 'standard for noise' (p<0.05), And the males' concern levels were higher than females' on domain of 'ecosystem and environment pollution'. But the females had higher concern levels than males on 'diet' and 'surrogate mother' (p<0.05). The analyzed results were discussed in respects of implication for teaching strategies and curriculum.

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Trial Burns of Low-Level Radioactive Wastes the Demonstration-Scale Incineration Plant at KAERI (한국원자력 연구소 실증소각시설에서의 저준위방사성폐기물 시험소각)

  • Yang, Hee-Chul;Kim, In-Tae;Kim, Jeong-Guk;Kim, Joon-Hyung;Seo, Yong-Chil
    • Nuclear Engineering and Technology
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    • v.27 no.5
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    • pp.767-774
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    • 1995
  • Behavior of radionuclides such $^{60}$ Co, $^{54}$ Mn and $^{137}$ Cs in the incineration Process was Studied by trial burns of simulated wastes with radio-isotope tracers. Behavior of nonvolatiles, $^{60}$ Co and $^{54}$ Mn, was similar to that of particulate matters in the process. Decontamination factors(DFs) for $^{60}$ Co and $^{54}$ Mn were 4.7$\times$10$^{5}$ and 6.2$\times$10$^{5}$ , respectively. Behavior of semivolatile radio-isotope, $^{137}$ Cs, was temperature dependent. DFs for $^{l37}$Cs at In different incineration temperature of 85$0^{\circ}C$ and $700^{\circ}C$ were 2.8$\times$10$^3$ and 2.6$\times$10$^4$, respectively. Trial bums of dry active waste(DAW) transported from nuclear power station(NPS) Kori 3,4 were also performed. DF for gross $\beta$/${\gamma}$ radioactivity in DAW was 1.1$\times$10$^{5}$ . This was a little higher than the estimated value, which was calculated from the tracer test results and nuclides distribution in the DAW. Average emission concentration was 0.019 Bq/N $m^3$, which could meet the maximal permissible concentration(MPC) in stack emission.n.

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Simulation of Plume Length Induced by Orimulsion Combustion (오리멀젼 연소시 발생하는 백연의 연기거리 전산모사)

  • Kwak, Byoung-Kyu;Kim, Jong-Ho;Joo, Ji-Bong;Lee, Jeong-Jin;Kim, Jin-Soo;Kim, Young-Hun;Yi, Jong-Heop
    • Clean Technology
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    • v.14 no.2
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    • pp.136-143
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    • 2008
  • The objective of this study is to investigate the visibility of plume at the Y power plant stack, which fires the orimulsion as a fuel. The plume contains numerous primary particles under $1\;{\mu}m$ size and inorganic ions possibly inferred by the chemicals of secondary aerosol formation. We evaluated the visibility of the plume using the modified PLUVUE-II model. The monitoring data on the particle size distribution (PSD) and secondary aerosols of sulfate were applied to estimate and evaluate the main factors of plume opacity. The chemical reactions were applied to the model for the secondary aerosol formation of $(NH_4)_2SO_4(s)$. The maximum plume length was estimated by an optic method using threshold contrast. The results showed that the plume length was strongly dependent upon the PSD and $(NH_4)_2SO_4(s)$ concentration of the plume emitted from the stack.

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The Effects of Thermal Degradation and Creep Damage on the Microstructure and Composition of the Carbides in the CrMo Steels for Power Plant (발전 설비용 CrMo강의 탄화물 구조와 조성 변화에 미치는 열화 및 크리프 손상의 영향)

  • Ju, Yeon-Jun;Hong, Gyeong-Tae;Lee, Hyeon-Ung;Sin, Dong-Hyeok;Kim, Je-Won
    • Korean Journal of Materials Research
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    • v.9 no.10
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    • pp.1018-1024
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    • 1999
  • The effects of operating temperature and stress on degradation of components in high temperature steam generator were investigated. Several 2.25CrlMo tubes which had operated over 20 years and an unused 9CrlMoVNb tube were tested. For the former samples, the amount of $\textrm{M}_{6}\textrm{C}$ carbide and its size are increased with the aging or operating time. The precipitation behavior of carbides ($\textrm{M}_{2}\textrm{O}$, $\textrm{M}_{6}\textrm{C}$) is changed with the operating temperature of the tubes. However, unused 9CrlMoVNb samples show a different carbide precipitation process due to high chromium, vanadium, and niobium contents. The amount of Cr-rich $\textrm{M}_{23}\textrm{C}_{6}$ carbide is significantly increased with aging time, but that of $\textrm{M}_{6}\textrm{C}$ type carbide is rarely changed with aging time at elevated temperatures.

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A Study on Microstructure and Mechanical Properties of Modified 9Cr-1Mo and 9Cr-0.5Mo-2W Steels for nuclear Power Plant (원자력용 개량 9Cr-1Mo 및 9Cr-0.5Mo-2W 강의 미세조직과 기계적 특성 연구)

  • Kim, Seong-Ho;Song, Byeong-Jun;Han, Chang-Seok;Guk, Il-Hyeon;Ryu, U-Seok
    • Korean Journal of Materials Research
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    • v.9 no.11
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    • pp.1137-1143
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    • 1999
  • Microstructure and mechanical properties of Mod.9Cr-1Mo and W added 9Cr-0.5Mo2W steels were investigated for liquid metal reactor (LMR) heat exchange tube. The tempering temperatures at which cell structure was formed were $700^{\circ}C$ for Mod.9Cr-1Mo steel and $750^{\circ}C$ for W added 9Cr0.5Mo-2W steel. indicating the recovery of dislocation was delayed by the addition of W. 9Cr-0.5Mo-2W steel had the same kinds of precipitates with Mod.9Cr-1Mo steel, but the W was included in the precipitates in 9Cr-0.5Mo-2W steel. Micro-hardness and ultimate tensile strength of 9Cr-0.5Mo-2W steel were higher than those of Mod.9Cr-1Mo steel. The impact property of Mod.9Cr-1Mo steel was superior to that of 9Cr-0.5Mo-2W steel.

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Preparation of Pt Catalysts for 2-propanol Dehydrogenation using Sol-gel Method (솔-젤법을 이용한 2-propanol 탈수소화 반응 Pt 촉매의 제조)

  • Lee, Yeong-Kweon;Lee, Hwaung;Song, Hyung Keun;Na, Byung-Ki
    • Korean Chemical Engineering Research
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    • v.45 no.4
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    • pp.328-334
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    • 2007
  • Chemical heat pump system of 2-propanol/acetone/hydrogen is most suitable to the recovery of waste heat of power plant. various types of 5 wt% Pt-alumina catalysts were prepared for 2-propanol dehydrogenation using sol-gel method. The characteristics and the dehydrogenation reaction rate of each catalyst were investigated. Pt-alumina xerogel catalyst has excellent reaction rate and good durability in comparison with the existing alumina supported Pt catalysts. Pt-alumina aerogel catalyst had the highest reaction rate in all prepared catalysts, but sufficient aging time was necessary to maintain its reaction rate. A potential advantage of the aerogel catalyst is the fact that the high temperature heat treatment is not required. Without heat treatment or with low temperature heat treatment, the Pt-alumina aerogel catalyst has excellent reaction rate as well as durability and this gives us the economic advantage. Alumina xerogel supported Pt catalyst prepared by incipient wetness method showed good reaction rate, and had good mechanical strength. Blank alumina xerogel prepared by sol-gel method can be used for the support of metal catalysts.