• 제목/요약/키워드: Research Reactors

검색결과 730건 처리시간 0.026초

연구용원자로 원격해체공정의 그래픽 전산모사 (Interactive graphic simulation of research nuclear reactor dismantling process)

  • 박영수;윤지섭;오원진;홍순혁
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
    • /
    • pp.848-851
    • /
    • 1997
  • A graphic simulation program is developed to assimilate the remote dismantling process of research nuclear reactors. This program makes extensive use of a commercial robot graphic instruction program. Firstly, a realistic graphic model of research reactors are built along with various dismantling equipments. Using the graphic instruction languages provided by IGRIP, then, a graphic process simulation program is developed that operates interactively with the user. Consequently, it is made possible for a process designer to visualize an arbitrary dismantling sequence and interactively modify the process. It is expected that the developed system will be utilized as an effective operator aid in both design and execution phases of remote dismantling of research reactor.

  • PDF

Proposed Neural Network Approach for Monitoring Plant Status in Korean Next Generation Reactors

  • Varde, P.V.;Hur, Seop;Lee, D.Y.;Moon, B.S.;Han, J.B.
    • International Journal of Fuzzy Logic and Intelligent Systems
    • /
    • 제3권1호
    • /
    • pp.112-120
    • /
    • 2003
  • This paper reports the development work carried out in respect of a proposed application of Neural Network approach for the Korean Next generation Reactor (KNGR) now referred as APR-1400. The emphasis is on establishing the methodology and the approach to be adopted towards realizing this application in the next generation reactors. Keeping in view the advantages and limitation of Artificial Neural Network Approach, the role of ANN has been limited to plant status or to be more precise plant transient monitoring. The simulation work carried out so far and the results obtained shows that artificial neural network approach caters to the requirements of plant status monitoring and qualifies to be incorporated as a part of proposed operator support systems of the referenced nuclear power plant.

Evaluation of New Design Concepts for Steam Generators in Sodium Cooled Liquid Metal Reactors

  • Kim, Seong-O.;Sim Yoonsub;Kim, Eui-kwang.;Myung-Hwan.Wi;Han, Dohee.
    • Nuclear Engineering and Technology
    • /
    • 제35권2호
    • /
    • pp.121-132
    • /
    • 2003
  • To reduce the construction cost and enhance the safety of sodium cooled liquid metal reactors, various kinds of new design concepts were evaluated using the KALIMER operation condition. The required equipment sizes were set for plant electricity output to be similar to that of KALIMER. The evaluations were made focusing on the plant performance and implementation practicality. Each design concept was evaluated for the concept itself and design impacts to interfacing systems. Through the evaluation of the concepts, it was found that the most favorable design concept is the integrated steam generator with forced convection using lead bismuth as the intermediate heat transfer fluid between the primary sodium tube and feed water/steam tube in the steam generator.

Enantiospecific separation in biphasic Membrane Reactors

  • Giorno, Lidietta
    • 한국막학회:학술대회논문집
    • /
    • 한국막학회 1998년도 추계 총회 및 학술발표회
    • /
    • pp.15-18
    • /
    • 1998
  • Membrane reactors are systems which combine a chemical reactor with a membrane separation process allowing to carry out simultaneously conversion and product separation. The catalyst can be immobilized on the membrane or simply compartmentalized in a reaction space by the membrane. Membrane reactors are today investigated to produce optically pure isomers and/or resolve racemic mixture of enantiomers. The interest towards these systems is due to the increasing demand of enantiomerically pure compounds to be used in the pharmaceutical, food, and agrochemical industries. In fact, enantiomers can have different biological activities, which often influence the efficacy or toxicity of the compound. On the basis of current literature there are basically two schemes on the use of membrane technology to produce enantiomers. In one case, the membrane itseft is intrinsically enantioselective: the membrane is the chiral system which selectively separates the wanted isomer on the basis of its conformation. In the other, a kinetic resolution using an enantiospecific biocatalyst is combined with a membrane separation process; the membrane separates the product from the substrate on the basis of their relative chemical properties (i.e. solubility). This kind of configuration is widely used to carry out kinetic resolutions of low water soluble substrams in biphasic membrane reactors [Giomo, 1995, 1997; Lopez, 1997]. These are systems where enzyme-loaded membranes promote reactions between two separate phases thanks to the properties of enzymes, such as lipases, to catalyse reactions at the org ic/aqueous interface; the two phases are maintained in contact and separated at the membrane level by operating at appropriate transmembrane pressure. A schematic representation of biphasic membrane reactor is shown in figure 1, while an example of enantiospecific reaction and product separation carried out with these systems is reported in figure 2.

