• Title/Summary/Keyword: preliminary calculation

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Role of Capital Expenditure in the Economic Evaluation of National R&D Investment Project for Cooperative Research of University-industry-research Institute: Cases of Woodchip Power Plant Construction (국가 R&D 산학연협동연구 투자계획안의 경제성 평가에서 자본적 지출의 역할: 목재칩을 이용한 발전소 건설의 경우를 중심으로)

  • YEO, Heejung
    • Journal of Korea Technology Innovation Society
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    • v.18 no.4
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    • pp.621-640
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    • 2015
  • The aim of this study is to provide evidence of how a change in the process of calculating the economic valuation of a project can affect the decision regarding national R&D investment. The paper examines a R&D project of cooperative research program of university-industry-research institute for the construction of a woodchip power plant to explore the role of capital expenditure in the economic evaluation of an investment project. The paper finds that the simple introduction of capital expenditure in the profitability analysis affects the perspectives on the construction plan. The results of this study indicate that standardization of the calculation process that takes different characteristics of industries into account is needed in the preliminary feasibility study of national R&D projects.

Preliminary Analysis of In-reactor Behavior of Three MOX Fuel Rods in the Maiden Reactor

  • Koo, Yang-Hyun;Lee, Byung-Ho;Sohn, Dong-Seong
    • Proceedings of the Korean Nuclear Society Conference
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    • 1999.10a
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    • pp.248.1-248
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    • 1999
  • Preliminary analysis of in-reactor thermal performance of three MOX fuel rods, which are going to be irradiated in the Halden reactor beginning in the first Quarter of the year 2000 under the framework of the OECD Halden Reactor Programme, have been conducted by using the computer code COSMOS to ensure their safe operation. Parametric studies have been carried out to investigate the effect of uncertainties on in-reactor behavior by considering the four kinds of uncertainties; thermal conductivity, linear power, manufacturing parameters, and model constants. The analysis shows that, in the case of annular MOX -1 fuel, calculation results for thermal performance vary widely depending on the selection of model constants for fission gas release (FGR). On the contrary, the thermal performance of solid MOX - 3 fuel does not depend on the choice of FGR constants to a large extent as MOX-I, because the fuel temperature is very high in the MOX-3 irrespective of the choice of FGR constants and hence the capacity of grain boundaries to retain gas atoms is not large enough to accommodate the number of gas atoms reaching the grain boundaries. It is planned that when the data on microstructure and thermal conductivity for each type of MOX fuel are available, new analysis will be made using these information. In addition, FGR model constants will be derived from the measured fuel centerline temperature, rod internal pressure and other related data.

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A Prediction Model of the Sum of Container Based on Combined BP Neural Network and SVM

  • Ding, Min-jie;Zhang, Shao-zhong;Zhong, Hai-dong;Wu, Yao-hui;Zhang, Liang-bin
    • Journal of Information Processing Systems
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    • v.15 no.2
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    • pp.305-319
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    • 2019
  • The prediction of the sum of container is very important in the field of container transport. Many influencing factors can affect the prediction results. These factors are usually composed of many variables, whose composition is often very complex. In this paper, we use gray relational analysis to set up a proper forecast index system for the prediction of the sum of containers in foreign trade. To address the issue of the low accuracy of the traditional prediction models and the problem of the difficulty of fully considering all the factors and other issues, this paper puts forward a prediction model which is combined with a back-propagation (BP) neural networks and the support vector machine (SVM). First, it gives the prediction with the data normalized by the BP neural network and generates a preliminary forecast data. Second, it employs SVM for the residual correction calculation for the results based on the preliminary data. The results of practical examples show that the overall relative error of the combined prediction model is no more than 1.5%, which is less than the relative error of the single prediction models. It is hoped that the research can provide a useful reference for the prediction of the sum of container and related studies.

