• Title/Summary/Keyword: Kori

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Feeding Habits of the Pointhead Flounder (Cleisthenes pinetorum) in the West Sea in Korea (한국 서해에 출현하는 용가자미(Cleisthenes pinetorum)의 식성)

  • Choi, Dong Hyuk;Youn, Byoung Il;Kim, Maeng Jin;Lee, Seung Hwan;Kwon, Dae Hyeon;Han, Kyeong Ho;Lee, Seung Jong
    • Korean Journal of Ichthyology
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    • v.33 no.4
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    • pp.273-277
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    • 2021
  • The feeding habits of the pointhead flounder, Cleisthenes pinetorum were studied in the West Sea in Korea. The samples were investigated using 360 specimens (21.7~48.1 cm in total length) collected by gill net of the coastal waters from January to December 2019. As a result, C. pinetorum consumed mainly Ophiuroidea and Pisces, but also ate small amounts of Macrura, Echinodermata, Amphipoda and Brachyura. The results of this study showed a difference with those of main feed habits of C. pinetorum caught in the coastal waters of Kori (Huh and Baeck, 2003). The proportion of fishes in prey items increased with size-related while that of Ophiuroidea decreased. As total length of C. pinetorum increased the mean number of preys per stomach (mN/ST) and weight of prey per stomach (mW/ST) tended to increase.

Classification and consideration for the risk management in the planning phase of NPP decommissioning project

  • Gi-Lim Kim;Hyein Kim;Hyung-Woo Seo;Ji-Hwan Yu;Jin-Won Son
    • Nuclear Engineering and Technology
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    • v.54 no.12
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    • pp.4809-4818
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    • 2022
  • The decommissioning project of a nuclear facility is a large-scale process that is expected to take about 15 years or longer. The range of risks to be considered is large and complex, then, it is expected that various risks will arise in decision-making by area during the project. Therefore, in this study, the risk family derived from the Decommissioning Risk Management (DRiMa) project was reconstructed into a decommissioning project risk profile suitable for the Kori Unit 1. Two criteria of uncertainty and importance are considered in order to prioritize the selected 26 risks of decommissioning project. The uncertainty is scored according to the relevant laws and decommissioning plan preparation guidelines, and the project importance is scored according to the degree to which it primarily affects the triple constraints of the project. The results of risks are divided into high, medium, and low. Among them, 10 risks are identified as medium level and 16 risks are identified as low level. 10 risks, which are medium levels, are classified in five categories: End state of decommissioning project, Management of waste and materials, Decommissioning strategy and technology, Legal and regulatory framework, and Safety. This study is a preliminary assessment of the risk of the decommissioning project that could be considered in the preparation stage. Therefore, we expect that the project risks considered in this study can be used as an initial data for reevaluation by reflecting the detail project progress in future studies.

A Study on the Significance of Unit Capacity Factor (Utilization Rate) of Nuclear Power Plants and Measures for Increasing (원전 이용률의 의의 및 증진방안 고찰)

  • Don Kug Lee;Chi Bum Bahn
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.18 no.2
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    • pp.87-100
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    • 2022
  • Unit capacity factor (utilization rate) of nuclear power plants (NPPs) is an important performance indicator. Since the first commercial operation of Kori Unit 1 began in April 1978, the utilization rate of domestic NPPs has gradually increased, reaching 90% from the end of the 1990s. However, due to various issues such as the Fukushima accident in 2011, corrosion of the CLP, the utilization rate dropped to 65~80%. In the early 1980s, the utilization rate of the U.S. NPPs was around 60%. However, since 2004, it has been consistently maintained above 90%. Therefore, in this study, we first examined the causes of declining the utilization rate in domestic NPPs. Next, the significances of the utilization rates are reviewed in five aspects: investment capability, electricity rate, safety and export, etc., with discussion on the current status of the utilization rates in the U.S. Based on this, three key factors are derived as the reasons of the increasing: equipment reliability program, on-line maintenance and the pursuit of institutional rationality. And finally, by synthesizing above results, the measures for increasing the utilization rate of domestic NPPs are proposed in terms of equipment management, institutional improvements, and personnel resources.

