• Title/Summary/Keyword: Plant Engineering Program

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Training Requirements for Control Room Operators of an Advanced Nuclear Power Plant

  • Park, Hong Joon;Park, Geun Ok;Kim, Sa Kil;Byun, Seong Nam
    • Journal of the Ergonomics Society of Korea
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    • v.32 no.1
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    • pp.107-115
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    • 2013
  • Objective: The aim of this study is to identify the training requirements of new nuclear power plant by a comprehensive literature review. Background: The design of instrumental and control systems for New NPP is applied fully digitalized systems. For example, soft-control, large display panels(LDP), and an advanced alarm system were applied to the APR-1400 or SMART. Method: The NUREG-0711 and international guideline of training program was analyzed from the following four phases of SAT(Systemic Approach to Training): Analysis, Design, Development, Implementation and Evaluation. Results: To identify the requirement of training program, 'Feedback' phase was considered and each phase of SAT was classified. Conclusion: A more systematic requirement of training program is needed which considers the computerized system was applied to the new NPP. Application: The results of the publishing can be useful for standardization of the systematic training program for the operators of NPP.

Life Cycle Assessment for the Business Activities of Green Company -2. Mass Balance and Environmental Improvement (녹색기업의 사업활동 전 과정에 대한 환경성 평가 -2. 물질수지 및 환경개선)

  • Shin, Choon-Hwan;Park, Do-Hyun
    • Journal of Environmental Science International
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    • v.22 no.4
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    • pp.425-433
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    • 2013
  • A mass balance of process was calculated by using the analysis of basic unit and environmental assessment of all the processes of Busan fashion color industry cooperative that operates a combined heat and power plant and a bio treatment plant. The mass balance for the combined heat and power plant was done, based on boiler and water treatment processes while each unit reactor was used for the bio treatment plant. From the results above, a resource recycle network, a treatment flowchart for food waste water/wastewater treatment and a carbon reduction program were established.

System dynamics simulation of the thermal dynamic processes in nuclear power plants

  • El-Sefy, Mohamed;Ezzeldin, Mohamed;El-Dakhakhni, Wael;Wiebe, Lydell;Nagasaki, Shinya
    • Nuclear Engineering and Technology
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    • v.51 no.6
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    • pp.1540-1553
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    • 2019
  • A nuclear power plant (NPP) is a highly complex system-of-systems as manifested through its internal systems interdependence. The negative impact of such interdependence was demonstrated through the 2011 Fukushima Daiichi nuclear disaster. As such, there is a critical need for new strategies to overcome the limitations of current risk assessment techniques (e.g. the use of static event and fault tree schemes), particularly through simulation of the nonlinear dynamic feedback mechanisms between the different NPP systems/components. As the first and key step towards developing an integrated NPP dynamic probabilistic risk assessment platform that can account for such feedback mechanisms, the current study adopts a system dynamics simulation approach to model the thermal dynamic processes in: the reactor core; the secondary coolant system; and the pressurized water reactor. The reactor core and secondary coolant system parameters used to develop system dynamics models are based on those of the Palo Verde Nuclear Generating Station. These three system dynamics models are subsequently validated, using results from published work, under different system perturbations including the change in reactivity, the steam valve coefficient, the primary coolant flow, and others. Moving forward, the developed system dynamics models can be integrated with other interacting processes within a NPP to form the basis of a dynamic system-level (systemic) risk assessment tool.

Production of Polyhydroxybutyrate from Crude Glycerol and Spent Coffee Grounds Extract by Bacillus cereus Isolated from Sewage Treatment Plant

