• Title/Summary/Keyword: thermal shield

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A thermal-flow analysis of deaerator floor of power plant for reducing the radiative heat transfer effect (발전소 Deaerator floor의 복사효과 저감을 위한 열유동 해석)

  • Kim, Tae-Kwon;Ha, Ji-Soo;Choi, Yong-Seok
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.17 no.12
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    • pp.476-481
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    • 2016
  • Steam power generation is used to produce electricity through a generator that is connected to a steam turbine. As a result, the surface temperature of the deaerator is $70^{\circ}C$during the summer season, the surface temperature of the storage tank is $67^{\circ}C$, and the air temperature is $50^{\circ}C$. This environment is inappropriate for workers and instruments. Workers adjacent to the deaerator and storage tank in particular feel higher temperatures because of the radiative heat transfer effect. Therefore, we optimized the cooling conditions by computational analysis. Case 1 is the current shape of the power plant, Case 2 has additional insulation, and Case 3 has a radiation shield. Flow is caused by a temperature difference between the heat sources in the wall, and hot air is trapped in the right upper end. Based on the temperature contours and the maximum temperature of the surfaces, Case 2 was found to be the most efficient for reducing radiative heat transfer effects.

Fabrication and Characteristics of Epoxy Resin-Type Based Neutron Shielding Materials (에폭시수지계 중성자 차폐재 제조 및 특성)

  • Cho, Soo-Haeng;Kim, Ik-Soo;Do, Jae-Bum;Ro, Seung-Gy;Park, Hyun-Soo
    • Korean Journal of Materials Research
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    • v.8 no.5
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    • pp.457-463
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    • 1998
  • New neutron shielding materials, KNS-201, KNS-301 and KNS-601 have been fabricated to be used for radioactive material shipping and storage cask. The base materials are a modified and a hydrogenated bisphenol- A type and novolac type epoxy resin, and aluminium hydroxide and boron carbide are added. These shielding materials offer good fluidity at processing, which makes it possible to form this resin shield into complicated geometric shapes such as radioactive material shipping and storage cask. Several measurements were made for the shielding materials to evaluate the thermal and mechanical properties and radiation resistance. The properties of the shielding materials are as follows: onset temperatures 2S7~28$0^{\circ}C$, thermal conductivities 0.9S~1.14W/m. K, thermal expansion coefficients 0.77~1.26x$10_{-6}{\circ}C_{-1}$, combustion characteristics < 80$0^{\circ}C$, ATB(average time of burning) < 5sec, AEB(average extent of burning) < 5mm, tensile strengths 2.5~3.2kg/$\textrm{mm}^2$, compressive strengths 13.2~1S.2kg/$\textrm{mm}^2$, flexural strengths 5.2 -6.4kg/$\textrm{mm}^2$. In general, the concerned properties of KNS-201, KNS-301 and KNS-601 were revealed to be better than those of NS-4- FR. foreign neutron shielding material. It is also observed that the radiation resistance of KNS- 601 was better than those of KNS-201 and KNS-301.

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Prediction of Weld Residual Stress of Narrow Gap Welds (협개선 용접부에 대한 용접잔류응력 예측)

  • Yang, Jun-Seog;Heo, Nam-Su
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.34 no.1
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    • pp.79-83
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    • 2010
  • The conventional welding technique such as shield metal arc welding has been mostly applied to the piping system of the nuclear power plants. It is well known that this welding technique causes the overheating and welding defects due to the large groove angle of weld. On the other hand, the narrow gap welding(NGW) technique has many merits, for instance, the reduction of welding time, the shrinkage of weld and the small deformation of the weld due to the small groove angle and welding bead width comparing with the conventional welds. These characteristics of NGW affect the deformation behavior and the distribution of welding residual stress of NGW, thus it is believed that the residual stress results obtained from conventional welding procedure may not be applied to structural integrity evaluation of NGW. In this paper, the welding residual stress of NGW was predicted using the nonlinear finite element analysis to simulate the thermal and mechanical effects of the NGW. The present results can be used as the important information to perform the flaw evaluation and to improve the weld procedure of NGW.

Development of Temperature Sensor Calibration System Using Cryocooler (극저온 냉동기를 이용한 온도센서 교정시스템 개발)

  • Kim, Myung Su;Choi, Yeon Suk;Kim, Dong Lak
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.37 no.1
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    • pp.87-93
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    • 2013
  • The selection of the temperature sensor in a cryogenic system depends on the temperature range, shape, and accuracy. An accurate temperature sensor is essential for improving the reliability of an experiment. We have developed a calibration system for cryogenic temperature sensors using a two-stage cryocooler. To reduce the heat load, a thermal shield is installed at the first stage with multiple layer insulation (MLI). We have also developed a sensor holder for calibrating more than 20 sensors simultaneously in order to save time and reduce costs. This system can calibrate sensors at variable temperatures via temperature control using a heater. In this paper, we present the design and fabrication of the temperature sensor calibration system and a representative experimental result.