Methodology for Developing Standard Schedule Activities for Nuclear Power Plant Construction through Probabilistic Coherence Analysis

  • kim, Woojoong
    • International conference on construction engineering and project management
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    • 2017.10a
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    • pp.8-13
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    • 2017
  • Nuclear power plant (NPP) constructions are large scale projects that are executed for several years, and schedule control utilizing various schedules is a critically important factor. Recently Korea independently developed the Advanced Power Reactor (APR) 1400 and is building nuclear facilities applying this new reactor type. The construction of Shin-Kori NPP (SKN) Unit 3, which adopted the APR1400, was completed and commercial operation has begun, while, SKN 4, Shin-Hanul NPP (SHN) Units 1&2, and SKN 5&6 are currently under construction. Prior to the development of the APR1400, Korea built 24 reactors and accumulated the schedule data of various reactor types which provided the foundation for schedule reduction to be possible. However, as there is no schedule development and review system established based on the standard schedule data (standard activities, durations, etc.) by reactor type, the process for developing the schedule for new builds is low in efficiency consuming much time and manpower. Also all construction data has been accumulated based on schedule activities. But because the connectivity of activities between projects is low, it is difficult to utilize such accumulated data (causes for schedule delay, causes for design changes, etc.) in new build projects. Due to such reasons, issues continue to arise in the process of developing standard schedule activities and a standard schedule for nuclear power plant construction. In order to develop a standard schedule for NPP construction, i) the development of an NPP standard schedule activity list, ii) development of the connection logic of NPP standard schedule activities, iii) development of NPP standard schedule activity resources and duration, and iv) integration of schedule data need to be performed. In this paper, an analysis was made on the coherence of schedule activity descriptions of existing NPPs by applying the probabilistic methodology on activities with low connectivity due to the utilization of the numbering system of four APR1400 reactors (SHN 1&2 and SKN 3&4).This study also describes the method for developing a standard schedule activity list and connectivity measures by extracting same and/or similar schedule activities.

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Preliminary Radiation Exposure Dose Evaluation for Workers of the Landfill Disposal Facility Considering the Radiological Characteristics of Very Low Level Concrete and Metal Decommissioning Wastes (극저준위 콘크리트, 금속 해체방폐물의 방사선적 특성을 고려한 매립형 처분시설 방사선작업자 예비 피폭선량 평가)

  • Ho-Seog Dho;Ye-Seul Cho;Hyun-Goo Kang;Jae-Chul Ha
    • Journal of Radiation Industry
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    • v.17 no.4
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    • pp.509-518
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    • 2023
  • The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during the dismantling process. For the disposal of Very-low-level waste, which is expected to account for the largest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detailed design to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is being developed to efficiently dispose of metal and concrete waste, which are mainly generated as Very low-level waste of decommissioning. In this study, based on the design characteristics of the 3-phase landfill disposal facility and the large container under development, radiation exposure dose evaluation was performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using the MCNP computer program, and the internal and external exposure dose evaluation due to damage to the decommissioning waste package during a drop accident was performed based on the evaluation method of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determine whether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of the evaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limit was confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the large container for dismantled radioactive waste, which is currently under development, was confirmed.

Occurrence and Chemical Composition of Ti-bearing Minerals from Drilling Core (No.04-1) at Gubong Au-Ag Deposit Area, Republic of Korea (구봉 금-은 광상일대 시추코아(04-1)에서 산출되는 함 티타늄 광물들의 산상과 화학조성)