  • Lee, Gi Na;Choi, So Young;Na, Jonguk;Youn, HaJin;Jang, Yu-Sin
    • KSBB Journal
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    • v.29 no.6
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    • pp.399-404
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    • 2014
  • Production of biodegradable polymer polyhydroxyalkanoates (PHAs) from industrial wastes exhibits several advantages such as recycle of waste and the production of high valuable products. To this end, this study aimed at isolating from the sewage treatment plant a PHA producing bacterium capable of utilizing wastes generated from biodiesel and food industries. A Bacillus cereus strain capable of producing poly(3-hydroxybutyrate) [P(3HB)] was isolated, which was followed by confirmation of P(3HB) accumulation by gas-chromatographic analyses. Then, the effects of nutrient limitation on P(3HB) production by B. cereus was first examined. Cells cultured in a minimal medium under the limitation of nitrogen, potassium and sulfur suggested that nitrogen limitation allows the highest P(3HB) accumulation. Next, production of P(3HB) was examined from both waste of biodiesel production (crude glycerol) and waste from food industry (spent coffee grounds). Cells cultured in nitrogen-limited minimal medium supplemented crude glycerol and waste spent coffee grounds extract accumulated P(3HB) to the contents of 2.4% and 1.0% of DCW. This is the first report demonstrating the capability of B. cereus to produce P(3HB) from waste raw materials such as crude glycerol and spent coffee grounds.

Effectiveness of Crew Resource Management Training Program for Operators in the APR-1400 Main Control Room Simulator (국내 원자력발전소 첨단 주제어실의 Crew Resource Management 교육훈련 효과 분석)

  • Kim, Sa-Kil;Byun, Seong-Nam;Lee, Dhong-Hoon;Jeong, Choong-Heui
    • IE interfaces
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    • v.22 no.2
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    • pp.104-115
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    • 2009
  • The objective of the study is to evaluate the effectiveness of Crew Resource Management (CRM) training program for operators in the Main Control Room (MCR) simulator of APR-1400 Nuclear Power Plant. The experiments were conducted for two different crews of operators performing six different emergency operating scenarios during four-week period. Each crew consisted of the five operators: senior reactor operator, safety technical advisor, reactor operator, turbine operator, and electric operator. All crews (Crew A and B) participated in the training program for the technical knowledge and skills which were required to operate the simulator of the MCR during the first week. To verify the effectiveness of the CRM training program; however, only Crew A was selected to attend the CRM training after the technical knowledge and skills training. The results of the experiments showed that the CRM training program improved the individual attitudes of Crew A significantly. Team skills of Crew A were found to be significantly better than those of Crew B. The CRM training did not have positive effects on enhancing the individual performance of Crew A; however, as compared to that of Crew B. Implication of these findings was discussed further in detail.

Spectral analysis for thermal discharge of Hadong Power Plant (하동화력 발전소 온배수에 대한 Spectrum 분석)

  • Park, Il-Heum;Lee, Geun-Hyo
    • Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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    • 2006.11a
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    • pp.435-440
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    • 2006
  • In order to understand changes of water temperature for thermal discharge of Hadong power plant in Gwangyang and Jinju Bay, it was analyzed for temperature data of representative season by MEM(Maximum entropy method) that is one of the spectral analysises. And due to understand effect of thermal discharge at each point, analyzed spectral data showed reactive energy rate of reference point by calculating energy from 24 time period to height frequency zone. As a result of spectral analysis, it showed that there were 9 points which are largely effected, 7 points which will be estimated, 6 points which is difficult to estimate, 14 points which rarely effected by thermal discharge.

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Analysis of Safety of the Chemical Facilities by Korea Risk Based-Inspection in the Petrochemical Plant (석유화학공장에서의 한국형 위험기반검사에 의한 화학설비의 안정성 평가)

  • Kim, Tae-Ok;Lee, Hern-Chang;Shin, Pyng-Sik;Choi, Byung-Nam;Jo, Ji-Hoon;Choi, Byung-Young;Park, Sung-Hoo;Kim, Hung-Kun
    • Journal of the Korean Society of Safety
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    • v.22 no.6
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    • pp.35-40
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    • 2007
  • As a way of improving the safety of the chemical facilities, the risk based-inspection(RBI) was executed for the facilities of the applied petrochemical plant using KS-RBI Ver. 3.0 program developed based on the API-581 based resource document(BRD). From an evaluation result of KS-RBI program, we could find the evaluation of the process safety management(PSM) for the applied plant, risk of the applied process, risk of static facilities and pipes, and the demage mechanism of the facilities. Also, we could suggest a proper inspection plan(frequency and method of inspection) using the calculated risk and the status of the facilities. Therefore, the applied plant could be achieved a reduced inspection cost by an extension of inspection frequency, improved productivity, improved reliability of the facilities, and a computerized history management.

