• 제목/요약/키워드: reactors

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축방향 직접화염 가열방식 로터리킬른 성능모형 (Performance analysis modeling of axial direction direct flame rotary kiln reactors)

  • 한택진;최상민
    • 한국연소학회:학술대회논문집
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    • 한국연소학회 2013년도 제46회 KOSCO SYMPOSIUM 초록집
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    • pp.59-60
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    • 2013
  • Rotary kiln furnace is one of the most widely used gas-solid reactors in the industrial field. Although the rotary kiln is a versatile system and has different size, approach to the reactor modeling can be generalized in terms of flow motion of the solid and gas phase, heat transfer and chemical reactions on purpose. In this paper, a performance analysis example case of axial direction direct flame rotary kiln is introduced.

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REACTOR PHYSICS CHALLENGES IN GEN-IV REACTOR DESIGN

  • DRISCOLL MICHAEL J.;HEJZLAR PAVEL
    • Nuclear Engineering and Technology
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    • 제37권1호
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    • pp.1-10
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    • 2005
  • An overview of the reactor physics aspects of Generation Four(GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and ecoomics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

재폐로 동작에 따른 초전도 한류기의 회복성능 분석 (Analysis of the Recovery Behavior of SFCL According to Reclosing Operation)

  • 하경훈;조용선;김덕구;최효상
    • 전기학회논문지
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    • 제60권5호
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    • pp.1073-1077
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    • 2011
  • The breaking capacity of circuit breakers could be no more increased in the electric power system. This is because the fault current increases due to continuous increases in electric power demand and facilities. To solve the problem, it is necessary to come up with an alternative. The superconducting fault current limiter (SFCL) has received an attention among various alternatives. The SFCL effectively reduce a fault current in cooperation with a power circuit breaker. A various types of the SFCL are suggested and a study on them have been progressed. As a result of it, the SFCL can be applyed to the electric power system in the near future. But, a study on recovery behaviors of the SFCL is not enough for applying to the electric power system. If the superconducting elements do not completely recover to the superconducting state after fault operation, it might be a breakdown of the superconducting elements due to heavy power burden and it gives an bad influence on the working of other electric devices. Additionally, the distribution power system has reclosing operation such as open-0.3sec-closed/open-3min-closed/open procedure. So we need to study more about improvement of the recovery behaviors of the SFCL. In this paper, we analyzed the recovery behaviors of a flux-coupling type SFCL according to reclosing operation when a single line-to-ground fault occurred and we compared recovery behaviors of the SFCL with and without a neutral line between secondary reactors and superconducting elements. Also, the flux-coupling type SFCL has advantageous for increases of capacity by controlling the variation in turn ratios between two reactors. Consequently, when the number of turns of the secondary reactors increased, the power burden of the superconducting elements was bigger due to the increase of impedances of the secondary reactors. To distribute the power burden, two superconducting elements connected in series and the balanced quenching of the superconducting elements was induced by connecting a neutral line.

중수로원전에서 발생하는 $^{14}C$에 대한 내부피폭 선량평가 프로그램에 관한 예비 조사 (Preliminary Study on the Internal Dosimetry Program for Carbon-14 at Korean CANDU Reactors)

  • 공태영;김희근;박규준;강덕원;이경진;이상구;박성철
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
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    • pp.317-320
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    • 2005
  • 방사선방호 신개념(ICRP-60)이 국내에서 법제화되어 2003년부터 시행됨에 따라 원자력발전소에 대한 보다 엄격해진 방사선방호 기준이 적용되고 있다 특히, 중수로 원자력발전소의 경우 $^{14}C$와 삼중수소로 인한 방사선작업종사자에 대한 방사선 위해가 경수로 원자력발전소보다 상대적으로 의기 때문에 작업종사자의 내부피폭 선량을 정확하게 측정하고 평가하여 내부피폭을 예방하는 노력이 필요하다. 본 보고서에는 중수로 원자력발전소에서 발생된 $^{14}C$의 체내 흡입으로 인한 방사선 작업종사자의 내부피폭 선량평가 방법을 정립하기 위해 예비적으로 $^{14}C$로 인한 인체대사모델을 분석하였고 $^{14}C$에 대한 내부피폭 선량평가 방법을 기술하였다.

