• Title/Summary/Keyword: Nuclear Program

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ANALYSIS OF TMI-2 BENCHMARK PROBLEM USING MAAP4.03 CODE

  • Yoo, Jae-Sik;Suh, Kune-Yull
    • Nuclear Engineering and Technology
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    • v.41 no.7
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    • pp.945-952
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    • 2009
  • The Three Mile Island Unit 2 (TMI-2) accident provides unique full scale data, thus providing opportunities to check the capability of codes to model overall plant behavior and to perform a spectrum of sensitivity and uncertainty calculations. As part of the TMI-2 analysis benchmark exercise sponsored by the Organization for Economic Cooperation and Development Nuclear Energy Agency (OECD NEA), several member countries are continuing to improve their system analysis codes using the TMI-2 data. The Republic of Korea joined this benchmark exercise in November 2005. Seoul National University has analyzed the TMI-2 accident as well as the currently proposed alternative scenario along with a sensitivity study using the Modular Accident Analysis Program Version 4.03 (MAAP4.03) code in collaboration with the Korea Hydro and Nuclear Power Company. Two input files are required to simulate the TMI-2 accident with MAAP4: the parameter file and an input deck. The user inputs various parameters, such as volumes or masses, for each component. The parameter file contains the information on TMI-2 relevant to the plant geometry, system performance, controls, and initial conditions used to perform these benchmark calculations. The input deck defines the operator actions and boundary conditions during the course of the accident. The TMI-2 accident analysis provided good estimates of the accident output data compared with the OECD TMI-2 standard reference. The alternative scenario has proposed the initial event as a loss of main feed water and a small break on the hot leg. Analysis is in progress along with a sensitivity study concerning the break size and elevation.

Analysis on the Changes of Teachers' Consciousness and Ambivalent Attitude through the Environmental Education Training (환경교육 직무연수를 통한 교사들의 의식변화와 양면가치태도 변화 분석)

  • Lee, Jin-Heon;Sung, Jung-Jin;Choi, Jin-Ha
    • Hwankyungkyoyuk
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    • v.18 no.1 s.26
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    • pp.120-133
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    • 2005
  • This study investigated the changes of consciousness and ambivalent attitudes about the important environmental issues among the teachers who enrolled the environmental education training. Experimental and control groups were composed with 47 and 30 person, respectively. Environmental issues were constructions of sea-wall, nuclear power plant and dam. Cronbach alpha of the self-developed questionnaire was $0.6909{\sim}0.8992$. Score were made with 5 Likert scales for consciousness, and with semantic differential half scale for ambivalent attitudes. Almost teachers(94.0% and 97.1%) have above 10 years teaching career. Strangers in environmental program were 53.2%. After environmental training, teachers' consciousness was significantly changed to negative about the construction of sea-wall for the farm field and industry complex area(p=0.019), and about the construction of dam for disaster like flood(p=0.026), and for adverse effects of citizen by fog(p=0.042). They were also significantly changed to negative about the construction of nuclear power plant for economical energy(p=0.004)', no-emission of greenhouse gases(p=0.033)', 'alternative energy(p=0.000)', 'destruction of ecology(p=0.052)' and 'social fear(p=0.009)'. The consciousness of teachers who have the experience of environmental training, were significantly changed to negative about the construction of nuclear power plant. Scores of teachers' ambivalent attitudes were made lower in experimental than control group about the construction of sea-wall and nuclear power plant. After education training, they were made lower so much as -10.0% in control, but higher much as +4.4% in experimental, and severely higher much as 86.5% in teachers who had experienced the environmental training about construction of sea-wall. Their scores were made lower so much as -3.3% in control, but much as -6.4% in control.

