• 제목/요약/키워드: direct water quenching

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보론강 판재 핫스탬핑시 직수분사냉각 공정의 적용성 (The Application of Direct Water Quenching Process in Hot Stamping of Boron Steels)

  • 박현태;권의표;임익태
    • 한국재료학회지
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    • 제29권12호
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    • pp.818-824
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    • 2019
  • In this study, the direct water quenching technique is applied to validate the applicability of direct water quenching as a cooling method in the hot stamping process of 3.2 mm thick boron steel sheet. Cooling performance of conventional die quenching and direct water quenching is compared. Higher cooling rate is obtained by hot stamping with direct water quenching compared to die quenching. As the flow rate of cooling water increases, the cooling rate increases, and a high cooling rate of 71 ℃/s is achieved under flow rate conditions of 0.8 L/min. Through direct water quenching, the cooling time required for sufficient cooling of the sheet is reduced. Full martensitic microstructure is obtained under flow rate condition of 0.8 L/min. Hardness increases with increasing flow rate. From these results, it is verified that the direct water quenching is applicable to the hot stamping of thick boron steel sheet.

3.2t 보론강 판재 직수냉각 핫스탬핑시 냉각수 유량에 따른 미세조직 및 기계적 특성 (Microstructure and Mechanical Properties of Hot-Stamped 3.2t Boron Steels according to Water Flow Rate in Direct Water Quenching Process)

  • 박현태;권의표;임익태
    • 한국재료학회지
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    • 제30권12호
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    • pp.693-700
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    • 2020
  • Direct water quenching technique can be used in hot stamping process to obtain higher cooling rate compared to that of the normal die cooling method. In the direct water quenching process, setting proper water flow rate in consideration of material thickness and the size of the area directly cooled in the component is important to ensure uniform microstructure and mechanical properties. In this study, to derive proper water flow rate conditions that can achieve uniform microstructure and mechanical properties, microstructure and hardness distribution in various water flow rate conditions are measured for 3.2 mm thick boron steel sheet. Hardness distribution is uniform under the flow condition of 1.5 L/min or higher. However, due to the lower cooling rate in that area, the lower flow conditions result in a drastic decrease in hardness in some areas in the hot-stamped part, resulting in low martensite fraction. From these results, it is found that the selection of proper water flow rate is an important factor in hot stamping with direct water quenching process to ensure uniform mechanical properties.

MAJOR THERMAL-HYDRAULIC PHENOMENA FOUND DURING ATLAS LBLOCA REFLOOD TESTS FOR AN ADVANCED PRESSURIZED WATER REACTOR APR1400

  • Park, Hyun-Sik;Choi, Ki-Yong;Cho, Seok;Kang, Kyoung-Ho;Kim, Yeon-Sik
    • Nuclear Engineering and Technology
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    • 제43권3호
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    • pp.257-270
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    • 2011
  • A set of reflood tests has been performed using ATLAS, which is a thermal-hydraulic integral effect test facility for the pressurized water reactors of APR1400 and OPR1000. Several important phenomena were observed during the ATLAS LBLOCA reflood tests, including core quenching, down-comer boiling, ECC bypass, and steam binding. The present paper discusses those four topics based on the LB-CL-11 test, which is a best-estimate simulation of the LBLOCA reflood phase for APR1400 using ATLAS. Both homogeneous bottom quenching and inhomogeneous top quenching were observed for a uniform radial power profile during the LB-CL-11 test. From the observation of the down-comer boiling phenomena during the LB-CL-11 test, it was found that the measured void fraction in the lower down-comer region was relatively smaller than that estimated from the RELAP5 code, which predicted an unrealistically higher void generation and magnified the downcomer boiling effect for APR1400. The direct ECC bypass was the dominant ECC bypass mechanism throughout the test even though sweep-out occurred during the earlier period. The ECC bypass fractions were between 0.2 and 0.6 during the later test period. The steam binding phenomena was observed, and its effect on the collapsed water levels of the core and down-comer was discussed.

보리 유식물에 처리한 수은의 분포 및 독성 연구 (Toxic Effects and Distribution of Mercury in Barley Seedlings)

  • 이춘환;장호식
    • 한국환경과학회지
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    • 제1권1호
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    • pp.13-21
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    • 1992
  • The inhibitory effects of mercury ions on the growth of barley seedlings were studied and the distribution of metal elements in the organs of treated plants was investigated by using synchrotron radiation induced X-ray emission (SRIXE). Although the treatment of mercury ions caused growth inhibition, the mercury-specific increase in variable fluorescence and the abolishment of energy-dependent quenching in broken barley chloroplasts as shown by Moon et at. (1992) were not observed in the leaves of growth-inhibited seedlings. Instead the treatment of mercury decreased Fmax and Fo values. However, Fmax/Fo ratio and photochemical and nonphotochemical quenching coefficients were not affected significantly. By SRIXE analysis of $10\mu\textrm{m}$ mercury chloride treated seedlings, accumulation of mercury in roots was observed after 1 hour of treatment and similar concentration was sustained for 48 hours. Relative contents of mercury was high in roots and underground nodes where seeds were attachedl but was very low in leaves. Iron and zinc were also distributed mainly in the lower parts of the seedlings. However after 72 hours of treatment the contents of these metals in roots decreased and their distribution became more uniform, which may lead to death of the plants. These results suggest that the observed inhibitory effects on barley seedlings upto 48 hours after the treatment is not due to direct damages in the photosynthetic apparatus, but due to its accumulation in roots and the consequent retardation of the growth of barley seedlings. The decrease in Fmax and Fo is probably due to the decrease in chlorophyll and protein contents caused by the retardation of growth. The observed slow expansion of primary leaves could be also explained by the retardation of growth, but the fluorescence induction pattern from the leaves did not show characteristic symptoms of leaves under water stress.