A STUDY ON OXIDATION TREATMENT OF URANIUM METAL CHIP UNDER CONTROLLING ATMOSPHERE FOR SAFE STORAGE

  • Kim, Chang-Kyu;Ji, Chul-Goo;Bae, Sang-Oh;Woo, Yoon-Myeoung;Kim, Jong-Goo;Ha, Yeong-Keong
    • Nuclear Engineering and Technology
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    • v.43 no.4
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    • pp.391-398
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    • 2011
  • The U metal chips generated in developing nuclear fuel and a gamma radioisotope shield have been stored under immersion of water in KAERI. When the water of the storing vessels vaporizes or drains due to unexpected leaking, the U metal chips are able to open to air. A new oxidation treatment process was raised for a long time safe storage with concepts of drying under vacuum, evaporating the containing water and organic material with elevating temperature, and oxidizing the uranium metal chips at an appropriate high temperature under conditions of controlling the feeding rate of oxygen gas. In order to optimize the oxidation process the uranium metal chips were completely dried at higher temperature than $300^{\circ}C$ and tested for oxidation at various temperatures, which are $300^{\circ}C$, $400^{\circ}C$, and $500^{\circ}C$. When the oxidation temperature was $400^{\circ}C$, the oxidized sample for 7 hours showed a temperature rise of $60^{\circ}C$ in the self-ignition test. But the oxidized sample for 14 hours revealed a slight temperature rise of $7^{\circ}C$ representing a stable behavior in the self-ignition test. When the temperature was $500^{\circ}C$, the shorter oxidation for 7 hours appeared to be enough because the self-ignition test represented no temperature rise. By using several chemical analyses such as carbon content determination, X-ray deflection (XRD), Infrared spectra (IR) and Thermal gravimetric analysis (TGA) on the oxidation treated samples, the results of self-ignition test of new oxidation treatment process for U metal chip were interpreted and supported.

Activation Reduction Method for a Concrete Wall in a Cyclotron Vault

  • Kumagai, Masaaki;Sodeyama, Kohsuke;Sakamoto, Yukio;Toyoda, Akihiro;Matsumura, Hiroshi;Ebara, Takayoshi;Yamashita, Taichi;Masumoto, Kazuyoshi
    • Journal of Radiation Protection and Research
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    • v.42 no.3
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    • pp.141-145
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    • 2017
  • Background: The concrete walls inside the vaults of cyclotron facilities are activated by neutrons emitted by the targets during radioisotope production. Reducing the amount of radioactive waste created in such facilities is very important in case they are decommissioned. Thus, we proposed a strategy of reducing the neutron activation of the concrete walls in cyclotrons during operation. Materials and Methods: A polyethylene plate and B-doped Al sheet (30 wt% of B and 2.5 mm in thickness) were placed in front of the wall in the cyclotron room of a radioisotope production facility for pharmaceutical use. The target was Xe gas, and a Cu block was utilized for proton dumping. The irradiation time, proton energy, and beam current were 8 hours, 30 MeV, and $125{\mu}A$, respectively. To determine a suitable thickness for the polyethylene plate set in front of the B-doped Al sheet, the neutron-reducing effects achieved by inserting such sheets at several depths within polyethylene plate stacks were evaluated. The neutron fluence was monitored using an activation detector and 20-g on de Au foil samples with and without 0.5-mm-thick Cd foil. Each Au foil sample was pasted onto the center of a polyethylene plate and B-doped Al sheet, and the absolute activity of one Au foil sample was measured as a standard using a Ge detector. The resulting relative activities were obtained by calculating the ratio of the photostimulated luminescence of each foil sample to that of the standard Au foil. Results and Discussion: When the combination of a 4-cm-thick polyethylene plate and B-doped Al sheet was employed, the thermal neutron rate was reduced by 78%. Conclusion: The combination of a 4-cm-thick polyethylene plate and B-doped Al sheet effectively reduced the neutron activation of the investigated concrete wall.

