• Korean Journal of Fisheries and Aquatic Sciences
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• v.24 no.4
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• pp.255-265
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• 1991

The Genus Acartia of calanoid copepod comprises about 50 species from world oceans. Most of them are neritic and very abundant in coastal waters. For the present study samples were collected from ten sites (Garolim Bay, Deukyang Bay, Chinhae Bay, Kyonggi Bay, Kwangyang Bay, Kori, Wolsung, Youngkwang, Uljin and Cheju area) during the period from September 1981 to December 1990 and at selected six stations in Masan Bay during the period from April 1986 to September 1987. As a result, Genus Acartia of Korea was identified as following ten species: Acartia bifilosa, A. danae, A. erythraea, A. hudsonica, A. negligens, A. eomorii, A. pacifica, A. sinjiensis, ,4. spinicauda and A. steueri. The key to the species was suggested and the description of A. sinjiensis was given as the new in Korean waters.

• Nuclear Engineering and Technology
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• v.18 no.1
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• pp.17-26
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• 1986

A test is made for a method to determine reliable bias in the criticality safety analysis of spent fuel storage pool with turnup credit between the reference and rack criticality calculation methods. The spent fuel pool of Kori Unit 1 is conceptually redesigned to the most compact rack with turnup credit, and its multiplication factors are calculated depending on fuel enrichment and burnup, by the Monte Carlo code KENO-IV as a reference and by a two-dimensional collision probability code FATAC as a practical method. Then, the computed values with the help of the above two computer codes are compared to evaluate the bias and its trend in terms of multiplication factor on fuel enrichment and turnup. The result indicates that the bias can be determined with reliability basis but without any disadvantage in criticality safety margin compared with the conventional method.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.1
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• pp.107-122
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• 2018

Kori unit 1, the oldest commercial nuclear power plant in South Korea, was permanently shut down in June 2017. There are a lot of things to consider in decommissioning nuclear power plants, and one of them is the radiological environmental impact assessment. Performed to promote the health and safety of residents around the nuclear power plant, radiological environmental impact assessment aims to confirm that off-site radiological dose from radioactive material released from the facility does not exceed the regulatory criteria. There are three main parts of environmental impact assessment: pre-decommissioning environmental monitoring, environmental monitoring during decommissioning, and impact on nearby residents. At present, although the Korea Nuclear Safety Act stipulates that radiological environmental impact assessment resulting from decommissioning should be carried out, the details have not been specified. Therefore, this paper compares and analyzes guidelines for evaluation of radiological environmental impacts of nuclear power plants overseas, and presents a draft on the assessment of radiological dose resulting from decommissioning according to the Korean situation.

• Journal of Radiation Protection and Research
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• v.29 no.2
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• pp.117-127
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• 2004

A dynamic compartment model was developed to evaluate the transport of accidently released radionuclides onto rice-fields. In the model, the surface water compartment and shoot-base absorption were introduced to account for the effect of irrigation, which is essential to a rice cultivation. The soil mixing by plough and irrigation before transplanting rice was also considered, and the rate of root-uptake and shoot-base absorption were modeled in terms of the function of biomass. In order to test the validation of the model, it was applied to the analysis of some simulated $^{137}Cs$ deposition experiments that were performed while cultivating rice in a greenhouse using soils sampled from rice-fields around Kori, Yonggwang and Ulchin nuclear power plants. The model prediction was generally agreed within about one order of magnitude with experimental data.

• Korean Journal of Construction Engineering and Management
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• v.18 no.1
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• pp.48-57
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• 2017

The construction of the first nuclear power plant (Kori #1) in Korea started in 1971, Korea operates 24 nuclear power plants and is constructing 4 in 2015. During about 45 years of construction experience, insufficient studies have been investigated for the identification of critical success factors(CSFs) for nuclear power plant construction. Based on literature reviews and focus group interviews, this study presented a list of CSFs for construction of nuclear power plants. A survey for validating the results of CSFs was conducted with 164 experts. This study indicates that attentions should be placed upon the lowest price-based contract awarding policy, the need for reasonable pricing standard implementation, database development, and deployment for experienced nuclear power plant construction workers, identification and nurturing of competitive subcontractors, and minimization of lag times in construction activities.

