• Title/Summary/Keyword: Plant Safety

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A Simple and Reliable Method for Preparation of Cross-Contamination-Free Plant Genomic DNA for PCR-Based Detection of Transgenes

  • Hwang, Seon-Kap;Kim, Young-Mi
    • BMB Reports
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    • v.33 no.6
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    • pp.537-540
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    • 2000
  • A simplified but reliable method was developed for the polymerase chain reaction (PCR)-based detection of genetically modified (GM) plants. The modified CTAB (mCTAB) method enabled us to prepare a high quality of genomic DNA from several hundred plant leaf samples in one day. Using DNA samples prepared from seven dicots and two monocots, approximately 1.75-kb regions spanning 17 S to 25 S ribosomal RNA genes were successfully amplified in a 2X PCR pre-mix containing BLOTTO. Further fidelity assessment of the mCTAB method by PCR analysis with Roundup Ready soybean (RRS) and non-RRS plants showed that the DNA samples prepared alternately from each of two lines were evidently free of cross-contamination. These results demonstrate that the mCTAB method is highly recommended for the rapid detection of transgenes in large numbers of leaf samples from diverse transgenic plants.

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A Study on the Productivity Increment through Construction of Lean Production System for Automobile Plant in China (중국 자동차 공장의 린 생산 체계 구축을 통한 생산성 향상에 관한 연구)

  • Jang, Jung-Hwan;Zhang, Jing-Lun;Yoo, Sung-Hee;Lee, Chang-Ho
    • Journal of the Korea Safety Management & Science
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    • v.14 no.1
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    • pp.117-122
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    • 2012
  • This paper deals with the productivity increment through construction of lean production system for automobile factory in China. This lean production system has been progressed according to 5 steps. Step 1 is the work preparation. Step 2 is the process design. Step 3 is the establishment of method to count production quantity. Step 4 is the establishment of measuring method for input and output. Finally, step 5 is the construction of flexible production system able to adapt for environment change. This lean production system is expected to obtain the productivity increment by 50% for plastic plant and reduction by 50% in inventory quantity.

A New Dynamic Reliability Assessment for Mid-loop Operations in a Nuclear Power Plant

  • Jae, Moosung
    • International Journal of Reliability and Applications
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    • v.3 no.1
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    • pp.25-35
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    • 2002
  • This paper presents a dynamic reliability assessment methodology for use in the safety assessment of a complex system such as a nuclear power plant. The method is applied to a dynamic analysis of the potential accident sequences that may occur during mid-loop operation in a nuclear power plant. The idea behind this approach consists of both the use of the concept of the performance achievement/requirement correlation and of a dynamic event tree generation method. The assessment of the system reliability depends on the determination of both the required performance distribution and the achieved performance distribution. The quantified correlation between requirement and achievement represents a comparison between two competing variables. It is demonstrated that this method is easily applicable and flexible in that it can be applied to any kind of dynamic reliability problem.

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A Study on the Availability Prediction of Start-up Power Supply in Nuclear Power Plant by FTAMethod (FTA기법에 의한 원전기동전원의 이용율 예측에 관한 연구)

  • Che, Gyu-Shik
    • The Transactions of the Korean Institute of Electrical Engineers A
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    • v.48 no.5
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    • pp.517-523
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    • 1999
  • The Start-up transformers or on-site stand-by transformers are installed for the start-up and shut-down of generator and emergency status in unclear power plant. The on-site power supply configuration using these transformers must be detemined by considering configuration requirements, site characteristics, reliability and availability severely because it is remarkably important for safety and benefit of plant. The start-up or stand-by power supply configuration has been determined considering only safety requirements and construction cost up to now in Korea. I study various reliability estimating methods for the prediction of availability, and estimate the unavailability for the start-up power supply system of two 1,000㎿ unclear power plants. I also detemine the reliability and unavailability and unavailavility of equipment, system and configuration using FTA method.

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Formal Design for Nuclear Power Plant Embedded Digital Plant Protection System (원자력 발전소 내장형 Digital Plant Protection System의 정형적 설계)

  • 김진현;김일곤;성창훈;이나영;최진영
    • Proceedings of the Korean Information Science Society Conference
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    • 2001.04a
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    • pp.88-90
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    • 2001
  • 원자력 발전소 내장형 시스템은 안정성과 신뢰성이 절대적으로 요구되는 Safety-critical 시스템이다. 이러한 시스템의 설계는 모호성이 없는 정형명세 언어로 설계함으로 설계자와 구현자 사이의 모호성 없는 의사전달을 달성할 수 있다. 이러한 특히 원자력 발전소 내장형 시스템의 설계에 있어서 설계자는 그가 설계한 설계를 시험(Validation)하고 검증(Verification)하는 기법을 필요로 하게 된다. 특히 시스템이 복잡해질수록 설계도 내의 오류를 발견하지 못할 가능성이 커진다. 본 논문에서는 시스템이 가질 수 있는 모든 상태를 만들어내어 검사하는 형태의 검증 기법인 정형기법을 통하여 Safety-critical 한 내장형 시스템의 설계를 검증함으로 보다 완벽한 시스템을 설계하는 기법을 제안한다.