6H - SiC single crystal growth by sublimation process (승화법에 의한 SiC 단결정 육성)

  • 강승민;오근호
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.5 no.1
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    • pp.50-59
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    • 1995
  • Abstract 6 H - SiC single crystal was grown by sublimation growth system which was self - designed and manufactured. In order that the SiC source might be decomposited and sublimed and deposited on the 6H - seed substrate grown by Acheson method, the temperature gradient, the growth parameters of growth temperature and pressure were operately adjusted. So we could get the optimum temperature gradient inside of the crucible. The graphite crucible with SiC powder and thermal shield componants were purified at the elevated temperature by means of Ar purging process and the source baking, then it distributed to reduce the amount of the impurities come from those parts. It was recognized that the optimum growth temperature of the crucible was$2300~2400^{\circ}C$ at the Ar atmospheric pressure of 200~400 torr, and at that moment the growth rate was 500~1000 $\mu\textrm{m}$. And then, the as- grown crystal was cut with the wafer form, the evaluation about the crystal was carried out by XRD, the optical microscopic observation and FT IR spectrum measurement.

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Post-purchase Evaluation on the Maternity Wear on the Current Korean Market by Survey and Wear test

  • Park, Soon-Jee;Lee, Hee-Jung;Suh, Chu-Yeon
    • Journal of Fashion Business
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    • v.11 no.3
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    • pp.15-34
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    • 2007
  • This study was designed to collect a precise information concerning to the preference and evaluations after usage of pregnant Korean woman for the maternity wear bysurvey and wear tests. Through the survey, 212 respondents were asked to answer what type of maternity wear they prefer and what requirements for maternity wear design are important. According to the results of survey, the mostly preferred maternity wear items were pants and one-piece dress. Korean customers for maternity wear usually pay more for the one-piece dress than other items and they also usually put on medium price pants and low-price blouse. Concerning to the purchase criteria, it may be said that design and movability, fit factors are the buying decision criteria of great weight for Korean pregnant women. Special function most desired was thermal insulation, followed by buffer action, electromagnetic shield and quickly water-absorbent and dry property. Preferred maternity wear design details were flat collar, slightly fitted waist and empire style, gather skirt, rubber band waist. Wear test was performed for two kinds of blouse (BL) and one-piece dress (OP), and threekinds of pants (PT), which have different design details respectively. According to the wear test for ready-to-wear maternity garments, the garment which considers well the characteristics of Korean pregnant women body shape earned much higher score no matter of brands or prices. Generally, high-priced national brands received an excellent evaluation in design aspect, but not satisfied with comfort to move.

Characterization of the Neutron for Linear Accelerator Shielding Wall using a Monte Carlo Simulation (몬테칼로시뮬레이션을 이용한 선형가속기 차폐벽에 대한 중성자 특성 평가)

  • Lee, Dong Yeon;Park, Eun Tae;Kim, Jung Hoon
    • Journal of radiological science and technology
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    • v.39 no.1
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    • pp.89-97
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    • 2016
  • As previous studies to proceed with the evaluation of the radioactive at linear accelerator's shielding concrete wall. And the shielding wall was evaluated the characteristics for the incoming neutron. As a result, the shielding wall is the average amount of incoming neutrons 10 MV 4.63E-7%, 15 MV 9.69E-6%, showed the occurrence of 20 MV 2.18E-5%. The proportion of thermal neutrons of which are found to be approximately 18-33%. The neutron generation rate can be seen as a slight numerical order. However, in consideration of the linear accelerator operating time we can not ignore the effects of neutrons. Accordingly radioactive problem of the radiation shield wall of the treatment room will be this should be considered.

Line-of-Sight Rate for Off-axis Seeker on a 2-axis Gimbal (2축 김발 위에 장착된 비축탐색기를 위한 시선각속도 계산)

  • Kim, Jeong-Hun;Park, Kuk-Kwon;Ryoo, Chang-Kyung
    • Journal of the Korean Society for Aeronautical & Space Sciences
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    • v.47 no.3
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    • pp.187-194
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    • 2019
  • The off-axis Infra-Red(IR) seeker is mounted on the nose cone side of the anti-air high speed missile to alleviate thermal shield effect due to aerodynamic heating. The seeker output can not be regarded as the Line-of-Sight(LOS) rate any more as missile's roll motion to keep the target tracking is associated. In this paper, we propose a method to calculate the LOS rate for off-axis seeker on a 2-axis gimbal. Firstly, true LOS rate equations are analytically derived but not implementable because boresight error rate is not measurable. And then the first order lag approximation to obtain boresight error rate is proposed. The proposed LOS rate calculation method can compensate the coupling effect by considering the rotations of missile and gimbal. The performance of the proposed method is verified via full nonlinear 6-DOF(Degree of Freedom) simulations.