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응축탱크로 방출되는 안정된 증기제트 응축모델 (Modeling on the Condensation of a Stable Steam Jet Discharging into a Quenching Tank)

  • 김환열;하광순;배윤영;박종균;최상민
    • 에너지공학
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    • 제10권4호
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    • pp.349-356
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    • 2001
  • 물과 증기의 직접접촉에 의한 응축 열전달은 움직이는 증기/물 경계면에서 열 및 물질 전달이 이루어지는 현상으로서, 매우 큰 열전달계수를 수반하는 특징이 있기 때문에 이를 응용한 설계가 산업계에서 광범위하게 이루어지고 있다. 본 연구에서는 단일 수평 배관을 통해 과냉각수가 있는 응축탱크로 안정된 증기제트가 방출될 때, 증기제트 형상을 예측하는 간단한 응축해석모델을 제시하였다. 해석모델은 축대칭 좌표계에서 질량, 운동량 및 에너지 방정식과 증기/물 경계면에서 의 응축 특성을 고려한 열평형 방정식을 사용하여 유도하였다. 증기/물 경계에서의 매우 큰 열전달율은 기존의 실험을 근거로 한 유효열전도계수에 의해 반영되었다. 해석결과는 실험결과와 비교하였고, 제시된 해석 모델은 실험에서 관찰된 바와 같이 증기 질량유속과 수조 온도가 증가할수록 증기제트 크기(반경 및 길이)가 증가하는 경향을 보였다.

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CORIUM COOLABILITY UNDER EX-VESSEL ACCIDENT CONDITIONS FOR LWRs

  • Farmer, Mitchell T.;Kilsdonk, Dennis J.;Aeschlimann, Robert W.
    • Nuclear Engineering and Technology
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    • 제41권5호
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    • pp.575-602
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    • 2009
  • In the wake of the Three Mile Island accident, vigorous research efforts were initiated to acquire a basic knowledge of the progression and consequences of accidents that involve a substantial degree of core degradation and melting. The primary emphasis of this research was placed on containment integrity, with: i) hydrogen combustion-detonation, ii) steam explosion, iii) direct containment heating (DCH), and iv) melt attack on the BWR Mark-I containment shell identified as energetic processes that could lead to early containment failure (i.e., within the first 24 hours of the accident). Should the core melt fail the reactor vessel, then non-condensable gas production from Molten Core-Concrete Interaction (MCCI) was identified as a mechanism that could fail the containment by pressurization over the long term. One signification question that arose as part of this investigation was the effectiveness of water in terminating an MCCI by flooding the interacting masses from above, thereby quenching the molten core debris and rendering it permanently coolable. Successful quenching of the core melt would prevent basemat melt through, as well as continued containment pressurization by non-condensable gas production, and so the accident progression would be successfully terminated without release of radioactivity to the environment. Based on these potential merits, ex-vessel corium coolability has been the focus of extensive research over the last 20 years as a potential accident management strategy for current plants. In addition, outcomes from this research have impacted the accident management strategies for the Gen III+LWR plant designs that are currently being deployed around the world. This paper provides: i) an historical overview of corium coolability research, ii) summarizes the current status of research in this area, and iii) highlights trends in severe accident management strategies that have evolved based on the findings from this work.

Elucidation of photo-induced electron transfer in a loop-forming peptide: Dye-Ala-Gly-Gln-Tyr

  • Lee, Hwiin;Kim, Jeongyun;Kwon, Yong-Uk;Lee, Minyung
    • Rapid Communication in Photoscience
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    • 제4권3호
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    • pp.59-62
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    • 2015
  • We investigated photo-induced electron transfer (PET) in a dye-labeled peptide, fluorophore-Ala-Gly-Gln-Tyr, employing time-resolved fluorescence. As an effort to develop new functional dyes, we studied an acriflavine derivative for the electron-acceptor in the excited state from tyrosine, an electrondonor in the ground-state. The pH dependence of the fluorescence lifetime of the model peptide indicates that electron transfer between the excited dye and tyrosine occurs when the tyrosine is deprotonated. The proton-coupled electron transfer appears to be sequential rather than concerted. We also report direct time measurements on the end-to-end loop formation processes of the peptide in water.

Microstructure and Fracture Path of Cr-Mn-N Steel upon Aging Treatment

  • Lee, Se-Jong;Sung, Jang-Hyun;Ralls, K.M.
    • 열처리공학회지
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    • 제4권3호
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    • pp.21-30
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    • 1991
  • Microstructural analysis was conducted to observe the effect of aging treatments in a Cr-Mn austenitic stainless steel containing nitrogen, and the amount, size, shape and distribution of precipitates were investigated. It was found that on water quenching from $1000^{\circ}C$ after holding 3 h at that temperature, the steel contained no precipitates observable by optical microscopy. Precipitation of phases begins at places most favorable for the formation of nuclei-in the boundaries of grains and twins. Precipitates were studied in detail by means of scanning electron microscopy (SEM) and transmission electron microscopy (TEM). Chemical compositions of precipitates were examined by the use of scanning transmission electron microscopy (STEM) together with an energy dispersive X-ray (EDX) microanalysis. Also chromium depletion adjacent to grain boundary precipitates was investigated by the use of Auger electron spectroscopy (AES) for a direct examination of the fracture surface chemistry.

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