• Title/Summary/Keyword: 인수기준

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동물약계

  • 한국동물약품협회
    • 동물약계
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    • no.19
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    • pp.4-4
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    • 1995
  • 1. 제조업 허가취소 2. 제조업 소재지변경 3. 요건확인 세부요령 공고 4. 배합사료제조용 동물약품첨가사용기준 개정의견 수렴 5. 가축질병 병성감정 실시기관 지정 6. 롱메리유의 사노피동물약품 인수 7. 배합사료 제조용 동물약품 잠정사용조치 8. 전문위원회 개최 9. 가축전염병 발생정보

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1985~1994 세계 농약 메이저들의 10년간의 성(盛)과 쇠(衰)

  • 한국농약공업협회
    • Agrochemical news magazine
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    • v.16 no.6 s.129
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    • pp.68-70
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    • 1995
  • 지난 10년간 세계 농약산업을 이끌어온 농약메이저들간에 많은 변화가 있어왔다. 기업간의 합병, 인수와 미국달러(US$\$$)를 기준으로 한 매출액 순위도 매우 심한 변화를 보여왔다. 최근 농약전문지인 는 창간 10주년을 맞아 발간한 특집부록에서 1985년부터 94년까지 10년간 세계 농약 메이저회사들의 매출액 순위를 분석, 그들의 성쇠(盛衰)를 평가해 놓았다. 전문을 번역 소개한다.

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Evaluation of X-ray System for Nondestructive Testing on Radioactive Waste Drums (방사성폐기물 드럼 비파괴 검사를 위한 X-ray 장비 평가)

  • Park, Jong-Kil;Maeng, Seong-Jun;Lee, Yeon-Ee;Hwang, Tae-Won
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.6 no.3
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    • pp.189-203
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    • 2008
  • The physical and chemical properties of radioactive waste drums, which have been temporarily stored on site, should be characterized before their shipment to a disposal facility in order to prove that the properties meet the acceptance guideline. The investigation of NDT(Nondestructive Test) method was figured out that the contents in drum, the quantitative analysis of free standing water and void fraction can be examined with X-ray NDT techniques. This paper describes the characteristics of X-ray NDT such as its principles, the considerations for selection of X-ray system, etc. And then, the waste drum characteristics such as drum type and dimension, contents in drum, etc. were examined, which are necessary to estimate the optimal X-ray energy for NDT of a drum. The estimation results were that: $(R)\acute{A}$ the proper X-ray energy is under 3 MeV to test the drums of 320 ${\beta}\S$ and less; $(R)\ddot{E}$ both X-ray systems of 450 keV and/or 3 MeV might be needed considering the economical efficiency and the realization. The number of drums that can be tested with 450 keV and 3 MeV X-ray system was figured out as 42,327 and 18,105 drums (based on storage of 2006. 12), respectively. Four testing scenarios were derived considering equipment procurement method, outsourcing or not, etc. The economical and feasibility assessment for the scenarios was resulted in that an optimal scenario is dependent on the acceptance guide line, the waste generator's policy on the waste treatment and the delivery to a disposal facility, etc. For example, it might be desirable that a waste generator purchases two 450 keV mobile system to examine the drums containing low density waste, and that outsourcing examination for the high density drums, if all NDT items such as quantitative analysis for 'free standing water' and 'void fraction', and confirmation of contents in drum have to be characterized. However, one 450 keV mobile system seems to be required to test only the contents in 13,000 drums per year.

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A Performance Evaluation of Diagnostic Display System by AAPM TG18 (AAPM TG18에 의한 진단용 CRT 디스플레이 시스템의 성능 평가)

  • Kim, H.J.;Jung, H.J.;Min, D.K.;Hong, J.O.;Kim, Y.N.
    • Korean Journal of Digital Imaging in Medicine
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    • v.6 no.1
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    • pp.9-18
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    • 2003
  • 디지털 영상 검출기와 디스플레이 기술의 발달과 의료영상전달시스템(PACS)의 출현은 전통적 필름방식에 비하여 디지털 방식으로 방사선과 영상을 획득하고 전송, 저장하는 매우 효과적인 수단을 제공하고 있다. 2002년 8월, 연세의료원 세브란스병원은 진단 영상 판독 목적으로 18 대의 CRT(Braco View, Belgium)와 32대의 평판 LCD(Totoku Electric Co., Ltd., Japan) 디스플레이 장치를 GE full-PACS(GE 메디칼시스템코리아 : GEMSK)와 연계하여 설치 완료하였다. 본 연구에서, 기하학적 왜곡, 반사, 휘도 반응, 휘도 균일도, 분해능, 노이즈,베일링 글레어, 칼라 균일도 항목들을 AAPM TG18 보고서 9.0에 따라서 시각적 그리고 부분적으로는 정량적인 방법으로 인수검사를 실시하여 보고한다. 사용된 장비는 색도계로도 사용되는 간편한 휘도계, TG18 테스트 패던, AAPM Tg18 AT plug-in software(Barco View Ltd., Kortrijk, Belgium)이었다. 칼라 균일도를 제외한 모든 테스트 결과는 AAPM TG18에서 권고하는 기준에 일치하였으며 진단 영상 판독에 사용하기에 전적으로 수락할 수 있는 성능이었다. 결론으로, 사용된 인수검사는 단지 인수 검사 표준을 제공하는 것 뿐만 아니라 품질검사(QC)의 지침, 판독 환경의 최적화 그리고 교체 시기나 업그레이드 시기를 결정하여주는 중요한 역할을 할 수 있을 것이다.

