• Title/Summary/Keyword: vertical reactor

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A kinetic study of pyrite in the lime roasting of a vertical cyclone (수직 싸이클론의 ${Ca(OH)}_{2}$ 배소에서 $FeS_{2}$의 열적반응에 관한 연구)

  • 조종상
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.9 no.1
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    • pp.119-125
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    • 1999
  • This research has been studied in terms of investigating the reaction behavior of pyrite with a cyclone reactor. The Mathematical model has developed pyrite oxidation and lime sulfation in this reactor. The model assumes a chemical control shrinking core behavior for the pyrite and a fluid film control shrinking core behavior for the lime. The model was solved and characterized numerically. Experiments have been performed to study the influence of reaction parameters such as reactor temperatures, pyrite particle sizes, air flow rates, feeding rates, and mixing ratio of pyrite and lime. The oxidation and sulfation products were characterized chemically and physically.

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A Conceptual Study of an Air-cooled Heat Exchanger for an Integral Reactor (일체형 원자로의 공랭식 열교환기 개념 연구)

  • Moon, Joo Hyung;Kim, Woo Shik;Kim, Young In;Kim, Myoung Jun;Lee, Hee Joon
    • The KSFM Journal of Fluid Machinery
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    • v.19 no.2
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    • pp.49-54
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    • 2016
  • A conceptual study of an air-cooled heat exchanger is conducted to achieve the long-term passive cooling of an integral reactor. A newly designed air-cooled heat exchanger is introduced in the present study and preliminary thermal sizing is demonstrated. This study mainly focuses on feasibility of an innovative air-cooled heat exchanger to extend the cooling period of the passive residual heat removal system(PRHRS) only in passive manners. A vertical shell-and-tube air-cooled heat exchanger is installed at the top of the emergency cooldown tank(ECT) to collect evaporated steam into condensate, which enables water inventory of the ECT to be kept. Finally, thermal sizing of an air-cooled heat exchanger is presented. The length and the number of tubes required, and also the height of a stack are calculated to remove the designated heat duty. The present study will contribute to an enhancement of the passive safety system of an integral reactor.

ONE-DIMENSIONAL ANALYSIS OF THERMAL STRATIFICATION IN THE AHTR COOLANT POOL

  • Zhao, Haihua;Peterson, Per F.
    • Nuclear Engineering and Technology
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    • v.41 no.7
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    • pp.953-968
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    • 2009
  • It is important to accurately predict the temperature and density distributions in large stratified enclosures both for design optimization and accident analysis. Current reactor system analysis codes only provide lumped-volume based models that can give very approximate results. Previous scaling analysis has shown that stratified mixing processes in large stably stratified enclosures can be described using one-dimensional differential equations, with the vertical transport by jets modeled using integral techniques. This allows very large reductions in computational effort compared to three-dimensional CFD simulation. The BMIX++ (Berkeley mechanistic MIXing code in C++) code was developed to implement such ideas. This paper summarizes major models for the BMIX++ code, presents the two-plume mixing experiment simulation as one validation example, and describes the codes' application to the liquid salt buffer pool system in the AHTR (Advanced High Temperature Reactor) design. Three design options have been simulated and they exhibit significantly different stratification patterns. One of design options shows the mildest thermal stratification and is identified as the best design option. This application shows that the BMIX++ code has capability to provide the reactor designers with insights to understand complex mixing behavior with mechanistic methods. Similar analysis is possible for liquid-metal cooled reactors.

Fabrication and Characterization of Gas-liquid Hybrid Reactor Equipped with Atmospheric Pressure Plasma (기-액 하이브리드 대기압 플라즈마 반응기 제작 및 특성 분석)

  • Kwon, Heoung Su;Lee, Won Gyu
    • Korean Chemical Engineering Research
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    • v.60 no.3
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    • pp.452-458
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    • 2022
  • Three types of gas-liquid hybrid horizontal, vertical and needle-to-cylinder plasma reactors were fabricated. Through these reactors, a high-efficiency, eco-friendly cleaning concept that generates reactive active species generated in atmospheric plasma discharge and gas-liquid activation reaction of cleaning components through the potential difference within the electrode was presented. As a result of comparing the efficiency for cleaning performance, the needle-to-cylinder type reactor had the best characteristics. Through this study, it was confirmed that the gas-liquid hybrid atmospheric pressure plasma reactor has the potential to be applied to ultra-precision cleaning processes such as semiconductor processes.

Techno-economic assessment of a very small modular reactor (vSMR): A case study for the LINE city in Saudi Arabia

  • Salah Ud-Din Khan;Rawaiz Khan
    • Nuclear Engineering and Technology
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    • v.55 no.4
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    • pp.1244-1249
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    • 2023
  • Recently, the Kingdom of Saudi Arabia (KSA) announced the development of first-of-a-kind(FOAK) and most advanced futuristic vertical city and named as 'The LINE'. The project will have zero carbon dioxide emissions and will be powered by clean energy sources. Therefore, a study was designed to understand which clean energy sources might be a better choice. Because of its nearly carbon-free footprint, nuclear energy may be a good choice. Nowadays, the development of very small modular reactors (vSMRs) is gaining attention due to many salient features such as cost efficiency and zero carbon emissions. These reactors are one step down to actual small modular reactors (SMRs) in terms of power and size. SMRs typically have a power range of 20 MWe to 300 MWe, while vSMRs have a power range of 1-20 MWe. Therefore, a study was conducted to discuss different vSMRs in terms of design, technology types, safety features, capabilities, potential, and economics. After conducting the comparative test and analysis, the fuel cycle modeling of optimal and suitable reactor was calculated. Furthermore, the levelized unit cost of electricity for each reactor was compared to determine the most suitable vSMR, which is then compared other generation SMRs to evaluate the cost variations per MWe in terms of size and operation. The main objective of the research was to identify the most cost effective and simple vSMR that can be easily installed and deployed.