Preliminary ALARA residual radioactivity levels for Kori-1 decommissioning and analysis of results and effects of remediation area

  • Seo, Hyung-Woo;Yu, Ji-Hwan;Kim, Gi-Lim;Son, Jin-Won
    • Nuclear Engineering and Technology
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    • v.54 no.3
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    • pp.1136-1144
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    • 2022
  • The effects of nearby residents and the public by the residual contamination from the decommissioning of nuclear facilities should comply with the dose criteria, and whether additional remediation action is necessary from the ALARA perspective must be determined. Therefore, we analyzed the requirements of ALARA action levels and performed preliminary ALARA evaluation. The ratio of residual contamination concentration to DCGL was calculated for the basement fill and the building occupancy mode. The results showed that the additional remediation actions below DCGL are not justified. In addition, we analyzed the effect of remediation area. It was noted that the increase of the remediation area showed a positive correlation with the Conc/DCGL value in the basement fill mode. On the other hand, in the building occupancy mode, since the floor area of the building is the target of remediation and has the effect of increasing the same as the evaluation area of the building occupants, but due to the difference in the amount of increase, the Conc/DCGL showed a negative correlation. We expect the approach and method of ALARA evaluation can be utilized for concrete cost-benefit calculation during the decommissioning or at the time of remediation.

Development of Standard Estimates for Garden Construction: Focused on Planting

  • Hong, Kwang-Pyo;Lee, Hyukjae
    • Journal of People, Plants, and Environment
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    • v.22 no.5
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    • pp.467-480
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    • 2019
  • Standard estimates are the numerical data of a unit quantity required for construction work such as the amount of materials, manpower, and the use of equipment required and are also a basis to calculate construction costs. Unfortunately, standard estimates for construction have also been used for garden construction these days as no standard estimates for garden construction have been developed or documented until now. As a result, many problems have arisen at garden construction sites since landscape construction and garden construction differ in terms of scope, size, design and construction methods. The purpose of this study was to develop standard estimates for garden construction for proper calculation of the cost of garden construction and to ensure gardens are created following appropriate construction processes. In order to develop standard estimates for garden construction, a preliminary survey was conducted on experts to understand current issues at first. After that, a questionnaire survey was done to examine problems of construction processes and ways of improvement, and on-site inspections were conducted utilizing CCTVs at construction sites to identify the actual amount of manpower required on site. Based on the results of the surveys and on-site inspections, a draft version of standard estimates for 5 types of planting work for garden construction was developed. Developing standard estimates for garden construction will serve as a stepping stone for the transparent and proper compensation for garden construction work, which will not only contribute to addressing issues between consumers and construction companies, but also to the stabilization of market economy and job creation.

STATE OF THE ART IN USING BEST ESTIMATE CALCULATION TOOLS IN NUCLEAR TECHNOLOGY

  • D'AURIA FRANCESCO;ANIS BOUSBIA-SALAH;PETRUZZI ALESSANDRO;NEVO ALESSANDRO DEL
    • Nuclear Engineering and Technology
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    • v.38 no.1
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    • pp.11-32
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    • 2006
  • System thermal-hydraulic codes have been used in the past decades in the areas of design, operation, licensing and safety of Nuclear Power Plants (NPPs). The development and validation of these codes have reached a high degree of maturity, through the consideration of huge experiments and advanced numerical models. Nowadays, the analyses are based upon realistic approaches rather than the conservative evaluation models. However the applications of these computational tools require preliminary qualification issues. Although huge amounts of financial and human resources have been invested for the development and improvement of codes, the calculation results are still affected by errors. In the sophisticated nuclear technology, design and safety of NPP, these errors must be quantified. An overview of the state of the art of the current thermal-hydraulic system code is developed and the need of uncertainty analysis in code calculations is emphasized. Several sources of uncertainty have been classified and commented, and typical applications of such methods are shown.

Preliminary Results on Food Consumpt ion Rates for Off-site Dose Calculation of Nuclear Power Plants (원전 주변 주민의 방사선량 평가를 위한 음식물 섭취량 조사 예비결과)

  • Lee Gab-Bock;Chung Yang-Geun;Bang Sun-Young;Kang Duk-Won
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.307-316
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    • 2005
  • The Internal dose by food consumption mostly account for radiological dose of public around nuclear poller plants(NPP). But, food consumption rate applied to off-site dose calculation in Korea which is the result of field investigation around Kori NPP by the KAERI in 1988, is not reflected of the latest dietary characteristics. 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. To update the food consumption rates of the maximum individual the analysis of the national food investigation results and field surveys around nuclear power plant sites have been carried out.