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Determination of Phantom Scatter Factors for Small Photon Fields (소조사면 광자선의 팬톰산란인수 결정)

  • Oh, Young-Kee;Choi, Tae-Jin;Kim, Jin-Hee;Kim, Ok-Bae
    • Progress in Medical Physics
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    • v.20 no.2
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    • pp.106-111
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    • 2009
  • Total scatter factor ($S_{cp}$), head scatter factor ($S_c$) and phantom scatter factor ($S_p$) are very important for accurate radiation therapy at stereotactic radiosurgery (SRS) with irregular field shape using micro-MLC and intensity modulated radiation therapy (IMRT) including many small field sizes. In this study we measured and compared $S_{cp}$ with reference ion chamber, pinpoint chamber and diode detector and adapted the resuls form diode detector. Head scatter factors for small field sizes were also measured with diode detector covered 1.5 cm-thick solid water build-up cap. Some errors like as electron contamination of 1~3% were included in the values of Sc but trend of total results of $S_c$ was coincided with basic theory. Phantom scatter factors for small field sizes were calculated form $S_{cp}$ and $S_c$. The results of $S_p$ were compared and were well-agreed with those of other authors.

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Prediction of Radionuclide Inventory for Low- and Intermediate-Level Radioactive Waste by Considering Concentration Limit of Waste Package (처분방사능량제한치를 고려한 중저준위 방사성폐기물 처분시설의 핵종재고량 산정(안))

  • Jung, Kang Il;Kim, Min Seong;Jeong, Noh Gyeom;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.1
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    • pp.65-82
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    • 2017
  • The result of a preliminary safety assessment that was completed by applying the radionuclide inventory calculated on the basis of available data from radioactive waste generation agencies suggested that many difficulties are to be expected with regard to disposal safety and operation. Based on the results of the preliminary safety assessment of the entire disposal system, in this paper, a unit package exceeding the safety goal is selected that occupies a large proportion of radionuclides in intermediate-level radioactive waste. We introduce restrictions on the amount of radioactivity in a way that excludes the high surface dose rate of the package. The radioactivity limit for disposal will be used as the baseline data for establishing the acceptance criteria and the disposal criteria for each disposal facility to meet the safety standards. It is necessary to draw up a comprehensive safety development plan for the Gyeongju waste disposal facility that will contribute to the construction of a Safety Case for the safety optimization of radioactive waste disposal facilities.

Study on the estimation of uncertainty for the air-borne noise measurements in a naval ship (함정 내 소음 평가를 위한 불확도 추정 기법 연구)

  • Kim, Seong-Yong
    • Journal of Advanced Marine Engineering and Technology
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    • v.38 no.4
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    • pp.396-402
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    • 2014
  • The measurement of air-borne noise in a naval ship is a crucial element. Because the noise in a naval ship interferes with a communication between crews and finally it causes to reduce the combat power. Thus, most of newly built ships have to satisfy the criteria of air-borne noise in the stage of delivery of a naval ship. In order to evaluate success or failure of criteria, uncertainty of the measurement should be considered. This study introduces the test method for the measurement of the air-borne noise in a naval ship and is concerned with the evaluation of uncertainty. The uncertainty results which was from the measurement of air-borne noise in 7 naval ships newly built satisfy the error tolerance(2dB). Therefore, it is need to reduce the error tolerance for the reliable measurement result.

