• Title/Summary/Keyword: 에너지코드

검색결과 413건 처리시간 0.03초

Numerical Calculation of λ-Mode of the Diffusion Equation (수치해법을 이용한 중성자 확산방정식의λ-Mode 계산)

  • Noh, T.W.;Oh, S.K.;Kim, S.Y.;Kim, C.H.
    • Nuclear Engineering and Technology
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    • 제19권4호
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    • pp.310-316
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    • 1987
  • A successive iteration method to calculate the λ-modes of the diffusion equation was developed. The 2-group, 3-dimensional computer code MOGEN was developed to implement this method, The accuracy of the method was demonstrated using 2-dimensional bare homogeneous rectangular reactor. The numerical solution shows good agreement with the analytic solution in terms of eigenvalue and eigenfunction As for the standard CANDU-600 reactor, the 2-dimensional modes were generated and these represent the conventional mode characteristics well. Finally, application of theλ-mode in reactor engineering problems is described briefly.

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A Theoretical Calculation of Photon Dose Equivalent Conversion Factor For Extremity Dosimeter (말단선량계의 광자선량당량환산인자에 대한 이론적 계산)

  • Kim, Kwang-Pyo;Lee, Won-Keun;Kim, Jong-Su;Yoon, Yeo-Chang;Yoon, Suk-Chul
    • Journal of Radiation Protection and Research
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    • 제21권1호
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    • pp.41-50
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    • 1996
  • In this study, the theoretical calculation of the air kerma-to-dose equivalent conversion factors was performed with a Monte Carlo N-Particle transport code for the two types of extremity phantom of the ANSI and the KAERI, respectively. Considering the distribution of absorbed dose due to the interaction of homogeneous Parallel broad beam of monoenergetic primary photons in the range between 15keV and 1.5MeV, the air kerma-to-dose equivalent conversion factors based on the kerma approximation were calculated. It is showed that all the theoretical conversion factors of the two types of the extremity phantom for the ANSI and the KAERI agree well with the experimental values of the ANSI N13.32 draft(1995) for each energy within 5.7%, maximum difference ratio, except for 13.6%, difference ratio in the case for the energy of less than 40keV. It is due to uncertainties of experiment occurred in the low X-ray energy range and geometry considered in the MCNP code.

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Research cases and considerations in the field of hydrosystems using ChatGPT (ChatGPT를 활용한 수자원시스템분야 문제해결사례 소개 및 고찰)

  • Do Guen Yoo;Chan Wook Lee
    • Proceedings of the Korea Water Resources Association Conference
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    • 한국수자원학회 2023년도 학술발표회
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    • pp.98-98
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    • 2023
  • ChatGPT(Chat과 Generative Pre-trained Transformer의 합성어)는 사용자와 주고받는 대화의 과정을 통해 질문에 답하도록 설계된 대형언어모델로, 지도학습과 강화학습을 모두 사용하여 세밀하게 조정된 인공지능 챗봇이다. ChatGPT는 주고받은 대화와 대화의 문맥을 기억할 수 있으며, 보고서나 실제로 작동하는 파이썬 코드를 비롯한 인간과 유사하게 상세하고 논리적인 글을 만들어 낼 수 있다고 알려져있다. 본 연구에서는 수자원시스템분야의 문제해결에 있어 ChatGPT의 적용가능성을 사례기반으로 확인하고, ChatGPT의 올바른 활용을 위해 필요한 사항에 대해 고찰하였다. 수자원시스템분야의 대표적인 연구주제인 상수관망시스템의 누수인지와 수리해석을 통한 문제해결에 ChatGPT를 활용하였다. 즉, 딥러닝 기반의 데이터분석을 활용한 누수인지와 오픈소스기반의 수리해석 모델을 활용한 관망시스템 적정 분석을 목표로 ChatGPT와 대화를 진행하고, ChatGPT에 의해 제안된 코드를 구동하여 결과를 분석하였다. ChatGPT가 제시한 코드의 구동결과를 사전에 연구자가 직접 구현한 코드구동 결과와 비교분석하였다. 분석결과 ChatGPT가 제시한 코드가 보다 더 간결할 수 있으며, 상대적으로 경쟁력 있는 결과를 도출하는 것을 확인하였다. 다만, 상대적으로 간결한 코드와 우수한 구동결과를 획득하기 위해서는 해당 도메인의 전문적 지식을 바탕으로 적절한 다수의 질문을 해야 하며, ChatGPT에 의해 작성된 코드의 의미를 명확히 해석하거나 비판적 분석을 하기 위해서는 전문가지식이 반드시 필요함을 알 수 있었다.