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차세대 원자력 시스템용 탄화규소계 세라믹스의 제조와 이온조사 특성 평가 (Fabrication and Ion Irradiation Characteristics of SiC-Based Ceramics for Advanced Nuclear Energy Systems)

  • 김원주;강석민;박경환;;류우석;박지연
    • 한국세라믹학회지
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    • 제42권8호
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    • pp.575-581
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    • 2005
  • SiC-based ceramics are considered as candidate materials for the advanced nuclear energy systems such as the generation IV reactors and the fusion reactors due to their excellent high-temperature strength and irradiation resistance. The advanced nuclear energy systems and their main components adopting ceramic composites were briefly reviewed. A novel fabrication method of $SiC_f/SiC$ composites by introducing SiC whiskers was also described. In addition, the charged-particle irradiation ($Si^{2+}$ and $H^{+}$ ion) into CVD SiC was carried out to simulate the severe environments of the advanced nuclear reactors. SiC whiskers grown in the fiber preform increased the matrix infiltration rate by more than $60\%$ compared to the conventional CVI process. The highly crystalline and pure SiC showed little degradation in hardness and elastic modulus up to a damage level of 10 dpa at $1000^{\circ}C$.

컴퓨터 시뮬레이션을 이용한 간헐폭기 MBR공정에서의 운전온도 변화에 따른 질소제거 성능 평가 (The Evaluation of Temperature Effect on Nitrogen RemovaI at Intermittent MBR System by Computer Simulation)

  • 이병희;박민정
    • 멤브레인
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    • 제22권6호
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    • pp.489-501
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    • 2012
  • 두 개의 간헐반응조, 막분리조, 탈기조로 구성된 생물학적 MBR고도처리 공정에 동일한 유입수량과 수질의 하수가 유입되는 경우 운전 온도 및 SRT (Sludge Retention Time)변화에 따른 질소제거 특성을 컴퓨터 시뮬레이션을 통해 파악하였다. SRT가 25일이고 운전온도가 $25^{\circ}C$인 경우 간헐반응조를 간헐폭기 시키는 경우에 운전온도 $13^{\circ}C$의 59%에서 31%로 질소제거효율이 급격히 떨어지는데, 이는 운전온도 $13^{\circ}C$에 비해서 간헐반응조의 RBO (Readily Biodegradable Organic) 농도가 낮아져서 발생한 현상으로 파악되었다. 운전온도 $25^{\circ}C$에서 SRT를 12.6일로 운전하는 경우 간헐반응조 RBO농도는 증가하고 질소제거 효율은 회복되었다. 간헐반응조를 갖는 MBR시스템에서 SRT와 운전온도가 간헐반응조 RBO농도에 미치는 영향은 좀더 깊게 연구되어야 한다.

Influence of operation of thermal and fast reactors of the Beloyarsk NPP on the radioecological situation in the cooling pond. Part 1: Surface water and bottom sediments

  • Panov, Aleksei;Trapeznikov, Alexander;Trapeznikova, Vera;Korzhavin, Alexander
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.3034-3042
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    • 2022
  • The results of radioecological monitoring of the cooling pond Beloyarsk NPP (Russia) have been presented. The influence of waste technological waters of thermal and fast NPP reactors on the content of artificial radionuclides in surface waters and bottom sediments of the Beloyarsk reservoir has been studied. The long-term dynamics of the specific activity of 60Co, 90Sr, 137Cs and 3H in the main components of the freshwater ecosystem at different distances from the source of radionuclide discharge has been estimated. Critical radionuclides (60Co and 137Cs), routes of their entry and periods of maximum discharge of radioisotopes into the cooling pond have been determined. It is shown that the technology of electricity generation at Beloyarsk NPP, based on fast reactors, has a much smaller effect on the flow of artificial radionuclides into the freshwater ecosystem of the reservoir. During the entire period of monitoring studies, the decrease in the specific activity of radionuclides from NPP origin in surface waters was 4.3-74.5 times, in bottom sediments 10-505 times. The maximum discharge of artificial radionuclides into the reservoir was noted during the period of restoration and decontamination work aimed at eliminating emergencies at the AMB thermal reactors of the first stage of the Beloyarsk NPP.