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Finite Element Analysis of Pipe Whip Restraint Behavior Under Jet Thrust Forces (유체 분사 추진력을 받는 배관 휩 구속장치 거동에 관한 유한요소해석)

  • Sugoong Koh;Lee, Young-Shin
    • Nuclear Engineering and Technology
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    • v.25 no.3
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    • pp.353-360
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    • 1993
  • Many types of pipe whip restraints are installed to protect the structural components from the anticipated pipe whip phenomena of high energy lines in nuclear power plants. It is necessary to investigate these phenomena accurately in order to design the pipe whip restraints properly and/or to evaluate the acceptability of the pipe whip restraint design. Various research programs have been conducted in many countries to develop analytical methods and to verify the validity of the methods. In this study, various types of finite elements in ANSYS[1], the general purpose finite element computer program, was used to simulate the postulated pipe whips to obtain impact loads and the calculated results were compared with the specific experimental results from the sample pipe whip test for the U-shaped pipe whip restraints. Some calculational models, having the gap element or the spring element between the pipe whip restraint and the pipe line, give reasonably good transient responses of the restraint forces compared with the experimental results, and could be useful in evaluating the acceptability of the pipe whip restraint design.

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Thermal Margin Analysis of the Korea Nuclear Unit 1 Reactor Core Consisting of Standard or Optimized Fuel Assemblies (표준 핵연료집합체 또는 최적 핵연료집합체가 장전된 원자력 1호기 원자로심의 열적여유도 분석)

  • Hyun Koon Kim;Ki In Han
    • Nuclear Engineering and Technology
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    • v.16 no.3
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    • pp.155-160
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    • 1984
  • Analyzed is the thermal margin of the Korea Nuclear Unit 1 (KNU-1) reactor core consisting of either 14 x 14 standard fuel assemblies (SFA) or optimized fuel assemblies (OFA). Employed for the analysis are two different thermal design methods; traditional and statistical thermal design method. Compared to the traditional design thermal method, the statistical thermal design method improves the core thermal margin utilizing best-estimate values for the core operating parameters combining their uncertainties in a statistical manner. Calculations are performed using a steady state and transient thermal-hydraulic analysis computer program, COBRA-IV-i. Calculated results show that the statistical thermal design method significantly improves the thermal margin and satisfies the core thermal design base of the KNU-1 SFA and OFA core. However, the thermal design base can not be met, if the traditional thermal design method is employed for the OFA role analysis.

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Feasibility Study of Seismic Probabilistic Risk Assessment for Multi-unit NPP with Seismic Failure Correlation (다수기의 확률론적 지진안전성 평가를 위한 지진손상 상관계수의 적용)

  • Eem, Seunghyun;Kwag, Shinyoung;Choi, In-Kil
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.34 no.5
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    • pp.319-325
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    • 2021
  • The 2011 East Japan Earthquake caused accidents at a number of nuclear power plants in Fukushima, highlighting the need for a study on the seismic safety of multiple NPP (Nuclear Power Plant) units. In the case of nuclear power plants built on a site that shows a similar seismic response, there is at least a correlation between the seismic damage of structures, systems, and components (SSCs) of nuclear power plants. In this study, a probabilistic seismic safety assessment was performed for the loss of essential power events of twin units. To derive an appropriate seismic damage correlation coefficient, a probabilistic seismic response analysis was performed. Using the external event mensuration system program, we analyzed the seismic fragility and seismic risk by composing a failure tree of multiple loss of essential power events. Additionally, a comparative analysis was performed considering the seismic damage correlation between SSCs as completely independent and completely dependent.

Numerical investigation on seismic performance of reinforced rib-double steel plate concrete combination shear wall

