Earticle

이 글은 계약법적 관점에서 스마트 계약의 성립에 중점을 두 고 논하고 있다. 여기에서 주목할 것은 스마트 계약의 성립이 전통적 계약 성립의 개념에 해당하는지 여부이다. 즉 스마트 계 약이 기존의 계약과 동일한 의미를 가지는지, 그렇지 않으면 계 약 성립의 끝을 의미하는지, 그에 따른 새로운 계약의 시작인지 의 문제를 살펴본다. 그리고 기존 계약법이 원칙적으로 스마트 계약의 성립을 통제할 수 있는지 검토한다. 그렇다면 스마트 계 약이 전통적 계약법을 넘어서는 혁신적 특성은 무엇인지에 대 해서 고찰한다. 이러한 문제의식을 가지고 다음 내용 순으로 살펴본다. 첫째, 계약의 발전 단계와 과학기술의 발전 과정에서 스마트 계약이 출현하게 된 배경을 살펴본다. 그리고 우리 사회에서 스마트 계 약을 어떻게 고려하고 있는지 살펴본다(Ⅱ). 둘째, 스마트 계약 의 개념에 관해 검토한다. 기술적 측면 및 법적 측면에서의 논 의를 정리한다(Ⅲ). 셋째, 계약의 성립을 중심으로 전통적 계약 과 스마트 계약의 정합성에 대하여 평가한다(Ⅳ). 끝으로 스마 트 계약이 계약법의 미래에 어떠한 영향을 미칠 수 있는지를 고찰한다(Ⅴ).

This paper focuses on the establishment of smart contracts from a contractual legal perspective. It is noteworthy here that the establishment of smart contracts corresponds to the concept of establishment of traditional contracts. In other words, the question of whether the smart contract has the same meaning as an existing contract, or the end of the contract, or the start of a new contract accordingly, is examined. In addition, it examines whether existing contract laws can in principle control the establishment of smart contracts. Then, consider what innovative characteristics of smart contracts have beyond the traditional contract law. For this study, the following are discussed. First, it looks at the background of the emergence of smart contracts in the development stage of contracts and in the process of development of science and technology. And it looks at how our society considers smart contracts (Ⅱ). Second, it reviews the concept of smart contracts. It summarizes the discussion in the technical and legal aspects (Ⅲ). Third, it evaluates the consistency between traditional and smart contracts, focusing on the establishment of contracts (IV). Finally, consider how smart contracts can affect the future of contract law (Ⅴ).

This paper suggests a method for developing computer code that can solve inverse heat conduction problem, The concept of the object-oriented development is employed to implement the computer code in an efficient and flexible fashion. The software design is conducted based on the unified modeling language. Furthermore, this paper also explains how to implement the deliverable computer code using the existing software development tools.

To develop computational thinking skills, university students are learning how to solve problems with algorithms, program commands and grammar, and program writing. Because non-computer majors have difficulty with computer programming-related content, they need a learning method to acquire coding knowledge from the process of understanding, interpreting, changing, and improving source codes by themselves. This study explored clone coding, refactoring coding, and coding methods using reconstruction tools, which are practical and effective learning methods for improving coding skills for students who are accustomed to coding. A coding learning process with the code reconstruction principle was designed to help non-computer majors use it to understand coding technology and develop their problem-solving ability and applied the coding technology learning method used in programmer education.

최근 새로운 교육방식과 더불어 신기술 매체를 교육현장에 도입해 효과적으로 활용하려는 노력들이 증 가하고 있으며 특히, 스마트폰을 이용한 모바일 교육에 관심이 두드러지는 경향이 있다. 스마트폰의 많은 보급으로 인해 국내에서도 QR코드의 교육적 활용에 대한 인식이 변화하고 있지만, QR코드를 실제 수업에 보편적으로 적용할 수 있는 연구와 성과는 적은 실정이다. 따라서 이 연구의 목적은 QR코드를 그래픽 프로그램 수업에 적용하여 교육적 효과성을 검증해 보고자 하는데 있으며, 결과는 다음과 같다. 기존의 수업 방식에 비해 QR코드를 활용한 수업방식이 흥미 및 관심, 기대감, 자기주도성 및 학습효과, 만족감의 측면에서 보다 긍정적인 영향을 주는 것을 확인하였다. 이를 통해 본 연구에서 제안한 형태로 다양한 수업 콘텐츠를 개발하고 적용한다면 학습 효과를 향상시키리라 기대된다.

