• Title/Summary/Keyword: $^{235}U$

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SHRIMP U-Pb Zircon Ages of the Gusandong (Kusandong) Tuff in the Cretaceous Gyeongsang Basin (백악기 경상분지 구산동응회암의 SHRIMP 저콘 연대)

  • Kim, Jong-Sun;Cho, Hyeongseong;Kim, Hong-Gyun;Son, Moon
    • The Journal of the Petrological Society of Korea
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    • v.22 no.3
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    • pp.235-249
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    • 2013
  • The Gusandong Tuff (Kusandong Tuff), known as a very significant key bed in the Cretaceous Gyeongsang Basin, is divided into (1) Northern Gusandong Tuff (NKT), (2) Southern Gusandong Tuff (SKT), and (3) Sinsudo Tuff, which were derived from different vents. In order to suggest their more accurate eruption times and to contribute to establishing stratigraphy of the basin, SHRIMP U-Pb zircon ages were determined from the three tuffs. As a result, the virtually same ages of $103.0{\pm}1.2$ Ma and $104.1{\pm}1.3$ Ma were obtained from NKT and SKT, respectively, which mean that they simultaneously erupted during 103~104 Ma. The zircon ages obtained from the Sinsudo Tuff are however divided into two groups i.e. $103.4{\pm}2.1$ and $95.79{\pm}0.98$ Ma. Based on distinctive morphology and cathodoluminescence image of the younger zircons, the younger age, $95.79{\pm}0.98$ Ma, is much more reasonable as the eruption time of the Sinsudo Tuff.

U.S. Policy and Current Practices for Blending Low-Level Radioactive Waste for Disposal (저준위 방사성폐기물의 혼합 관련 미국의 정책과 실제 적용)

  • Kessel, David S.;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.3
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    • pp.235-243
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    • 2016
  • In the near future, many countries, including the Republic of Korea, will face a significant increase in low level radioactive waste (LLW) from nuclear power plant decommissioning. The purpose of this paper is to look at blending as a method for enhancing disposal options for low-level radioactive waste from the decommissioning of nuclear reactors. The 2007 U.S. Nuclear Regulatory Commission strategic assessment of the status of the U.S. LLW program identified the need to move to a risk-informed and performance-based regulatory approach for managing LLW. The strategic assessment identified blending waste of varying radionuclide concentrations as a potential means of enhancing options for LLW disposal. The NRC's position is that concentration averaging or blending can be performed in a way that does not diminish the overall safety of LLW disposal. The revised regulatory requirements for blending LLW are presented in the revised NRC Branch Technical Position for Concentration Averaging and Encapsulation (CA BTP 2015). The changes to the CA BTP that are the most significant for NPP operation, maintenance and decommissioning are reviewed in this paper and a potential application is identified for decommissioning waste in Korea. By far the largest volume of LLW from NPPs will come from decommissioning rather than operation. The large volumes in decommissioning present an opportunity for significant gains in disposal efficiency from blending and concentration averaging. The application of concentration averaging waste from a reactor bio-shield is also presented.

Effect of Korean red ginseng marc fermented by Bacillus subtilis on swine immunity

  • Kim, Hong-Kook;Choe, Yeong-Ho;Kim, Geun-Seop;Kim, Ha-Young;Kim, Byeong-Soo
    • Korean Journal of Veterinary Service
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    • v.41 no.3
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    • pp.141-147
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    • 2018
  • Red ginseng marc is a by-product of Korean red ginseng (panax ginseng CA Meyer) and contains ginsenoside which has pharmacological effects. The Korean red ginseng marc was fermented with Bacillus subtilis (RGMB). This study was carried out to investigate the RGMB effect on swine immunity. The variation of ginsenoside depending on the RGMB fermentation time was analyzed. Swine (Landrace${\times}$Yorkshire) were divided into control group (basic diet) and RGMB group (RGMB 1% diet). One percent RGMB was fed to the RGMB group for 28 days. The biochemical parameters, cytokine and immunoglobulin were analyzed. For 48 hours of fermentation on RGMB, ginsenoside Rb1 had increased 180.94%, Rg3 235.85%. Rg1 wasn't detected before fermentation, but was detected after 48 hours of fermentation. The RGMB had effect of deceasing initial AST concentration $79.33{\pm}12.85U/L$ to $54.00{\pm}14.46U/L$ in final and was significantly lower (P<0.05) than control in final. In final RGMB had significantly lower (P<0.05) ALT concentration of $48.57{\pm}8.26U/L$ comparing with control group of $65.43{\pm}10.31U/L$. RGMB had the effect of significantly decreasing (P<0.05) $IL-1{\beta}$, IL-6 and $TNF-{\alpha}$ concentration of $2.44{\pm}1.31ng/mL$, $0.71{\pm}0.36ng/mL$ and $0.51{\pm}0.21ng/mL$. The IgA concentration had significantly increased (P<0.05) in RGMB group of $0.56{\pm}0.06mg/mL$ in final. These results demonstrate that RGMB has effect of increasing immunity and practicable to use as feed additives on swine.