  • PDF

Structural Properties of Dielectric Barrier Reactor with Hole (DBH) for CF4 Decomposition

  • Jung Jung Gun;Kim Jong Suk;Park Jae Yoon;Kim Kwang Soo;Rim Geun Hie
    • Transactions on Electrical and Electronic Materials
    • /
    • 제4권4호
    • /
    • pp.30-35
    • /
    • 2003
  • In this paper, the $CF_4$ decomposition efficiency is investigated for three simulated plasma reactors that are needle plate reactor, metal particle reactor, and dielectric barrier reactor with hole (DBH). The$CF_4$ decomposition efficiency by DBH is much better than that by needle plate reactor or metal particle reactor. When applied voltage is increased up to the critical voltage for spark formation in the all reactors, the $CF_4$ decomposition efficiency is increased. The $CF_4$ decomposition efficiency in needle plate reactor and metal particle reactor is about $12\%$ and $22\%$ respectively at applied voltage of 23 kV (consumption power: 110 W) and $CF_4$ concentration of 500 ppm, however, the $CF_4$ decomposition efficiency is more than $95\%$ in case of DBH. DBH should be much better than two reactors investigated for $CF_4$ decomposition.

Xenon in molten salt reactors: The effects of solubility, circulating particulate, ionization, and the sensitivity of the circulating void fraction

  • Price, Terry J.;Chvala, Ondrej;Taylor, Zack
    • Nuclear Engineering and Technology
    • /
    • 제52권6호
    • /
    • pp.1131-1136
    • /
    • 2020
  • Xenon behaves differently in molten salt reactors (MSRs) compared to solid fuel reactors. This behavior needs exploring due to the large reactivity effect of the 135Xe isotope, given the current interest in MSR power plant development for commercial deployment. This paper focuses on select topics in xenon transport, reviews relevant past works, and proposes specific research questions to advance the state of the art in each of the focus areas. Specifically, the paper discusses the issue of xenon solubility in MSRs, the behavior of particulates circulating in MSR fuel salt and its influence on the xenon transport, the possibility of ionization of xenon atoms which changes its effective size and thus affects its mass transport, and finally the issue of circulating void fraction and how it is measured. This work presents specific recommendations for MSR designers to research the limits of Henry's law validity, circulating particulate scrubbers, validity of mass transport coefficients in high radiation fields, and the effects of pump speed on circulating void fraction.

혐기조-간헐포기조-개량조로 구성된 영양소 제거 공정에서 온도의 영향 (Temperature Effect on the Nutrient Removal in the Combined Biological Nutrient Removal System (CBNR) with Anaerobic-Intermittent Aerobic-Modified Oxic Reactors)