  • Bong Chul Yoo
    • Korean Journal of Mineralogy and Petrology
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    • v.36 no.3
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    • pp.185-197
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    • 2023
  • The Gubong Au-Ag deposit consists of eight lens-shaped quartz veins. These veins have filled fractures along fault zones within Precambrian metasedimentary rock. This has been one of the largest deposits in Korea, and is geologically a mix of orogenic-type and intrusion-related types. Korea Mining Promotion Corporation drilled into a quartz vein (referred to as the No. 6 vein) with a width of 0.9 m and a grade of 27.9 g/t Au at a depth of -728 ML by drilling (No. 90-12) in the southern site of the deposit, To further investigate the potential redevelopment of the No. 6 vein, another drilling (No. 04-1) was carried out in 2004. In 2004, samples (wallrock, wallrock alteration and quartz vein) were collected from the No. 04-1 drilling core site to study the occurrence and chemical composition of Ti-bearing minerals (ilmenite, rutile). Rutile from mineralized zone at a depth of -275 ML occur minerals including K-feldspar, biotite, quartz, calcite, chlorite, pyrite in wallrock alteration zone. Ilmenite and rutile from ore vein (No. 6 vein) at a depth of -779 ML occur minerals including white mica, chlorite, apatite, zircon, quartz, calcite, pyrrhotite, pyrite in wallrock alteration zone and quartz vein. Based on mineral assemblage, rutile was formed by hydrothermal alteration (chloritization) of Ti-rich biotite in the wallrock. Chemical composition of ilmenite has maximum values of 0.09 wt.% (HfO2), 0.39 wt.% (V2O3) and 0.54 wt.% (BaO). Comparing the chemical composition of rutile at a depth -275 ML and -779 ML, Rutile at a depth of -779 ML is higher contents (WO3, FeO and BaO) than rutile at a depth of -275 ML. The substitutions of rutile at a depth of -275 ML and -779 ML are as followed : rutile at a depth of -275 ML Ba2+ + Al3+ + Hf4+ + (Nb5+, Ta5+) ↔ 3Ti4+ + Fe2+, 2V4+ + (W5+, Ta5+, Nb5+) ↔ 2Ti4+ + Al3+ + (Fe2+, Ba2+), Al3+ + V4++ (Nb5+, Ta5+) ↔ 2Ti4+ + 2Fe2+, rutile at a depth of -779 ML 2 (Fe2+, Ba2+) + Al3+ + (W5+, Nb5+, Ta5+) ↔ 2Ti4+ + (V4+, Hf4+), Fe2+ + Al3+ + Hf 4+ + (W5+, Nb5+, Ta5+) ↔ 2Ti4+ + V4+ + Ba2+, respectively. Based on these data and chemical composition of rutiles from orogenic-type deposits, rutiles from Gubong deposit was formed in a relatively oxidizing environment than the rutile from orogenictype deposits (Unsan deposit, Kori Kollo deposit, Big Bell deposit, Meguma gold-bearing quartz vein).

A Study on the Food Consumption Rates for Off-site Radiological Dose Assessment around Korean Nuclear Power Plants (국내 원자력발전소 주변 주민의 방사선량 평가를 위한 음식물 섭취율 설정 연구)

  • Lee, Gab-Bock;Chung, Yang-Geun
    • Journal of Radiation Protection and Research
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    • v.33 no.4
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    • pp.183-196
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    • 2008
  • The internal dose by food consumption mostly accounts for radiological dose of public around nuclear power plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commssion) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The Ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in $2001{\sim}2002$. Also, the food consumption rates for maximum individual are re-estimated.

Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant (원자력발전소 PSI/ISI 데이터 관리를 위한 지능형 데이터 베이스 프로그램 개발)

  • Park, Un-Su;Park, Ik-Keun;Um, Byong-Guk;Park, Yun-Won;Kang, Suk-Chul
    • Journal of the Korean Society for Nondestructive Testing
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    • v.18 no.5
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    • pp.389-397
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    • 1998
  • For an effective and efficient management of large amounts of preservice/inservice inspection(PSI/ISI) data in nuclear power plants, an intellegent Windows 95-based data management program was developed. This program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis in the past are avoided. The program extracts, and the associated remedies. Furthermore, additional inspection data and comments can be easily added or deleted for subsequent PSI/ISI operation. Although the initial version of the program was applied to Kori nuclear power plant, this program can be equally applied to other nuclear power plant. And also this program can be used to offer the fundamental data for application of evaluation data related to fracture mechanics analysis(FMA), probabilistic reliability assessment(PRA) of PSI/ISI results, performance demonstration initiative(PDI) and risk-informed ISI based on probability of detection(POD) information of ultrasonic examination. Besides, the program can be further developed as a unique PSI/ISI data management expert system that can be apart of PSI/ISI data management expert system that can be a part of PSI/ISI Total Support System(TSS) for Korean nuclear power plants.