LOCAL BURNUP CHARACTERISTICS OF PWR SPENT NUCLEAR FUELS DISCHARGED FROM YEONGGWANG-2 NUCLEAR POWER PLANT

  • Ha, Yeong-Keong;Kim, Jung-Suck;Jeon, Young-Shin;Han, Sun-Ho;Seo, Hang-Seok;Song, Kyu-Seok
    • Nuclear Engineering and Technology
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    • v.42 no.1
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    • pp.79-88
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    • 2010
  • Spent $UO_2$ nuclear fuel discharged from a nuclear power plant (NPP) contains fission products, U, Pu, and other actinides. Due to neutron capture by $^{238}U$ in the rim region and a temperature gradient between the center and the rim of a fuel pellet, a considerable increase in the concentration of fission products, Pu, and other actinides are expected in the pellet periphery of high burnup fuel. The characterization of the radial profiles of the various isotopic concentrations is our main concern. For an analysis, spent nuclear fuels originating from the Yeonggwang-2 pressurized water reactor (PWR) were chosen as the test specimens. In this work, the distributions of some actinide isotopes were measured from center to rim of the spent fuel specimens by a radiation shielded laser ablation inductively coupled plasma mass spectrometer (LA-ICP-MS) system. Sampling was performed along the diameter of the specimen by reducing the sampling intervals from 500 ${\mu}m$ in the center to 100 ${\mu}m$ in the pellet periphery region. It was observed that the isotopic concentration ratios for minor actinides in the center of the specimen remain almost constant and increase near the pellet periphery due to the rim effect apart from the $^{236}U$ to $^{235}U$ ratio, which remains approximately constant. In addition, the distributions of local burnup were derived from the measured isotope ratios by applying the relationship between burnup and isotopic ratio for plutonium and minor actinides calculated by the ORIGEN2 code.

The Recent Trends and Policy Issues on Alternative Medicine in the Western Countries: -Focusing on U.S.A.- (서구 각국의 대체의료에 관한 최근동향 -미국을 중심으로-)

  • 유왕근
    • Korean Journal of Health Education and Promotion
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    • v.15 no.2
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    • pp.235-256
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    • 1998
  • Currently, alternative medicine is highly utilized in the western countries. The public as well as health care practitioners have been paying a considerable attention to alternative medicine. This rapid growth in alternative medicine in many western countries suggests a high degree of public dissatisfaction with the limitations of orthodox medicine and concern over the side effects of chemical drugs. There is also a widespread recognition of the growing financial, social and personal cost for orthodox medicine. In addition, there is a growing need for a less fragmented, more participative and humane approach compared with contemporary medicine. Alternative medicine, which is based on holistic approach and lead to less expensive health care, may have the potential to playa significant role in overcoming the limitations of orthodox medicne in the western country. In this context, this study explores the recent trends of research on alternative medicine in western countries, particularly U.S.A. The study can provide us with valuable information on the types, training and education, utilization, insurance coverage, and regulation of alternative medicine in the western countries, thus offer important policy implications for the improvement of the korean health care system.

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Optimization for Novel Glucanhydrolase Production of Lipomyces starkeyi KSM 22 by Statistical Design

  • PARK, JUN-SEONG;BYUNG-HOON KIM;JIN-HA LEE;EUN-SEONG SEO;KAB-SU CHO;HYUN-JUNG PARK;HEE-KYOUNG KANG;SUN-KYUN YOO;MYUNG-SUK HA
    • Journal of Microbiology and Biotechnology
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    • v.13 no.6
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    • pp.993-997
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    • 2003
  • Response surface methodology was applied to find the optimum conditions for the production of DXAMase (containing both dextranase and amylase activities) based on the cultivation variables (pH, temperature, and agitation rate). The experimental values from the model equation conceded with predicted values in which the predicted values for dextranase and amylase activities were 2.26 and 3.52 U/ml at pH 4, $28^{\circ}C$, 235 rpm, and the corresponding experimental values were 2.41 and 3.68 U/ml, respectively.