Recently along with the teaching methods, the effort to apply new technology in educational environment is increasing. Especially, it is getting more interesting about mobile education by using smart phone. Because of spreading smart phones, there are changes of recognition to apply the QR codes for educational purpose. However, there are still lack of research and result in order to using the QR codes commonly in classes. Therefore, the purpose of the project is to verify the educational effectiveness by applying QR codes in computer graphics class. The result are as follows; Compared to precious teaching methods, there are several benefits by using QR codes in class such as high interests, attention, expectation, and self-oriented. In addition, it confirmed to give more positive influence on the side of learning effect and satisfaction. Because of those strong positive benefits, we expect to increase the learning effect in educational environment if various educational contents are developed and applied in advance.

D$_2$O에 대한 Butler의 scattering kernel에 관해 조사하였다. 이 kernel을 사용한 전자계산 코드 DEUKER를 개발하였으며 이를 이용하여 산란법칙, 미분산란 단면적 및 전산란 단면적을 계산하였다. D$_2$O 분자내의 어떤 두개 원자간의 산란 영향은 열에너지 영역에서의 산란 중성자 분포를 결정하는데 있어서 중요한 인자가 된다. 따라서 여러 입사 중성자 에너지에 따른 에너지 전달 산란 단면적에 관해 조사하여 이 kernel의 원자로 내의 중성자 분포 계산을 위한 사용 가능성을 연구하였다. 또한 본 연구를 통하여 D$_2$O와 $H_2O$에서의 중성자 산란 과장의 차이점을 밝혔다.

Based on the Butler scattering kernel for D$_2$O, a computer code DEUKEB has been developed to compute the scattering laws, differential scattering cross sections and total scattering cross sections. Interference scattering between ally two atoms of a D$_2$O molecule is important in resolving the distribution of scattered neutrons in thermal energy region. Energy-transfer scattering cross sections are, therefore, studied in the various incident neutron energies. This study may be put in practice to utilize the kernel in determining the neutron spectrum in a reactor system. The study also shows that the scattering process in D$_2$O is somewhat different from that in $H_2O$.

Numerical prediction of fission product plateout and circulating coolant activities under normal operating conditions is crucial in the design of a high temperature gas-cooled reactor (HTGR). The results are used for the maintenance and repair of the components as well as the safety analysis regarding early source terms under loss of coolant accident scenarios. In this work, a new computer code named POSCA (Plate-Out Surface and Circulating Activities) was developed based on a one-dimensional model to evaluate fission product plateout and circulating coolant activities within the primary circuit of a HTGR. The verification and validation of study for the POSCA code was done using available analytical results and two in-pile experiments (i.e., OGL-1 and VAMPYR-1). The results of the POSCA calculations show that POSCA is able to simulate plateout and circulating coolant activities in a HTGR with fast computation and reasonable accuracy.

A total of 17 experimental data for the onset of slugging, which is assumed to be the precursor of the condensation-induced waterhammer (CIWH), have been obtained for various How rates of water Incorporating the most recent correlations of interfacial heat transfer and friction factor developed for a circular geometry and using an improved criterion of transition from stratified to a slug flow, two existing analytical models to predict lower and upper bounds for CIWH have been upgraded. Applicability of the present as well as existing CIWH models has been tested by comparison with two sets of CIWH data. The result of this comparison shows that the applicability of the present as well as existing models is reasonably good. Based on the present models for CIWH, a computer code entitled as“KAIST-CIWH”has been developed and sample guide charts to find CIWH free regions for a given combination of major flow parameters in a long horizontal pipe have been presented along with the results of parametric studies of major parameters (D, P, $T_{f,in}$, and L/D) on the critical inlet water flow rate（$W_{f,in}_crit$ for both lower and upper bounds. In addition, two simple formulas for lower and upper bounds that can be used in an emergency for quick results have been presented.