  • 강영희;한기봉
    • 한국물환경학회지
    • /
    • 제22권4호
    • /
    • pp.639-647
    • /
    • 2006
  • The temperature effect at $20^{\circ}$ and $10^{\circ}$ on the nutrient removal efficiency was evaluated in the combined biological nutrient removal system (CBNR) with anaerobic-intermittent aerobic-oxic reactors. The test was conducted under the conditions of various ratios of intermittent aeration time and distribution of influent raw water to CBNR. The removal efficiencies of organics, nitrogen and phosphorus were a little bit better at $20^{\circ}$ than at $10^{\circ}$. However the large difference of temperature effect on the nutrient removal efficiency between $20^{\circ}$ and $10^{\circ}$ was not appeared because of highly sustained MLSS concentrations in the reactors and controlled intermittent aeration time. In the removal of phosphorus, Mode III (50/70 min in aeration on/off time, 3 times of intermittent aeration) showed more effective compared with short aeration time of Mode IV. In case of N, P removal, the denitrification rate was lower in Mode A with splitted inflow into anaerobic and intermittent aeration basins than in Mode B with sole inflow into anaerobic basin.

Study of the Design of Data Acquisition and Analysis Systems for Multi-purpose Regional Energy Systems

  • Lee, Han-Sang;Yoon, Dong-Hee;Jang, Gil-Soo;Park, Jong-Keun;Park, Goon-Cherl
    • Journal of Electrical Engineering and Technology
    • /
    • 제5권1호
    • /
    • pp.16-20
    • /
    • 2010
  • Recently, the smart grid has become a hot issue and interest in related power sources have increased accordingly. The implementation of a smart grid can enable many generation resources to be linked to the power system, including small-scale reactors for the purpose of co-generation. Research on small-scale reactors is being carried out all over the world. Similarly, Korea is also conducting research on multi-purpose regional energy systems using nuclear energy. This paper proposes a real-time data acquisition and analysis system for small-scale reactors, and is known as the REX-10 (Regional Energy rX 10 MVA). This analysis requires real-time simulations for the power system since it needs data communication with a remote REX-10. A RTDS (Real Time Digital Simulator) has been used for the simulation, and a SCADA/HMI system interfaced with the RTDS is proposed for the purpose of monitoring and control of the regional energy system.

배치 실험을 이용한 암모니아 제거 기작 및 효율 평가 (Evaluation of Ammonia Removal Mechanisms and Efficiencies Through Batch Experiments)

  • 장지은;강지영;김혜원;신규진;진성욱
    • 한국지하수토양환경학회지:지하수토양환경
    • /
    • 제27권6호
    • /
    • pp.37-46
    • /
    • 2022
  • As the amount of livestock wastewater increases, ammonia contamination in surface water and groundwater is also increasing, and its treatment is urgently needed. In this study, indigenous soil bacteria was utilized for ammonia removal in artificial wastewater and associated removal mechanisms and efficiencies were evaluated. Two batch reactors were configurated to contain natural soil and artificial wastewater at 1:10 mass ratio, and incubated for 84 and 168 hours, respectively. The results showed that ammonia was completely removed within 48 and 72 hours in the first and second reactors, respectively. There were no significant changes in ammonia concentrations in the control groups without soil. Nitrate was formed in the reactors, indicating that the main removal mechanism of ammonia was nitrification by nitrifying bacteria. Nitrate was further converted to nitrogen gas by denitrification in the anaerobic environment, which was caused by consumption of oxygen during the nitrification process.

원자력 열수력 실험 연구의 현황과 미래 - 연구개발 동향 고찰 - (Status and Future of Experimental Study on Nuclear Thermal Hydraulics - A Review of Research and Development Status -)

  • 박군철;전지한
    • 대한기계학회논문집B
    • /
    • 제33권9호
    • /
    • pp.643-657
    • /
    • 2009
  • This paper introduces the current nuclear experimental research activities in KAERI, the unique nuclear research institute in Korea, and the universities in Korea to solve and assess the issues which have been faced in the design of new reactors such as APR1400, SMART, GEN-IV reactors as well as fusion reactor. Also the experimental evaluations of safety for operating nuclear plants have been presented. The nuclear thermalhydraulic experiments performed in such organizations are classified the fundamental test, the separated effect test, and the integral effect test with ATLAS and SNUF. Introduction is deployed according to institutes. Finally, the future works and the direction of research voyage in the nuclear thermal-hydraulic field were suggested.