원자력 사고 안전성 향상을 위한 SiCf/SiC 복합소재 개발 동향 (A Review of SiCf/SiC Composite to Improve Accident-Tolerance of Light Water Nuclear Reactors)

  • 김대종;이지수;천영범;이현근;박지연;김원주
    • Composites Research
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    • 제35권3호
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    • pp.161-174
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    • 2022
  • SiC 섬유강화 복합체는 경수형 원자로의 안전성을 획기적으로 향상시킬 수 있는 사고저항성 핵연료 피복관 소재이다. 지르코늄 합금 피복관 및 금속기반 사고저항성 핵연료 피복관에 비해, 중대 사고 환경에서도 우수한 구조적 안정성을 가지고 부식 속도가 매우 낮아, 사고 시 원자로의 온도를 낮추고 사고 진행을 늦출 수 있다. 본 논문에서는 현재 개발되고 있는 사고저항성 SiC 복합체 핵연료 피복관의 개념 및 가동/사고환경에서의 다양한 특성, 상용화를 위해 해결해야 할 다양한 이슈에 대해서 소개하고자 한다.

Influence of operation of thermal and fast reactors of the Beloyarsk NPP on the radioecological situation in the cooling pond: Part II, Macrophytes and fish

  • Aleksei Panov ;Alexander Trapeznikov;Vera Trapeznikova ;Alexander Korzhavin
    • Nuclear Engineering and Technology
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    • 제55권2호
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    • pp.707-716
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    • 2023
  • The influence of waste technological waters of thermal and fast reactors of Beloyarsk NPP (Russia) on the accumulation of 60Co, 90Sr and 137Cs in macrophytes and ichthyofauna of the cooling pond has been studied. Critical radionuclides, routes of their entry into the ecosystem and periods of maximum discharge of radioisotopes into the cooling pond have been determined. It is shown that the technology of electricity generation at the Beloyarsk NPP, based on fast reactors, has a much smaller effect on the release of artificial radionuclides into the environment. Therefore, during the entire period of monitoring studies (1976-2019), the decrease in the specific activity of radionuclides of NPP origin in macrophytes was 13-25800 times, in ichthyofauna 1.5-44.5 times. The maximum discharge of artificial radionuclides into the Beloyarsk reservoir was noted during the period of restoration and decontamination work aimed at eliminating the emergencies at the AMB reactors of NPP. The factors influencing the accumulation of artificial radionuclides in the components of the freshwater ecosystem of the Beloyarsk cooling pond have been determined, including: the physicochemical nature of radioisotopes, their concentration in surface water, the temperature of the aquatic environment, the trophicity of the reservoir, the species of hydrobionts.

공기부양반응기 내에서의 액체순환속도를 위한 모델 (A Model for Liquid Circulation Velocity in Airlift Reactors)

  • 최근호
    • Korean Chemical Engineering Research
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    • 제61권3호
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    • pp.446-455
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    • 2023
  • 공기부양반응기(airlift reactor) 내의 액체순환속도(liquid circulation velocity)를 예측하기 위한 수학적 모형이 유체순환고리(fluid circulation loop)에 대한 기계적 에너지 수지를 기초로 개발되었다. 그 모형은 90° 방향전환으로 인한 에너지 손실과 반응기의 각 부위에서의 마찰로 인한 에너지 손실 그리고 단면적의 변화로 인한 에너지 손실을 모두 고려하였다. 마찰과 방향전환 그리고 단면적 변화에 의한 손실계수를 각각 고려한 모형이 집중매개변수(lumped parameter)를 사용한 기존의 모형보다 액체순환속도를 더 잘 예측할 수 있었다. 순환액체속도는 추적자펄스방법(tracer pulse method)으로 측정하였다. 개발된 모형은 상하부에 연결관(connecting pipe)을 갖는 외부순환 공기부양반응기에서 얻은 본 연구의 실험 결과의 대부분은 물론이고 다양한 형태의 공기부양반응기에서 얻어진 다른 연구자들의 결과도 ±20%이내의 오차로 잘 예측할 수 있었다. 외부 및 내부순환 공기부양반응기에서 순환유체의 90° 방향전환과 관련된 손실계수에 대한 유용한 실험식을 구하여 액체순환속도를 예측하는 데 사용하였다.