중대사고시 LMFBR의 에어로졸(aerosol) 동특성을 살피기 위해 전산코드인 MCAD (Multicomponent Aerosol Dynamics)가 개발되었다. 사고경과에 따른 두 방사능원의 상대적인 충돌확률을 적용하여 에어로졸계를 모사할 수 있다. Brownian 확산과 중력작용에 의한 결합 및 제거과정을 고려했으며, 입자형태를 묘사하기 위해 밀도보정과 형태요소(shape factor)를 동시에 고려하였다. ORNL의 NSPP-300 계열 실험자료와 기존의 코드를MCAD의 입증에 이용하였다. 그 결과 MCAD의 계산치와 실험치 및 기존의 코드 계산값이 일치함을 보여준다. 여러 입력자료의 불화실한 값들을 정의하고, 그들값의 한계로 설정하기 위하여 불확실성 및 민감도해석을 수행하였다. 14개의 입력자료를 선택하여 실험계획법과 Latin hypercube sampling에 의한 입력자료를 조합하여 그 회귀 (regression) 정도를 반응표면 계획법(Response surface method)에 의해 구하였다. 각 변수들의 중요성 및 시간경과에 따른 그들의 상대적인 등위를 결정하기 위하여 단계식 회귀방법 (Stepwise regression method)을 고려했다. LHS에 의한 회귀모형에 Monte Carlo Method를 적용하여 계산값 및 변수들에의 신뢰도를 향상시켰다.

To analyze the aerosol dynamics in severe accidents of LMFBR, a new computer code entitled MCAD (Multicomponent Aerosol Dynamics) has been developed. The code can treat two component aerosol system using relative collision probability of each particles as sequences of accident scenarios. Coagulation and removal mechanisms incorporating Brownian diffusion and gravitational sedimentation are included in this model. In order to see the effect of particle geometry, the code makes use of the concept of density correction factor and shape factors. The code is verified using the experimental result of NSPP-300 series and compared to other code. At present, it fits the result of experiment well and agrees to the existing code. The input variables included are very uncertain. Hence, it requires uncertainty and sensitivity analysis as a supplement to code development. In this analysis, 14 variables are selected to analyze. The input variables are compounded by experimental design method and Latin hypercube sampling. Their results are applied to Response surface method to see the degree of regression. The stepwise regression method gives an insight to which variables are significant as time elapse and their reasonable ranges. Using Monte Carlo Method to the regression model of LHS, the confidence level of the results of MCAD and their variables is improved.

The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal-hydraulic design and performance analysis computer code for a countercurrent H-OTSG installed in a small pressurized water reactor. The H-OTSG is represented by one characteristic tube in the model. The secondary side of the H-OTSG is divided into single-phase liquid region, nucleate boiling region, postdryout region, and single-phase vapor region. Different heat transfer correlations and pressure drop correlations are reviewed and applied. To benchmark the developed physical models and the computer code, H-OTSGs developed in Marine Reactor X and System-integrated Modular Advanced ReacTor are simulated by the code, and the results are compared with the design data. The overall characteristics of heat transfer area, temperature distributions, and pressure drops calculated by the code showed general agreement with the published data. The thermal-hydraulic characteristics of a typical countercurrent H-OTSG are analyzed. It is demonstrated that the code can be utilized for design and performance analysis of an H-OTSG.