A Study on the Implementation Effect of Accident Management Strategies on Safety

  • Moosung Jae;Kim, Dong-Ha;Jin, Young-Ho
    • Nuclear Engineering and Technology
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    • v.28 no.3
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    • pp.247-256
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    • 1996
  • This paper presents a new approach for assessing accident management strategies using containment event trees (CETs) developed during an individual plant examination (IPE) for a reference plant (CE type, 950 MWe PWR). Various accident management strategies to reduce risk have been proposed through IPE. Three strategies for the station blackout sequence are used as an example : 1) reactor cavity flooding only, 2) primary system depressurization only, and 3) doing both. These strategies are assumed to be initiated at about the time of core uncovery. The station blackout (SBO) sequence is selected in this paper since it is identified as one of the most threatening sequences to safety of the reference plant. The effectiveness and adverse effects of each accident management strategy are considered synthetically in the CETs. A best estimate assessment for the developed CETs using data obtained from NUREG-1150, other PRA results, and the MAAP code calculations is performed. The strategies are ranked with respect to minimizing the frequencies of Various containment failure modes. The proposed approach is demonstrated to be very flexible in that it can be applied to any kind of accident management strategy for any sequence.

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Smart Grid Utilization of modern technology in agriculture (스마트 그리드 기술의 현대농업에의 활용방안)

  • Kim, Kwang-Man
    • Journal of the Korea Safety Management & Science
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    • v.14 no.4
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    • pp.211-218
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    • 2012
  • In this paper, we propose a system architecture of the AMI to be applied in the modern agricultural sector. Agricultural electricity costs in South Korea is very inexpensive compared with other industries. It is expected to increase oil prices to rise over the medium to long term so the facilities must to be installed for farmers in terms of energy savings and energy costs. The research and development of plant factory which can replace the ills of modern agriculture is very active. The technologies of smart grid and plat factory are good paradigm of next generation agricultural sector. Good use of smart grid technologies, the traditional energy consumption industries, agriculture sector can be self-sufficiency industry. In this article the AMI architecture is developed and it will be applicable for modern farmers plant factory.

A Study on MES Construction for Automobile Plant in China (중국 자동차 공장의 MES 구축 연구)

  • Lee, Doo-Yong;Zhang, Jing-Lun;Jang, Jung-Hwan;Yoo, Sung-Hee;Lee, Chang-Ho
    • Journal of the Korea Safety Management & Science
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    • v.14 no.4
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    • pp.265-270
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    • 2012
  • This paper deals with the application and effects of MES for H automobile plant in China. There existed the production planning and the different work order in PL painting plant, but we can simultaneously prepare the painting parts and parts delivery and assembly according to painting color by introducing MES. We can respond the change of production planning and operate integratively the PL painting, parts storage and parts delivery and then we can results in reasonable logistics. We obtained the exact production information, correct work order, precise delivery order. We obtained not only the improvement of logistics but also the reduction of inventory.

SOME POWER UPRATE ISSUES IN NUCLEAR POWER PLANTS

  • Tipping, Philip
    • Nuclear Engineering and Technology
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    • v.40 no.4
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    • pp.251-254
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    • 2008
  • Issues and themes concerned with nuclear power plant uprating are examined. Attention is brought to the fact that many candidate nuclear power plants for uprating have anyway been operated below their rated power for a significant part of their operating life. The key issues remain safety and reliability in operation at all times, irrespective of the nuclear power plant's chronological or design age or power rating. The effects of power uprates are discussed in terms of material aspects and expected demands on the systems, structures and components. The impact on operation and maintenance methods is indicated in terms of changes to the ageing surveillance programmes. Attention is brought to the necessity checking or revising operator actions after power up-rating has been implemented.

A Study on the Nonlinear Restoring Force Characteristics for Shear Wall Structures by JEAC 4601 (JEAC 4601에 의한 전단벽 구조물의 비선형 복원력 특성에 대한 고찰)

  • Lee, Won Hun;Kim, Hee Kyun;Song, Sung Bin;Hwang, Kee Tae
    • Journal of the Earthquake Engineering Society of Korea
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    • v.25 no.3
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    • pp.121-128
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    • 2021
  • Structures of domestic nuclear power plants are designed to perform elastic behavior against beyond design earthquakes, but studies on the nonlinear behavior of structures have been insufficient since the beyond design earthquake. Accordingly, it is judged that it will be necessary to develop an evaluation method that considers the nonlinear behavioral characteristics to check the safety margin for a standard nuclear power plant structure. It is confirmed that the restoring force characteristics for each member level can be identified through the calculation formula, and the lateral stiffness for each story can also be easily calculated by JEAC 4601. In addition, as a result of applying the evaluation method of JEAC 4601 as a nonlinear restoring force model of the nuclear power plant, a certain degree of safety margin can be identified.