• Title/Summary/Keyword: blanket

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A Theoretical Model of Critical Heat Flux in Flow Boiling at Low Qualities

  • Kim, Ho-Young;Kwon, Hyuk-Sung;Hwang, Dae-Hyun;Kim, Yongchan
    • Journal of Mechanical Science and Technology
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    • v.15 no.7
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    • pp.921-930
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    • 2001
  • A new theoretical critical heat flux (CHF) model was developed for the forced convective flow boiling at high pressure, high mass velocity, and low quality. The present model for an intermittent vapor blanket was basically derived from the sublayer dryout theory without including any empirical constant. The vapor blanket velocity was estimated by an axial force balance, and the thickness of vapor blanket was determined by a radial force balance for the Marangoni force and lift force. Based on the comparison of the predicted CHF with the experimental data taken from previous studies, the present CHF model showed satisfactory results with reasonable accuracy.

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A Study on the Anaerobic Treatment of the Phenol Wastewater with the Sludge Blanket-Packed Bed Reactor (슬러지-고정상 반응기에서 페놀폐수의 혐기성 처리에 관한 연구)

  • 안재동;박동일;김재우;장인용
    • Journal of Environmental Health Sciences
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    • v.22 no.3
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    • pp.72-80
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    • 1996
  • This study was carried to investigate the biodegradability of phenol wastewater in the sluge blanket-packed bed reactor(SBPBR). The reactor consisted of two regions. The lower region was a sludge blanket of 0.5 m height and the upper region was a packed-bed. The phenol and COD concentration of the effluent, the gas production and the composition of gas were measured to determine the performance of the anaerobic wastewater treatment system as the phenol concentration of the influent was increased from 600 to 1800 mg/l. Stable biodegradation of phenol wastewater could be achieved with the anaerobic treatment system from 600 to 1200 mg/l of the influent phenol concentration. But the SBPBR system was getting more serious at 1800 mg/l of influent phenol concentration. At the steady state of the influent phenol concentration of 600-1200 mg/l, the treatment performance showed the phenol removal efficiency of 94.5~96.3%, the COD removal efficiency of 93.3~96% and the gas production of 4.94~9.64 l/day.

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New Approach to Pressure Control of a Impression Cylinder for Roll Coater (인쇄성능 향상을 위한 롤코터용 임프레션 실린더의 압력 제어)

  • Yun, S.N.;Ham, Y.B.;Park, J.H.
    • Journal of Power System Engineering
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    • v.13 no.3
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    • pp.59-64
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    • 2009
  • This study presents a new approach to pressure control of a impression cylinder for roll coater which is a kind of face pressure control between blanket roll and impression roll. Roll-to-Roll method for printing is a very useful tool for mass production such as RFID elements, smart sensors and solar cell devices. In this study, a decupling control strategy of the roll coater which is a combination of a cylinder system, a dry system and two pressure regulators with two pneumatic cylinders was discussed. Also, the characteristics of component such as a pressure regulator having a pressure reducing function and the movement of a blanket roll and a impression cylinder were analyzed using the Matlab software. From this results, the techniques of a shock and a vibration reduction were suggested.

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Characteristics of a Fusion Driven Transmutation Reactor

  • Hong, B.G.
    • Proceedings of the Korean Vacuum Society Conference
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    • 2012.02a
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    • pp.582-582
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    • 2012
  • Characteristics of a fusion-driven transmutation reactor was investigated. A compact reactor concept is desirable from an economic viewpoint. For the optimal design of a reactor, a radial build of reactor components has to be determined by considering the plasma physics and engineering constraints which inter-relate various reactor components. In a transmutation reactor, design of blanket and shield play a key role in determining the size of a reactor; the blanket should produce enough tritium for tritium self-sufficiency, the transmutation rate of waste has to be maximized, and the shield should provide sufficient protection for the superconducting toroidal field (TF) coil. To determine the radial build of the blanket and the shield, not only a radiation transport analysis but also a burnup calculation were coupled with the system analysis and it allowed the self-consistent determination of the design parameters of a transmutation reactor.

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웨스팅하우스형 V5H 원전 연료 제조를 위한 소결체 장입 장비 개발

  • 공상필;신세용;이용성;황창환;권용복;김풍오
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05b
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    • pp.617-622
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    • 1995
  • 원전 연료는 이산화 우라늄의 원통형 소결체를 지르칼로이 피복관에 장입 시킨 원전 연료봉을 집합체 다발로 조립하여 제조된다. 지금까지 국산 연료에는 연료봉의 전길이에 대하여 일정한 농축도의 소결체가 장입 되도록 설계 및 제조되어 왔다. 그러나 Westinghouse의 V5H 연료에서는 연료봉의 상 하단에 각각 6 인치 길이의 천연 우라늄 소결체가 추가로 장입 되어야 하는 이른바 Axial Blanket 연료 제조 기술을 요구하고 있어서 새로운 장비의 도입 또는 개발이 필요하게 되었다. 기존의 소결체 장입 공정은 Siemens사에서 도입된 기술로써 연료봉 양단에 Axial Blanket을 장전 할 수가 멀게 되어 있다. 따라서 기술적으로 Axial Blanket 연료의 제조가 가능할 뿐 아니라 연료의 제조 건전성을 보다 향상시킬 수 있고 생산성이 우수한 장비를 국내 기술로 국산화 개발하였다.