• Proceedings of the Korea Society for Simulation Conference
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• 2000.11a
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• pp.61-66
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• 2000

The KEPRI has been upgrading the KNPEC(Korea Nuclear Power Education Center) #2 simulator, a replica of Yonggwang Unit 1 & 2, due to the outdated systems. The scenarios, such as the continuous load change, are selected to verify and validate the simulator, and the data required to V&V are generated with the best-estimated codes, RETRAN and MARS. The reactor coolant system and steam generator system are cut up into volumes and junctions for the accurate model of the scenarios, and other components and control systems are modeled. For the model the operation and design data of the plants is used and in some cases the data of Kori Unit 3 & 4 is used to fill up the lack of required data. The results of some selected analyses with the models are compared with the operating data of the plants to verify the models, and the analyses of the scenarios are carried out to generated the data for the V&V of the simulator

• Speech Sciences
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• v.9 no.2
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• pp.69-87
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• 2002

This paper investigates how focus contributes to the phonological and phonetic realization of Japanese intonation. Pierrehumbert & Beckman (1988) pointed out that textual prominence results in the H-tone peak raising on the focused item and IP (Intonational Phrase) initiation before the focused item. Similarly Kori (1989) suggested that the F0 peaks on the words after the focused item tend to be suppressed. Although they give a general description of the characteristics of focus phenomena in Japanese intonation, they fail to explain the F0 peak interaction between H phrasal tone and lexically specified pitch accent in more-than-3-mora words whose accent locations varies from early to late. In this paper, we perform the experiment to investigate the following three points. First, we would like to look at the systematic intonational differences between focused and neutral APs; specifically, focused APs, either accented or unaccented, are compared with the neutral counterparts in terms of F0 pattern. Second, we investigate F0 patterns of a focused AP with more than 3 morae, as the accent of the word varies from early to late. Since an AP with a late accent has a H- on the second mora as well as H*+L on its accent mora, it is expected that these peaks will show systematic F0 pattern when it is focused. Our third concern is F0 patterns of a post focus AP with more than 3 morae, that is, whether a post-focus word is dephrased or just downstepped as the word accent location varies from early to late. This paper is significant in that it tries to clarify the F0 peak interaction between H-and lexical pitch accent H*+L in a variety of focus contexts in Japanese intonation.

• Journal of Radiation Protection and Research
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• v.32 no.2
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• pp.71-78
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• 2007

The purpose of this study is to analyze the social behavior, especially, the evacuation-related social behavior, of the transients in the radiological emergency planning zone(EPZ) of nuclear power plants. So, the meaning and kinds of the evacuation and the significance of the trip generation time(TGT) have been reviewed. The characteristics of the social behavior of the transient around Ulchin, Wolsong and Kori sites was analyzed through field surveys by using the questionnaire. The major findings of this research implications are as follows. First, for securing the safe evacuation, the alternatives to effectively provide the information on the evacuation warning may be prepared. Second, it is necessary to establish the education and training of transient's evacuation. Third, it is needed that the cause and background of the evacuation refusal are identified and the new response plan to secure transient's safety is prepared.

• Nuclear Engineering and Technology
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• v.17 no.4
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• pp.256-266
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• 1985

The loss of coolant flow accident is analyzed for the pressurized water reactor of Korea Nuclear Unit-1. The loss of coolant flow accident is classified into three types in accordance with its severity; partial loss of coolant flow, complete loss of coolant flow and pump locked rotor accident. Analysis has been carried out in three stages; system transient and average core analysis, DNBR calculation and hot spot analysis. The purpose of developing KTRAN is to simulate the transient fast. For the DNBR calculation, the thermal hydraulic codes, SCAN and COBRA IV-1, are adopted. And for the hot spot analysis, the fuel thermal transient code LTRAN is employed. This code system should be fast responding to the transient analysis. In case the transient occurs, severity comes within a couple of seconds. So response should be fast to accomodate the following sequence of the accident. Unfortunately this purpose could not be achieved by KTRAN. However, the calculated results are well comparable with FSAR results in range. Thereby, the effectiveness of KTRAN code analysis in this type of accident is proven.

• Journal of the Korean Recycled Construction Resources Institute
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• v.7 no.4
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• pp.316-322
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• 2019

A probabilistic approach considering uncertainties was employed to investigate the effects on the material characteristics and strength of nuclear bio-logical shield concrete walls, when exposed to long-term radiation during the entire service life. Time-dependent compressive and tensile strengths were estimated by conducting the neutron fluence analysis. For the contaminated concrete, individual compressive and tensile failure probabilities can be possibly evaluated by not only establishing limit-state function withthe predefined critical values but also performing Monte Carlo Simulation. Nuclear power plant types similar to the Kori Unit 1, which was shut off permanently in 2017 after the 40-year operation, were herein selected for an illustrative purpose. Consequently, the probability-based performance assessment and prediction of contaminated concrete walls were well demonstrated.