Demonstration of EPRI CHECWORKS Code to Predict FAC Wear of Secondary System Pipings of a Nuclear Power Plant

  • Lee, Sung-Ho;Seong Jegarl;Chung, Han-Sub
    • Nuclear Engineering and Technology
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    • v.31 no.4
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    • pp.375-384
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    • 1999
  • The credibility of CHECWORKS FAC model analysis was evaluated for plant application in a model plant chosen for demonstration. The operation condition at each pipe component was defined before the wear rate analysis by plant data base, water chemistry analysis, and network flow analysis. The predicted wear was compared with the measured wear for 57 sample components selected from 43 susceptible line groups analysed. The inspected 57 locations represent components of highest predicted wear in each line group. Both absolute value and relative ranking comparisons indicated reasonable correlations between the predicted and the measured values. Four components showed much higher measured wear rates than the predicted ones in the feed water train from main feed water pump discharge to steam generator, probably due to high hydrazine concentration operation the effect of which had not been incorporated into the CHECWORKS model. The measured wear was higher than the predicted one consistently for components with least susceptibility to FAC. It is believed that the conservatism maintained during UT data analysis dominated the measurement accuracy. A great deal of enhancement is anticipated over the current plant pipe management program when a comprehensive plant pipe management program is implemented based on the model analysis.

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A Comparative Case Study of 2016 Gyeongju and 2011 Virginia Earthquakes (2016년 경주지진과 2011년 미국 버지니아지진에 대한 비교 연구 및 사례 분석)

  • Kang, Thomas H.K.;Jeong, Seung Yong;Kim, Sanghee;Hong, Seongwon;Choi, Byong Jeon
    • Journal of the Earthquake Engineering Society of Korea
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    • v.20 no.7_spc
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    • pp.443-451
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    • 2016
  • A Gyeongju earthquake in the magnitude of 5.8 on the Richter scale (the moment magnitude of 5.4), which was recorded as the strongest earthquake in Korea, occurred in September 12, 2016. Compared with the 2011 Virginia earthquake, the moment magnitude was slightly smaller and its duration was 3 seconds, much shorter than 10 seconds of the Virginia earthquake, resulting in relatively minor damage. But the two earthquakes are quite similar in terms of the overall scale, unexpectedness, and social situation. The North Anna Nuclear Power Plant, which is a nuclear power plant located at 18 km away from the epicenter of the Virginia earthquake, had no damage to nuclear reactors because the reactors were automatically shut down as the design basis earthquake value was exceeded. Ground accelerations of the 2016 Gyeongju earthquake did not exceed the threshold value but the manual shutdown was carried out so that Wolsong Nuclear Power Site was not damaged. Damaged historic homestead house and masonry structures due to the Virginia earthquake have been repaired, reinforced, and rebuilt based on a long-term earthquake recovery project. Likewise, it will be necessary to carefully carry out an earthquake recovery planning program to improve overall seismic performance and to reconstruct the historic buildings and structures damaged as a result of the Gyeongju earthquake.

Development of Computer Measurement and Control System for Plant Growth Responses (식물(植物)의 생장반응(生長反應) 계측(計測)을 위한 컴퓨터 계측(計測) 및 제어(制御) 시스템 개발(開發))

  • Kim, M.S.;Choi, D.S.;Park, J.M.;Ryu, K.H.;Noh, S.H.
    • Journal of Biosystems Engineering
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    • v.18 no.1
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    • pp.37-47
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    • 1993
  • This study was conducted to develop the on-line monitoring system for plant growth responses. The system consisted of two parts. One system was the measuring system and the other was its controlling system. The established measuring systems were the ultrasonic wave sensor driver for height of plant, the potentiometer for diameter of plant stem, and the weighing system with strain gage application for plant weight. Also, computer program for measurement and controlling was developed, and the whole system was tested by the fabricated plant, and the actual plant growth responses were monitored by the system. When monitoring the actual plant growth responses, even the small amount of plant growth resposes could be measured by the system within tolerable error ranges.

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