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Human Tutoring vs. Teachable Agent Tutoring: The Effectiveness of "Learning by Teaching" in TA Program on Cognition and Motivation

  • Lim, Ka-Ram;So, Yeon-Hee;Han, Cheon-Woo;Hwang, Su-Young;Ryu, Ki-Gon;Shin, Mo-Ran;Kim, Sung-Il
    • 한국HCI학회:학술대회논문집
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    • 2006.02a
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    • pp.945-953
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    • 2006
  • The researchers in the field of cognitive science and learning science suggest that the teaching activity induces the elaborative and meaningful learning. Actually, lots of research findings have shown the beneficial effect of learning by teaching such as peer tutoring. But peer tutoring has some limitations in the practical learning context. To overcome some limitations, the new concept of "learning by teaching" through the agent called Teachable Agent. The teachable agent is a modified version of traditional intelligent tutoring system that assigns a role of tutor to teach the agent. The teachable agent monitors individual difference and provides a student with a chance for deep learning and motivation to learn by allowing them to play an active role in the process of learning. That is, The teaching activity induces the elaborative and meaningful learning. This study compared the effects of our teachable agent, KORI, and peer tutoring on the cognition and motivation. The field experiment was conducted to examine whether learning by teaching the teachable agent would be more effective than peer tutoring and reading condition. In the experiment, all participants took 30 minutes lesson on rock and rock cycle together to acquire the base knowledge in the domain. After the lesson, participants were randomly assigned to one of the three experimental conditions; reading condition, peer tutoring condition, and teachable agent condition. Next, participants of each condition moved into separated place and performed their own learning activity. After finishing all of the learning activities in each condition, all participants were instructed to rate the interestingness using a 5-point scale on their own learning activity and leaning material, and were given the comprehension test. The results indicated that the teachable agent condition and the peer tutoring condition showed more interests in the learning than the reading condition. It is suggested that teachable agent has more advantages in overcoming the several practical limitations of peer tutoring such as restrictions in time and place, tutor's cognitive burden, unnecessary interaction during peer tutoring. The applicability and prospects of the teachable agent as an efficient substitute for peer tutoring and traditional intelligent tutoring system were also discussed.

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An Analysis on the Deep Geological Disposal Concepts Considering the Spent Fuel Length (사용후핵연료 길이에 따른 심지층 처분시스템 분석)

  • LEE, Jongyoul;KIM, Hyeona;LEE, Minsoo;CHOI, Heuijoo;KIM, Keonyoung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.13 no.3
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    • pp.201-209
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    • 2015
  • Currently, 23 nuclear power plants are in operation at Kori, Uljin, Younggwang and Wolsong site and a reference deep geological disposal system has been developed for the spent fuels generated by them. The reference spent fuel for this disposal system has 4.5wt% of initial enrichment, 55 GWd/MtU of burn-up, and 40 years of cooling time. In this paper, to improve disposal efficiency and economic feasibility, the characteristics of spent fuels from nuclear power plants, such as type and burn-up, were reviewed. A disposal canister concept for shorter length and relatively lower burn-up spent fuels than the reference spent fuels was developed. Based on this canister concept, thermal analyses were carried out and a deep geological disposal concept was proposed. Measures of disposal efficiency such as unit disposal area and disposal density were compared between this disposal system and the reference disposal system. Also, economic feasibility, such as the volume reduction of copper, cast iron, and bentonite, was analyzed and the results of these analyses showed that the disposal system proposed in this paper has an efficiency of at least 20%. These results could be used for establishing spent fuel management policy and designing practical disposal systems for spent fuels.