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A study on Relationship between Pattern wafer and Blanket Wafer for STI-CMP (STI-CMP 공정을 위한 Pattern wafer와 Blanket wafer 사이의 특성 연구)

  • 김상용;이경태;김남훈;서용진;김창일;이우선;장의구
    • Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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    • 1999.05a
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    • pp.211-213
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    • 1999
  • In this paper, we documented the controlling oxide removal amount on the pattern wafer using removal rate and removal thickness of blanket wafer. There was the strong correlation relationship for both(correlation factor:0.7109). So, we could confirm the repeatability as applying for STI CMP process from the obtained linear formular. As the result of repeatability test, the difference of calculated polishing time and actual polishing time was 3.48 seconds based on total 50 lots. If this time is converted into the thickness, it is from 104$\AA$ to 167$\AA$. It is possible to be ignored because it is under the process margin.

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Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

  • Qiang Lian;Simiao Tang;Longxiang Zhu;Luteng Zhang;Wan Sun;Shanshan Bu;Liangming Pan;Wenxi Tian;Suizheng Qiu;G.H. Su;Xinghua Wu;Xiaoyu Wang
    • Nuclear Engineering and Technology
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    • v.55 no.11
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    • pp.4274-4281
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    • 2023
  • Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure. In this paper, the three-dimensional method for thermal-hydraulics/neutronics coupling analysis is developed and applied for the full-scale module of the helium-cooled ceramic breeder tritium breeding blanket (HCCB TBB) designed for China Fusion Engineering Test Reactor (CFETR). The explicit coupling scheme is used to support data transfer for coupling analysis based on cell-to-cell mapping method. The coupling algorithm is realized by the user-defined function compiled in Fluent. The three-dimensional model is established, and then the coupling analysis is performed using the paralleled Coupling Analysis of Thermal-hydraulics and Neutronics Interface Code (CATNIC). The results reveal the relatively small influence of the coupling analysis compared to the traditional method using the radial fitting function of internal heat source. However, the coupling analysis method is quite important considering the nonuniform distribution of the neutron wall loading (NWL) along the poloidal direction. Finally, the structure optimization of the blanket is carried out using the coupling method to satisfy the thermal requirement of all materials. The nonlinear effect between thermal-hydraulics and neutronics is found during the blanket structure optimization, and the tritium production performance is slightly reduced after optimization. Such an adverse effect should be thoroughly evaluated in the future work.

저형상비 토카막 중성자원에 기반한 핵변환로 형상 연구

  • Hong, Bong-Geun
    • Proceedings of the Korean Vacuum Society Conference
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    • 2016.02a
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    • pp.414.2-414.2
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    • 2016
  • The optimal configuration of a transmutation reactor based on a low aspect ratio tokamak is determined using coupled analysis of tokamak systems and neutron transport. The inboard radial build of the reactor components is obtained from plasma physics and engineering constraints, while outboard radial builds are mainly determined by constraints on a neutron multiplication, a tritium-breeding ratio, and a power density. It is shown that a breeding blanket model has an impact on the radial build of a transmutation blanket. A burn cycle has to be determined to limit a fast neutron fluence of a plasma facing material below a radiation damage limit.

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Denitrification of the wastewater containing nitrate by various hydrogen donor addition (각종 수소공여체의 첨가에 의한 $NO_3^--N$ 함유 폐수의 탈질)

  • Kim, Hyeong-Seok;Eun, Jong-Keug;Park, Seung-Cho
    • Journal of Environmental Science International
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    • v.4 no.3
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    • pp.229-237
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    • 1995
  • This study was investigated with denitrification of wastewater containing nitrate using upflow sludge blanket process. Contents of this study were the NO3--N removal efficiency by various hydrogen donor addition, determination of optimum COD/$NO_3^--N$ ratio and characteristics of granular sludge.

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Denitrification of the wastewater containing nitrate by various hydrogen donor addition (각종 수소공여체의 첨가에 의한 $NO_3^--N$ 함유 폐수의 탈질)

  • Kim, Hyeong-Seok;Eun, Jong-Keug;Park, Seung-Cho
    • Journal of Environmental Science International
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    • v.4 no.3
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    • pp.77-77
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    • 1995
  • This study was investigated with denitrification of wastewater containing nitrate using upflow sludge blanket process. Contents of this study were the NO3--N removal efficiency by various hydrogen donor addition, determination of optimum COD/$NO_3^--N$ ratio and characteristics of granular sludge.