원자로 내에서 연소 중인 핵연료나 저장 또는 재처리 중인 사용후핵연료의 성분으로서 시설의 공정설계, 안전성분석 및 차폐설계에 중요한 입력자료가 되는 핵분열생성물질, 방사화생성물 및 악티나이드의 핵종 농도와 이에 대응하는 방사능 강도의 기기 별 시간변 화율을 해석할 수 있는 코드 개발할 목적으로 MULTISAMS 정상 평형상태 모델을 구현하였다. MULTISAMS 코드의 반응공정 모델은 서로 연결되어 있으며 내부에 방사성물질의 혼합유체가 순환하는 세 종류의 반응기(원자로, 열교환기 및 화학반응기) 계통에서 자연적 또는 설계에 의해 일어나는 현상으로서; 반응기 간의 물질 흐름; 각 반응기 내에서 방사성 붕괴, 변환, 이동과 중성자 흡수 및 핵분열; 외부로부터 특정 핵종의 유입혹은 유출을 고려한 시간종속 핵종농도보존방정식 이론에 근거한다. 코드의 유용성 및 신뢰성을 검증하기 위해 현재 개념설계가 진행 중인 AMBIDEXTER원자력 에너지시스템을 대상으로 ORIGEN2 계산과 비교하였다. 두 코드 간의 입력조건과 배경이론차이점 때문에 절대적 비교가 불가능하므로 단순이론의 중간매개코드로서 SAMS를 이용한 2단계 비교방법을 따랐다. 결론은 MULTISAMS는 ORIGEN2 계산의 수렴치와 근사하게 일치하면서 ORIGEN2 가 다룰 수 없는 핵주기 연속후처리공정의 정상가동 시 핵종 평형농도를 기기 별로 계산할 수 있다는 장점을 확인하였다.

A PC window-based computer code, CONPAS (CONtainment Performance Analysis System), has been developed to integrate the numerical, graphical, and results-operation aspects of Level 2 probabilistic safety assessments (PSA) for nuclear power plants automatically. As a main logic for accident progression analysis, it employs a concept of the small containment phenomenological event tree (CPET) helpful to trace out visually individual accident progressions and of the detailed supporting event tree (DSET) for its detailed quantification. For the integrated analysis of Level 2 PSA, the code utilizes five distinct, but closely related modules. Its computational feasibility to real PSAs has been assessed through an application to the UCN 3&4 full scope Level 2 PSA. Compared with other existing computer codes for Level 2 PSA, the CONPAS code provides several advanced features: (1) systematic uncertainty analysis / importance analysis / sensitivity analysis, (2) table / graphical display & print, (3) employment of the recent Level 2 PSA technologies, and (4) highly effective user interface. The main purpose of this paper is to introduce the key features of CONPAS code and results of its feasibility study.

A computer code COSMOS has been developed based on the CARO-D5 for the thermal analysis of LWR UO$_2$ and MOX fuel rod under steady-state and transient operating conditions. The main purpose of the COSMOS, which considers high turnup characteristics such as thermal conductivity degradation with turnup and rim formation at the outer part of fuel pellet, is to calculate temperature profile across fuel pellet and fission gas release up to high burnup. A new mechanistic fission gas release model developed based on physical processes has been incorporated into the code. In addition, the features of MOX fuel such as change in themo-mechanical properties and the effect of microscopic heterogeneity on fission gas release have been also taken into account so that it can be applied to MOX fuel. Another important feature of the COSMOS is that it can analyze fuel segment refabricated from base irradiated fuel rods in commercial reactors. This feature makes it possible to analyze database obtained from international projects such as the MALDEN and RISO, many of which were collected from refabricated fuel segments. The capacity of the COSMOS has been tested with some number of experimental results obtained from the HALDEN, RISO and FIGARO programs. Comparison with the measured data indicates that, although the COSMOS gives reasonable agreement, the current models need to be improved. This work is being performed using database available from the OECD/NEA.