INVESTIGATION OF THE CNS HOLE SHAPE AND A PROPOSED INSTALLATION METHOD FOR A VACUUM CHAMBER FOR THE HANARO REACTOR

  • Cho Yeong-Garp;Kim Young-Ki;Lee Kye-Hong;Choung Yun-Hang
    • Nuclear Engineering and Technology
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    • v.38 no.5
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    • pp.455-458
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    • 2006
  • The HANARO reactor has a vertical hole for a cold neutron source (CNS) in the heavy-water reflector tank, i.e., the CNS hole, which was considerably deformed during its welding to the horizontal cold neutron (CN) beam tube. This paper presents an investigation of the form of the CNS hole for the optimal design of the a vacuum chamber for the CNS. In addition, the installation method of the vacuum chamber into the CNS hole for minimizing the water thickness between the vacuum chamber and the nose of the CN beam tube is proposed.

Conceptual Study for the Moderator Selection of the Cold Neutron Source Facility for HANARO

  • Cho, Young-Sik;Jonghwa Chang;Park, Chang-Oong
    • Nuclear Engineering and Technology
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    • v.30 no.2
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    • pp.140-147
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    • 1998
  • Basic concept of a cold neutron source for a 30 MW heavy water moderated reactor (HANARO) is developed. The source is a cold bottle located in a vertical hole near the reactor core. Since the bottle does not have sufficient volume for cooling, the optimum liquid mixture ratio is studied between liquid hydrogen and liquid deuterium. We also studied the variation of the gain depending on the volume of the bottle. The calculation is performed by a coupled MCNP model and by a semi-analytic approach. For the current geometry, 80% liquid deuterium mixture with liquid hydrogen gives the highest gain at 10 A neutron wave.

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Design of Passive Treatment Systems for Mine Drainage Waters

  • Jeen, Sung-Wook
    • Journal of Soil and Groundwater Environment
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    • v.22 no.2
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    • pp.1-9
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    • 2017
  • Passive treatment systems are commonly used for remediation of mine drainage waters because they do not require continuous chemical inputs and operation. In this study, the selection and design criteria for such systems were evaluated, particularly the two most commonly used ones, i.e., permeable reactive barriers (PRBs) and vertical flow biological reactors (VFBRs). PRBs and VFBRs are operated on the same principles in terms of biochemical reaction mechanisms, whereas differences relate to configuration, engineering, and water management. In this study, each of these systems were described with respect to key design variables, such as metal removal mechanisms and removal rates, effectiveness and longevity, general design and construction, flow capacity, and cost. The information provided from this study could be used as a design guideline when a passive treatment option is considered for potential remediation of a mine site.

Analysis and Experiment of VS(Vertical Stabilization) Converter Controller for International Thermonuclear Experimental Reactor (국제 핵융합실험로용 VS(Vertical Stabilization) 컨버터 제어기 해석 및 실험)

  • Jo, Hyunsik;Oh, Jong-Seok;Cha, Hanju
    • Proceedings of the KIPE Conference
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    • 2014.07a
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    • pp.239-240
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    • 2014
  • 본 논문에서는 국제 핵융합실험로용 VS 컨버터 제어기 해석 및 실험에 대하여 서술하였다. VS 컨버터는 플라즈마의 수직 안정성을 제어하기 위해서 ${\pm}1000V$의 정격전압과 최대 ${\pm}25kA$의 전류를 공급해야 하며, 영 전류구간이 없이 4상한 운전을 수행할 수 있어야 한다. 이를 위해서 부하전류의 크기에 따른 동작모드 구분과 순환전류제어기, 차전류 제어기가 요구되며 싸이리스터의 소자 특성에 의하여 발생하는 중복각 보상과 싸이리스터의 전류실패를 방지하는 감마제어가 포함이 된 점호각이 보장 되어야 한다. 본 논문에서는 국제 열핵융합실험로용 VS 컨버터 제어기를 해석하고, 실제 제어기와 RTDS를 연동하여 9ms의 순환전류 제어기 응답성과 계통에 50% 새그가 발생하였을 때 전류실패를 방지하는 감마제어의 타당성을 실험으로 확인하였다.

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Structural Integrity Assessment of the Internal Structure (원전 기기 내부구조물에 대한 구조건전성평가)

  • Lee, Han-Hee;Choi, Jin-Young
    • Proceedings of the KSME Conference
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    • 2007.05b
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    • pp.3497-3500
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    • 2007
  • The internal structure is subjected to dynamic analysis due to the structural integrity. The internal structure shall be installed in the vertical hole call IR1 of reactor core. In order to verify the deflection of the internal structure, the mode and response spectrum analysis of the internal structure was performed. The natural frequency of the internal structure is 11.6 Hz(mode 1 and 2) and deflections of the internal structure are less than values of allowable design (3.2 mm).

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