Characterization of Cement Solidification for Enhancement of Cesium Leaching Resistance (세슘 침출 저항성 증진 시멘트 고화체의 제조 및 특성 평가)

  • Kim, Gi Yong;Jang, Won-Hyuk;Jang, Sung-Chan;Im, Junhyuck;Hong, Dae Seok;Seo, Chel Gyo;Shon, Jong Sik
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.2
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    • pp.183-193
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    • 2018
  • Currently, the Korea Atomic Energy Research Institute (KAERI) is planning to build the Ki-Jang Research Reactor (KJRR) in Ki-Jang, Busan. It is important to safely dispose of low-level radioactive waste from the operation of the reactor. The most efficient way to treat radioactive waste is cement solidification. For a radioactive waste disposal facility, cement solidification is performed based on specific waste acceptance criteria such as compressive strength, free-standing water, immersion and leaching tests. Above all, the leaching test is important to final disposal. The leakage of radioactive waste such as $^{137}Cs$ causes not only regional problems but also serious global ones. The cement solidification method is simple, and cheaper than other solidification methods, but has a lower leaching resistance. Thus, this study was focused on the development of cement solidification for an enhancement of cesium leaching resistance. We used Zeolite and Loess to improve the cesium leaching resistance of KJRR cement solidification containing simulated KJRR liquid waste. Based on an SEM-EDS spectrum analysis, we confirmed that Zeolite and Loess successfully isolated KJRR cement solidification. A leaching test was carried out according to the ANS 16.1 test method. The ANS 16.1 test is performed to analyze cesium ion concentration in leachate of KJRR cement for 90 days. Thus, a leaching test was carried out using simulated KJRR liquid waste containing $3000mg{\cdot}L^{-1}$ of cesium for 90 days. KJRR cement solidification with Zeolite and Loess led to cesium leaching resistance values that were 27.90% and 21.08% higher than the control values. In addition, in several tests such as free-standing water, compressive strength, immersion, and leaching tests, all KJRR cement solidification met the waste acceptance or satisfied the waste acceptance criteria for final disposal.

Characteristics of Solidified Cement of Electrokinetically Decontaminated Soil and Concrete Waste (동전기 제염 토양 및 콘크리트 폐기물의 시멘트 고화 특성)

  • Koo, Daeseo;Sung, Hyun-Hee;Hong, Sang Bum;Seo, Bum Kyoung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.1
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    • pp.83-91
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    • 2018
  • While using an electrokinetic method to analyze the characteristics of cement solidification of radioactive wastes from decontaminated uranium soil and concrete, the compressive strength, pH, electrical conductivity, irradiation effects, and volume expansion were measured for the solidified cement specimens. The workability of cement solidified from radioactive waste was about 170-190%. After the solidified cement was irradiated, the compressive strength decreased by about 15%, but met the criteria ($34kgf{\cdot}cm^{-2}$) of KORAD (Korea Radioactive Waste Agent). According to the results of SEM-EDS for solidified cement, the aluminum phase was well combined with cement, while the calcium phase was separated from cement. The volume of solidified cement in radioactive wastes was dependent on the waste-to-cement ratio and the amount of water, and increased by about 30% under the conditions used in this study. Therefore, it was concluded that permanent disposal of electrokinetically decontaminated radioactive wastes is appropriate.

Characteristics Evaluation of Solidifying Agent for Disposal of Radioactive Wastes Using Waste Concrete Powder (원전 폐콘크리트의 방사성 폐기물 처분용 고화제로의 활용을 위한 고화체 특성 평가)

  • Seo, Eun-A;Lee, Ho-Jae;Kwon, Ki-Hyon;Kim, Do-Gyeum
    • Journal of the Korean Recycled Construction Resources Institute
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    • v.9 no.4
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    • pp.451-459
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    • 2021
  • The purpose of this study is to evaluate the performance of a solidifying agent for recycling the fine powder separated from the nuclear power plant decommissioned concrete as a solidifying agent(SA) for radioactive waste. In order to evaluate the performance of the solidifying agent, a powder simulating the fine powder of waste concrete separated from the dismantled concrete of a nuclear power plant was produced, and the main variables were the type of binder and the replacement ratio of zeolite. The solidifying agent was evaluated for fluidity performance, compressive strength, and leaching resistance to non-radioactive cesium. The compressive strength of SA increased as the zeolite replacement ratio increased, and the SA containing 5% or more of zeolite showed a compressive strength that was 1.4 to 1.7 times higher than the acceptance criteria. The cesium leaching index of all specimens was 6 or higher, satisfying the acceptance criteria, and the leaching index of SA was 1.47~1.63 times higher than that of OPC. In particular, the average leaching index after 28 days of the 5% zeolite-substituted solidifying agent was 9.15, which was improved by about 6.4% compared to OPC, and it was confirmed that the zeolite was effective in improving the leaching resistance to cesium ions by showing stable performance over the entire period.