The present paper reports the development of a computational code based on the Adaptive Group of Ink Drop Spread (AGIDS) for reconstruction of the neutron noise sources in reactor cores. AGIDS algorithm was developed as a fuzzy inference system based on the active learning method. The main idea of the active learning method is to break a multiple input-single output system into a single input-single output system. This leads to the ability to simulate a large system with high accuracy. In the present study, vibrating absorber-type neutron noise source in an International Atomic Energy Agency-two dimensional reactor core is considered in neutron noise calculation. The neutron noise distribution in the detectors was calculated using the Galerkin finite element method. Linear approximation of the shape function in each triangle element was used in the Galerkin finite element method. Both the real and imaginary parts of the calculated neutron distribution of the detectors were considered input data in the developed computational code based on AGIDS. The output of the computational code is the strength, frequency, and position (X and Y coordinates) of the neutron noise sources. The calculated fraction of variance unexplained error for output parameters including strength, frequency, and X and Y coordinates of the considered neutron noise sources were $0.002682{\sharp}/cm^3s$, 0.002682 Hz, and 0.004254 cm and 0.006140 cm, respectively.

The approximated nonlinear least squares (ALS) method has been used for adjusting unknown universal constants in the complex simulation code, which is very time-consuming to execute. The ALS tunes or calibrates the computer code by minimizing the squared difference between real observations and computer output using a surrogate such as a Gaussian process model. A potential drawback of the ALS is that it does not take the uncertainty in the approximation of the simulation by a surrogate model into account. The calibration result is too dependent on selection of a surrogate model. To address these problems, we consider a simple ensemble method that averages the respective estimates from four different models. A total of three test functions in different conditions are examined for a comparative analysis. Based on the test function study, we find that the ensemble method by four models provides better results than the ALS method. We also review some calibration methods including a generalized ALS, an iterative version of ALS, and likelihood-based method. We provide a brief discussion for comparison and future direction.

Among those tests performed during the Yonggwang Nuclear Power Plant Units 3 and 4 (YGN 3&4) Power Ascension Test period, the Loss of a Main Feedwater Pump test at l00% power is one of the major test which characterize the capability of YGN 3&4. In this event, one of the two normally operating main feedwater pumps is tripped resulting in a 50% reduction in the feedwater flow. Unless the NSSS and Turbine/Generator control systems actuate properly, the reactor will be tripped on low SG water level or high pressurizer pressure. The test performed at Unit 3 was successful by meeting all acceptance criteria, and the plant was stabilized at a reduced power level without reactor trip. The measured test data for the major plant parameters are compared with the predictions made by the KISPAC computer code, an updated best-estimate plant performance analysis code, to verify and validate its applicability. The comparison results showed good agreement in the magnitude as well as the trends of the major plant parameters. Therefore, the KISPAC code can be utilized for the best-estimate nuclear power plant design and simulation tool after a further verification using other plant test data.

A new three-dimensional (3D) Monte Carlo ion implantation simulator, TRICSI, has been developed to investigate 3D mask effects in the typical mask structure for ion implantation into crystalline silicon. We present the mask corner and mask size effects of implanted boron range profiles, and also show the calculated damage distributions by applying the modified Kinchin-Pease equation in the single-crystal silicon target. The simulator calculates accurately and efficiently the implanted-boron range profiles under the relatively large implanted area, using a newly developed search algorithm for the collision partner in the single-crystal silicon. All of the typical implant parameters such as dose, tilt and rotation angles, in addition to energy can be used for the 3D simulation of ion implantation.

During the development process of a thermal-hydraulic system code, a non-regression test (NRT) must be performed repeatedly in order to prevent software regression. The NRT process, however, is time-consuming and labor-intensive. Thus, automation of this process is an ideal solution. In this study, we have developed a program to support an efficient NRT for the SPACE code and demonstrated its usability. This results in a high degree of efficiency for code development. The program was developed using the Visual Basic for Applications and designed so that it can be easily customized for the NRT of other computer codes.