• Title/Summary/Keyword: Program Codes

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Analysis of control rod driving mechanism nozzle rupture with loss of safety injection at the ATLAS experimental facility using MARS-KS and TRACE

  • Hyunjoon Jeong;Taewan Kim
    • Nuclear Engineering and Technology
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    • v.56 no.6
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    • pp.2002-2010
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    • 2024
  • Korea Atomic Energy Research Institute (KAERI) has operated an integral effect test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS), with reference to the APR1400 (Advanced Power Reactor 1400) for tests for transient and design basis accidents simulation. A test for a loss of coolant accident (LOCA) at the top of the reactor pressure vessel (RPV) had been conducted at ATLAS to address the impact of the loss of safety injections (LSI) and to evaluate accident management (AM) actions during the postulated accident. The experimental data has been utilized to validate system analysis codes within a framework of the domestic standard problem program organized by KAERI in collaboration with Korea Institute of Nuclear Safety. In this study, the test has been analyzed by using thermal-hydraulic system analysis codes, MARS-KS 1.5 and TRACE 5.0 Patch 6, and a comparative analysis with experimental and calculation results has been performed. The main objective of this study is the investigation of the thermal-hydraulic phenomena during a small break LOCA at the RPV upper head with the LSI as well as the predictability of the system analysis codes after the AM actions during the test. The results from both codes reveal that overall physical behaviors during the accident are predicted by the codes, appropriately, including the excursion of the peak cladding temperature because of the LSI. It is also confirmed that the core integrity is maintained with the proposed AM action. Considering the break location, a sensitivity analysis for the nodalization of the upper head has been conducted. The sensitivity analysis indicates that the nodalization gave a significant impact on the analysis result. The result emphasizes the importance of the nodalization which should be performed with a consideration of the physical phenomena occurs during the transient.

U.S. GENERATION IV REACTOR INTEGRATED MATERIALS TECHNOLOGY PROGRAM

  • Corwin William R.
    • Nuclear Engineering and Technology
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    • v.38 no.7
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    • pp.591-618
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    • 2006
  • An integrated R&D program is being conducted to study, qualify, and in some cases, develop materials with required properties for the reactor systems being developed as part the U.S. Department of Energy's Generation IV Reactor Program. The goal of the program is to ensure that the materials research and development (R&D) needed to support Gen IV applications will comprise a comprehensive and integrated effort to identify and provide the materials data and its interpretation needed for the design and construction of the selected advanced reactor concepts. The major materials issues for the five primary systems that have been considered within the U.S. Gen IV Reactor Program-very high temperature gas-cooled, supercritical water-cooled, gas-cooled fast spectrum, lead-cooled fast spectrum, and sodium-cooled fast spectrum reactors-are described along with the R&D that has been identified to address them.

Performance Simulation of a Ramjet Using Visual C++ Program

  • Owino, George Omollo;Kong, Chang-Duk
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2008.03a
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    • pp.499-502
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    • 2008
  • This paper presents on research findings of how Visual C++ program can be used to generate codes capable of performing ramjet engine simulation To understand the diversity and applicability of this tool an arbitrary ramjet model will be considered for which generated output values will be compared with those from a commercial program GASTURB 9 iterated under the same input parameters. Several governing thermodynamic equations will first be discussed in order that we understand the fundamental idea behind values printed out on the GUI. C++ compiler was chosen as a tool of use due to its availability, ease of use, ability to compute functions faster and uniquely possible to make a stand alone GUI executable in DOS mode. The program is developed in such a way that given the ambient flight conditions, burner exit temperature and several geometry areas the program generates its own input values used in the succeeding stations. A close resemblance of output values that define performance and thermodynamic state of the engine was realized between GASTURB 9 and using this code made from C++ compiler.

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Ethical Codes in Scientific and Technological Communities and the Case of Korea (과학기술단체의 윤리강령과 한국의 사례)

  • Choi, Kyung-Hee;Kim, Eun-Cheol;Song, Sung-Soo
    • Journal of Engineering Education Research
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    • v.12 no.1
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    • pp.82-94
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    • 2009
  • This paper examines the roles, main contents, and writing guidelines of ethical codes, and analyses the developmental process and characteristics of ethical codes of scientific and technological communities in Korea. Korean communities occasionally tried for ethical codes from the 1970s to the 1990s, and have paid a serious attention to ethical codes in the 2000s. The forms of ethical codes became more sophisticated pursuing detailed commentary and ethical education. The focus of contents changed from professional dignity to social responsibility, and the importance of research integrity became embossed in the 2000s. Scientific and technological communities in Korea should make or revise ethical codes with self-imposed control considering realistic operation.

Neutronics analysis of TRIGA Mark II research reactor

  • Rehman, Haseebur;Ahmad, Siraj-ul-Islam
    • Nuclear Engineering and Technology
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    • v.50 no.1
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    • pp.35-42
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    • 2018
  • This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, ${\theta}$) and 3-D (r, ${\theta}$, z), using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied using various libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0), Joint Evaluated Fission and Fusion File (JEFF-3.1), Japanese Evaluated Nuclear Data Library (JENDL-3.2), and Joint Evaluated File (JEF-2.2) nuclear data. The simulation results showed that the multiplication factor calculated for all these data libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134 was also calculated with different homogenization approaches. A comparison was made with experimental and reported Monte Carlo results, and it was found that, using proper homogenization of absorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantly improved.