Isolation and Characterization of Aeromons hydrophila PBl6 and Properties of Synthetic Wastewater Degradation (Protease 생성균 Aeromonas hydrophila PB16의 분리 및 합성폐수처리능)

  • 박형수;양선영;김무훈;이종광;유용호;박두현
    • Korean Journal of Microbiology
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    • v.38 no.4
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    • pp.235-240
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    • 2002
  • Protease producing bacterium, PB16 was isolated from food processing wastewater sludge and paddy field soil samples and selected by the clear zone and enzyme activity test. The isolate was gram negative, rod type and its protease productivity was 6.49 U/ml. As a result of API20NE kit test and 16S rDNA sequencying, the isolated PB16 was identified as Aeromonas hydrophila (99%). The growth rate ($h^{-1}$) was 0.21 in synthetic waste water only and 0.26 in synthetic waste water containing vitamin and mineral using a bioscreen C. Synthetic wastewater removal rate was 59 and 87%, respectively after 1 and 3 day reaction (intial CODcr was 2,472 mg/l).

The influence of strengthening the hollow steel tube and CFST beams using U-shaped CFRP wrapping scheme

  • Zand, Ahmed W. Al;Hosseinpour, Emad;Badaruzzaman, Wan Hamidon W.
    • Structural Engineering and Mechanics
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    • v.66 no.2
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    • pp.229-235
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    • 2018
  • This study investigated the behaviour of the simply supported hollow steel tube (HST) beams, either concrete filled or unfilled when strengthened with carbon fibre reinforced polymer (CFRP) sheets. Eight specimens with varied tubes thickness (sections classification 1 and 3) were all tested experimentally under static flexural loading, four out of eight were filled with normal concrete (CFST beams). Particularly, the partial CFRP strengthening scheme was used, which wrapped the bottom-half of the beams cross-section (U-shaped wrapping), in order to use the efficiency of high tensile strength of CFRP sheets at the tension stress only of simply supported beams. In general, the results showed that the CFRP sheets significantly improved the ultimate strength and energy absorption capacities of the CFST beams with very limited improvement on the related HST beams. For example, the load and energy absorption capacities for the CFST beams (tube section class 1) were increased about 20% and 32.6%, respectively, when partially strengthened with two CFRP layers, and these improvements had increased more (62% and 38%) for the same CFST beams using tube class 3. However, these capacities recorded no much improvement on the related unfilled HST beams when the same CFRP strengthening scheme was adopted.

Effect of DUPIC Cycle on CANDU Reactor Safety Parameters

  • Mohamed, Nader M.A.;Badawi, Alya
    • Nuclear Engineering and Technology
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    • v.48 no.5
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    • pp.1109-1119
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    • 2016
  • Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (CANDU) reactors (DUPIC) cycle is still under investigation, DUPIC cycle is a promising method for uranium utilization improvement, for reduction of high level nuclear waste, and for high degree of proliferation resistance. This paper focuses on the effect of DUPIC cycle on CANDU reactor safety parameters. MCNP6 was used for lattice cell simulation of a typical 3,411 MWth PWR fueled by $UO_2$ enriched to 4.5w/o U-235 to calculate the spent fuel inventories after a burnup of 51.7 MWd/kgU. The code was also used to simulate the lattice cell of CANDU-6 reactor fueled with spent fuel after its fabrication into the standard 37-element fuel bundle. It is assumed a 5-year cooling time between the spent fuel discharges from the PWR to the loading into the CANDU-6. The simulation was carried out to calculate the burnup and the effect of DUPIC fuel on: (1) the power distribution amongst the fuel elements of the bundle; (2) the coolant void reactivity; and (3) the reactor point-kinetics parameters.

A Comparative strudy on the Insulation Performance of the Super Window by Actual Survey and Simulation (초단열 슈퍼윈도우의 단열성능 실측과 시뮬레이션 비교 분석)

  • Kim, Chi-Hoon;Ahn, Byung-Lip;Jang, Cheol-Yong;Hong, Won-Hwa
    • 한국태양에너지학회:학술대회논문집
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    • 2009.11a
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    • pp.231-235
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    • 2009
  • According to flow of energy, the loss occurs through walls, roofs, windows and so on. Among these case, most of the loss that is about 45% occurs through windows. windows's U-value is six times higher than wall's one according to Building code, so the loss through windows accounts for very much rates. Currently, Exterior wall's U-value about building envelope is 0.35~0.58W/ mK, but windows's one is 3.3W/ mK. It means that the loss through windows occupy very much amounts relatively. Therefore, the solution is required to reduce energy loss and increasing displeasure caused by excessive influx of solar energy through windows, to solve the problems Like decoloration on indoor furniture an clothes by harmful ultraviolet rays, air conditioning and increased cost. Therefore, on this paper, Thermal Performance was evaluated through actual test about high insulation Super Window which can improve thermal performance and the Simulation result was compared with actual resul by using Simulation program WINDOW and THERM.

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