  • Longyun Zhou;Xiaohu Li;Xiaojun Li
    • Nuclear Engineering and Technology
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    • v.56 no.1
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    • pp.78-91
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    • 2024
  • Double steel plate concrete composite shear wall (SCSW) has been widely utilized in nuclear power plants and high-rise structures, and its shear connectors have a substantial impact on the seismic performance of SCSW. Therefore, in this study, the mechanical properties of SCSW with angle stiffening ribs as shear connections were parametrically examined for the reactor containment structure of nuclear power plants. The axial compression ratio of the SCSW, the spacing of the angle stiffening rib arrangement and the thickness of the angle stiffening rib steel plate were selected as the study parameters. Four finite element models were constructed by using the finite element program named ABAQUS to verify the experimental results of our team, and 13 finite element models were established to investigate the selected three parameters. Thus, the shear capacity, deformation capacity, ductility and energy dissipation capacity of SCSW were determined. The research results show that: compared with studs, using stiffened ribs as shear connectors can significantly enhance the mechanical properties of SCSW; When the axial compression ratio is 0.3-0.4, the seismic performance of SCSW can be maximized; with the lowering of stiffener gap, the shear bearing capacity is greatly enhanced, and when the gap is lowered to a specific distance, the shear bearing capacity has no major affect; in addition, increasing the thickness of stiffeners can significantly increase the shear capacity, ductility and energy dissipation capacity of SCSW. With the rise in the thickness of angle stiffening ribs, the improvement rate of each mechanical property index slows down. Finally, the shear bearing capacity calculation formula of SCSW with angle stiffening ribs as shear connectors is derived. The average error between the theoretical calculation formula and the finite element calculation results is 8% demonstrating that the theoretical formula is reliable. This study can provide reference for the design of SCSW.

Quantification of Brain Images Using Korean Standard Templates and Structural and Cytoarchitectonic Probabilistic Maps (한국인 뇌 표준판과 해부학적 및 세포구축학적 확률뇌지도를 이용한 뇌영상 정량화)

  • Lee, Jae-Sung;Lee, Dong-Soo;Kim, Yu-Kyeong;Kim, Jin-Su;Lee, Jong-Min;Koo, Bang-Bon;Kim, Jae-Jin;Kwon, Jun-Soo;Yoo, Tae-Woo;Chang, Ki-Hyun;Kim, Sun-I.;Kang, Hye-Jin;Kang, Eun-Joo
    • The Korean Journal of Nuclear Medicine
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    • v.38 no.3
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    • pp.241-252
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    • 2004
  • Purpose: Population based structural and functional maps of the brain provide effective tools for the analysis and interpretation of complex and individually variable brain data. Brain MRI and PET standard templates and statistical probabilistic maps based on image data of Korean normal volunteers have been developed and probabilistic maps based on cytoarchitectonic data have been introduced. A quantification method using these data was developed for the objective assessment of regional intensity in the brain images. Materials and Methods: Age, gender and ethnic specific anatomical and functional brain templates based on MR and PET images of Korean normal volunteers were developed. Korean structural probabilistic maps for 89 brain regions and cytoarchitectonic probabilistic maps for 13 Brodmann areas were transformed onto the standard templates. Brain FDG PET and SPGR MR images of normal volunteers were spatially normalized onto the template of each modality and gender. Regional uptake of radiotracers in PET and gray matter concentration in MR images were then quantified by averaging (or summing) regional intensities weighted using the probabilistic maps of brain regions. Regionally specific effects of aging on glucose metabolism in cingulate cortex were also examined. Results: Quantification program could generate quantification results for single spatially normalized images per 20 seconds. Glucose metabolism change in cingulate gyrus was regionally specific: ratios of glucose metabolism in the rostral anterior cingulate vs. posterior cingulate and the caudal anterior cingulate vs. posterior cingulate were significantly decreased as the age increased. 'Rostral anterior'/'posterior' was decreased by 3.1% per decade of age ($P<10^{-11}$, r=0.81) and 'caudal anterior'/'posterior' was decreased by 1.7% ($P<10^{-8}$, r=0.72). Conclusion: Ethnic specific standard templates and probabilistic maps and quantification program developed in this study will be useful for the analysis of brain image of Korean people since the difference in shape of the hemispheres and the sulcal pattern of brain relative to age, gender, races, and diseases cannot be fully overcome by the nonlinear spatial normalization techniques.