The Development of Discharge Analysis Educational Program on NCS-Based for Medical Information Management (NCS 기반 의료정보관리를 위한 퇴원분석 교육프로그램 개발)

  • Choi, Joon-Young
    • The Journal of the Korea institute of electronic communication sciences
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    • v.12 no.5
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    • pp.957-964
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    • 2017
  • In this study, It developed a program to carry out the training courses for NCS based medical information management tasks and to can understand the practical working knowledge of learners. This program is an educational program that can generate medical information by analyzing data of medical records after generating and storing data of medical records. Because the contents of the medical records vary and there are quantitative differences in the medical records, the contents of the medical records can be summarized and stored in the discharge analysis program for the standard of educational data. The medical terminology DB, medical terminology related DB, medical care related DB by the NCS ability unit element can be constructed and managed using the program. The following are the contents that can be learned through operation of the program. first, it's can understand Medical information DB management regulations through understanding sturucture of database. Second, it can understand the structure and function of the diagnostic code and medical practice code that are input to the discharge analysis program. The diagnostic codes and medical practice codes entered in the discharge analysis program can be searched and analyzed by each fields. Third, It can be advance medical information management ability by inputting and extracting data and generating medical information. In this study, It developed program that Students can be obtained Knowledge of medical information management and improved management competency by generate and analyze medical record data using discharge analysis program.

Automated Test Data Generation based on Executable Object Codes (실행가능 목적 코드를 기반으로 하는 자동 테스트 데이터 생성)

  • Chung, In-Sang
    • The Journal of the Institute of Internet, Broadcasting and Communication
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    • v.12 no.2
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    • pp.189-197
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    • 2012
  • It is usual for test data generation to be performed using either high-level specifications or source codes written in high-level programming languages. In certain circumstances, however, such information is not always available. This paper presents a technique that generates test data based on executable object codes. The proposed technique makes use of a very simple function minimization technique without sophisticated object code analysis and produces test data dynamically. We have conducted a simple experiment to evaluate the effectiveness of the proposed test data generation technique with a triangle classification program to show that branch coverage can be easily achieved.

Flexural strength of circular concrete-filled tubes

  • Lee, Minsun;Kang, Thomas H.-K.
    • Advances in Computational Design
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    • v.1 no.4
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    • pp.297-313
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    • 2016
  • The flexural strength of circular concrete-filled tubes (CCFT) can be estimated by several codes such as ACI, AISC, and Eurocode 4. In AISC and Eurocode, two methods are recommended, which are the strain compatibility method (SCM) and the plastic stress distribution method (PSDM). The SCM of AISC is almost the same as the SCM of the ACI method, while the SCM of Eurocode is similar to the ACI method. Only the assumption of the compressive stress of concrete is different. The PSDM of Eurocode approach is also similar to the PSDM of AISC, but they have different definitions of material strength. The PSDM of AISC is relatively easier to use, because AISC provides closed-form equations for calculating the flexural strength. However, due to the complexity of calculation of circular shapes, it is quite difficult to determine the flexural strength of CCFT following other methods. Furthermore, all these methods give different estimations. In this study, an effort is made to review and compare the codes to identify their differences. The study also develops a computing program for the flexural strength of circular concrete filled tubes under pure bending that is in accordance with the codes. Finally, the developed computing algorithm, which is programmed in MATLAB, is used to generate design aid graphs for various steel grades and a variety of strengths of steel and concrete. These design aid graphs for CCFT beams can be used as a preliminary design tool.

Unified Version Management of KISTI-ACOMS (온라인논문투고관리시스템(KISTI-ACOMS)의 통합 버전 관리)

  • Jeong, hee-seok;Choi, myung-seok;Park, jae-won;Kang, moo-yeong
    • Proceedings of the Korea Contents Association Conference
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    • 2007.11a
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    • pp.381-385
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    • 2007
  • KISTI-ACOMS(Online peer review system), which is installated for more than 270 learned societies, is getting harder to manage large amount of source codes, because the number of installation has been growing much faster than we expected at the development time. Moreover the fundamental problem of this system, that frequent requests of modification from societies comes with modification of source codes, makes it more difficult to manage this program systematically. Thereupon we formulated a system to provide services for many societies using one version of source code, and this system is expected to reduce the managed amount of source codes and to make us cope with requests of societies of more positive than until now.

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Korean and United States: Comparison of Costs of Nursing Interventions (NIC과 연계된 산부인과 환자 간호중재에 대한 한국 건강보험 수가체계와 미국 ABC 코드체계와의 수가 비교 분석)

  • Hong, Sung-Jung;Lee, Eun-Joo
    • Korean Journal of Adult Nursing
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    • v.24 no.4
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    • pp.358-369
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    • 2012
  • Purpose: This study was performed to compare the costs of nursing interventions implemented for the obstetrical and gynecological patients using Korean Reimbursement System and ABC codes system developed in the US for costing out interventions performed by health care professional. Methods: First, the narrative data on nursing interventions were extracted from electronic medical record system of a tertiary university and mapped with Nursing Intervention Classification (NIC) by two researchers until 100% consent was reached. Narrative nursing interventions mapped with NIC were then remapped with ABC codes system using the electronic program developed in the research. The mapping data were analyzed with real numbers, frequency, percentage, mean, and standard deviation. Results: More nursing interventions were mapped with ABC codes than Korean reimbursement system. Total of 97 different types of narrative interventions could be mapped with NIC, 43 NIC interventions could be reimbursed by ABC code but only 16 NIC interventions were reimbursed by Korea Reimbursement System. Conclusion: Korean medical insurance fee system needs amendment to include more comprehensively interventions performed by nurses which are very important to patient outcomes. Further study is needed to develop strategies to costing out nursing interventions.