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Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model

  • Farkas, Istvan;Hutli, Ezddin;Farkas, Tatiana;Takacs, Antal;Guba, Attila;Toth, Ivan
    • Nuclear Engineering and Technology
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    • v.48 no.4
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    • pp.941-951
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    • 2016
  • The aim of this work is to simulate the thermohydraulic consequences of a main steam line break and to compare the obtained results with Rossendorf Coolant Mixing Model (ROCOM) 1.1 experimental results. The objective is to utilize data from steady-state mixing experiments and computational fluid dynamics (CFD) calculations to determine the flow distribution and the effect of thermal mixing phenomena in the primary loops for the improvement of normal operation conditions and structural integrity assessment of pressurized water reactors. The numerical model of ROCOM was developed using the FLUENT code. The positions of the inlet and outlet boundary conditions and the distribution of detailed velocity/turbulence parameters were determined by preliminary calculations. The temperature fields of transient calculation were averaged in time and compared with time-averaged experimental data. The perforated barrel under the core inlet homogenizes the flow, and therefore, a uniform temperature distribution is formed in the pressure vessel bottom. The calculated and measured values of lowest temperature were equal. The inlet temperature is an essential parameter for safety assessment. The calculation predicts precisely the experimental results at the core inlet central region. CFD results showed a good agreement (both qualitatively and quantitatively) with experimental results.

A Study on Development Standard Calculation Program of Forest Road Drainage Facilities (임도 배수시설 규격 산정 프로그램 개발에 관한 연구)

  • Choi, Yeon-Ho;Lee, Joon-Woo;Kim, Myeong-Jun
    • Journal of Korean Society of Forest Science
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    • v.100 no.1
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    • pp.25-33
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    • 2011
  • The purpose of this study is to develop a standard calculation program of forest road drainage facilities that may help forest road designers to design forest road drainage facilities more conveniently and precisely. Especially, the characteristics of this program is that the forest road designers may calculate the amount of outflow in the basin using rainfall intensity data conveniently, without the data designers should acquire through site measurements when they carry out indoor preliminary measurements before they go out for outdoor measurements. In this manner, excessive design may be restrained by offering minimum standard calculation for drainage structures. And also this study was designed to facilitate proper layout of drainage structures by calculating outflow discharge of each basin where forest roads will be installed. Especially, this study will contribute to leveling-up of forest design techniques as the researcher has prepared the reports on whole process of drain pipe installation and provided them in the form of computer file or printout, which show a rational design process, and make it possible to modify in case of an error.

Unified calculation model for the longitudinal fundamental frequency of continuous rigid frame bridge

  • Zhou, Yongjun;Zhao, Yu;Liu, Jiang;Jing, Yuan
    • Structural Engineering and Mechanics
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    • v.77 no.3
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    • pp.343-354
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    • 2021
  • The frequencies formulas of the bridge are of great importance in the design process since these formulas provide insight dynamic characteristics of the structure, which guides the designers to parametric analyses and the layout of the bridge in conceptual or preliminary design. Continuous rigid frame bridge is popular in the mountainous area. Mostly, this type of bridge was simplified either as a girder or cantilever when calculating the frequency, however, studies showed that the different configuration of the bridge made the problem more complex, and there is no unified fundamental calculation pattern for this kind of bridge. In this study, an empirical frequency equation is proposed as a function of pier's height, stiffness of pier and the weight of the structure. A unified fundamental frequency formula is presented based on the energy principle, then the typical continuous rigid frame bridge is investigated by finite element method (FEM) to study the dynamic characteristics of the structure, and then several key parameters are investigated on the effect of structural frequency. These parameters include the number, position and stiffness of the tie beam. Nonlinear regression analyses are conducted with a comprehensive statistical study from plenty of engineering structures. Finally, the proposed frequency equation is validated by field test results. The results show that the fundamental frequency of the continuous rigid frame bridge increases more than 15% when the tie beams are set, and it increases with the stiffness ratio of tie beam to pier. The results also show that the presented unified fundamental frequency has an error of 4.6% compared with the measured results. The investigation can predicate the approximate longitudinal fundamental frequency of continuous ridged frame bridge, which can provide reference for the seismic response and dynamic impact factor design of the pier.