Effects of Cortical Activation upon Mechanical Force-Mediated Changes in the OPG and RANKL Levels in Gingival Crevicular Fluid

  • Yu, Nam-Hyun;Kwak, So-Yeong;Hong, So-Yeon;Kim, Jong-Ghee;Jeon, Young-Mi;Lee, Jeong-Chae
    • International Journal of Oral Biology
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    • v.34 no.4
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    • pp.199-203
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    • 2009
  • This study investigated whether orthodontic force influences the production of osteoprotegerin (OPG) and receptor activator of nuclear factor-kappa B ligand (RANKL) in vivo, both of which are affected by cortical activation. Mechanical force was applied to the maxillary premolars of orthodontic patients by fitting the transpalatal arch prior to cortical activation of the gingival tissue. Gingival crevicular fluid (GCF) samples were then collected from each patient using paper strips before and after 1, 3, 7 or 14 days of treatment. The OPG and RANKL levels in the GCF were determined by enzyme-linked immunosorbent assays. The levels of OPG were significantly increased after 1 day of fitting the appliance and decreased to basal levels at 3 days after fitting. In contrast, the RANKL levels were dramatically decreased at 1 day after fitting, but recovered to those of the untreated control at 3 days after the force application. The force-mediated changes in the OPG and RANKL levels of the GCF were unaffected by cortical activation during these experimental periods. Collectively, these results suggest that an acute and severe change between the OPG and RANKL levels plays an important role in stimulating the cellular responses required for alveolar bone remodeling by orthodontic treatment.

Nutrition Knowledge and Need for a Dietary Education Program among Marriage Immigrant Women in Gyeongbuk Region (경북지역 결혼이주여성의 영양지식 및 식생활 교육 프로그램 요구도 조사)

  • Jeong, Mi-Jeong;Jung, Eun-Kyung;Kim, Ae-Jung;Joo, Nami
    • Journal of the Korean Dietetic Association
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    • v.18 no.1
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    • pp.30-42
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    • 2012
  • The purpose of this study was to provide basic materials and assistance for developing a nutritional education program targeting marriage immigrant women, and it was carried out on 86 female marriage immigrants living in the Gyeongbuk region. An average age of the female marriage immigrants who participated in this survey were 28.6 years, and their home countries were the Philippines (32.6%), Vietnam (29.1%), and so on. Exactly 59.3% of subjects had been married for 1~5 years, and 40.7% of the subjects had an education status of less than middle school graduation. The majority of them (65.1%) had one more children, and 51.2% of subjects were a part of a nuclear-family, with the husband's age between 40~49 years old (58.1%). Concern for nutrition label was significantly different according to number of children (P<0.01), period of marriage (P<0.001), and education level (P<0.05). It was demonstrated that a higher level of education was associated with a higher need to learn about nutritional information. Understanding nutritional facts and knowledge was significantly higher among the women with two children than no child (P<0.05), period of marriage >10 years than <1 year (P<0.01), and education level of college & university graduation than less than middle school (P<0.05). Sixty percent of the women surveyed participated in the education program of 'Korean language' as they were in their country, and the most preferred education program was 'Korean dietary life and culture' (39.5%). Regarding participation and educational method, the majority of subjects responded that they wanted to learn nutritional education in a cooking academy or school (52.9%) and public health center (34.1%).

The BIDAS Program : Bioassay Data Analysis Software for Evaluating Radionuclide Intake and Dose (BIDAS프로그램 : 방사성 핵종의 섭취량과 선량 평가용 생물학적분석 자료 해석 소프트웨어 프로그램)

  • Tae-Yong Lee;Jong-Kyung Kim;Jong-Il Lee;Si-Young Chang
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.2 no.2
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    • pp.113-124
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    • 2004
  • A computer software program, called BIDAS (BIoassay Data Analysis Software) is developed to interpret the bioassay measurement data in terms of intakes and the committed effective dose using the human respiratory tract model (HRTM), gastrointestinal tract (GI-tract) model and biokinetic models currently recommended by the International Commission on Radiological Protection (ICRP) to describe the behavior of the radioactive materials within the body. The program consists of three modules; first, a database module to manage the bioassay data, second, another databasee module to store the predicted bioassay quantities of each radionuclide and finally, a computational module to estimate the intake and committed effective dose calculated with the bioassay quantity measurement values from either an acute or chronic exposure of the radionuclies within the body. This paper describes the features of the program as well as the quality assurance check results of the BIDAS software program.

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