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The Analysis of Fire Dispersion Characteristics of Vinyl and Rubber Cords Used Indoors (옥내용 비닐코드 및 고무코드의 화재확산특성 분석)

  • Choi, Chung-Seog;Shong, Kil-Mok;Kim, Dong-Ook;Kim, Dong-Woo;Kim, Young-Seok
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • 제19권1호
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    • pp.130-135
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    • 2005
  • The electrical fire frequently happens through careless use such as poor contact, mechanical stress on power cord sets. In this paper, we simulated a wall-model in order to investigate the patterns of fire dispersion on power cord sets which consists of vinyl cord and rubber cord, etc. The fire progress and dispersive patterns were measured by a high speed imaging system(HG-100K, REDLAKE, USA). From the results, the fire pattern of power cord sets was progressed in order of flashover, scattering and disconnection. The short-circuit of the vinyl cords happened easier than the rubber cords by the external flame. In case vinyl cord is disconnected. the fire progress is not observed because the ignition energy decreases. Whereas, the fire progressed continuously in case of the rubber cord.

Assessment and Improvement of the Horizontal In-Tube Condensation Heat Transfer Model in the MARS code (MARS 코드의 수평관내부 응축열전달 모델 평가 및 개선)

  • Lee, Hyun Jin;Ahn, Tae Hwan;Yun, Byong Jo;Jeong, Jae Jun
    • Journal of Energy Engineering
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    • 제25권1호
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    • pp.56-68
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    • 2016
  • Extensive researches have been carried out for enhancing the safety of nuclear power plants and, especially, the development of passive cooling systems, such as passive containment cooling system (PCCS) and passive residual heat removal system, is increasingly important, where condensation is a crucial heat transfer mechanism. Recently, Ahn & Yun et al. developed a horizontal in-tube condensation heat transfer model as one of the activities for the PCCS development. In this work, we implemented the Ahn & Yun 's condensation heat transfer model into the MARS code and assessed it using the PASCAL experimental data. Based on the results of the assessment, we identified the limitations of the Ahn & Yun 's model and suggested a modified Ahn & Yun 's model, and assessed the model using various experimental data.

Development and Verification of AMBIKIN2D, A Two Dimensional Kinetics Code for Fluid Fuel Reactors (유동핵연료원자로를 위한 이차원 동특성 코드 AMBIKIN2D 개발 및 검증)

  • Lee, Young-Joon;Oh, See-Kee
    • Journal of Energy Engineering
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    • 제17권1호
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    • pp.23-30
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    • 2008
  • The neutron kinetic analysis methods for the molten-salt reactors are quite different from those for conventional solid-fuel reactors, which do not take into account the flowing-fuel-induced neutronics effects. Therefore, for dynamics and safety analyses of the molten-salt reactor systems, the conventional kinetics codes would not be appropriate to accurately predict its transient behaviors. A point-kinetics with flowing- fuel model has been used to assess the fluid-fuel reactor system safety, but recognized as not to be sufficient to simulate spatial distributions of delayed-neutron precursors and neutron populations during transients for given detail reactor models. In order to meet this requirement, AMBIKIND, a 2-group, 2-dimensional neutron kinetics code suitable for the molten-salt reactor systems was developed. This paper explains the code's theoretical and numerical descriptions and, as a part of its verification, includes some simulation results of MSRE stability experiments. Even though the present reactor model does not include the recirculation effect of the fuel-salt through the reactor system, the AMBIKIN2D code should be able to predict the power and phase shift at various power levels and reactivity insertions with better accuracy.

Assessment of MARS Multi-dimensional Two-phase Turbulent Flow Models for the Nuclear System Analysis (발전소 계통해석을 위한 MARS 코드의 다차원 이상 난류 유동 모델 검증계산)

  • Lee S.M.;Lee U.C.;Bae S.W.;Chung B.D.
    • Journal of Energy Engineering
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    • 제15권1호
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    • pp.1-7
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    • 2006
  • The multi-dimensional two-phase flow models were developed for analyze the multi-dimensional behaviors or nuclear systems. To verify the simple turbulence model, The single phase mixing problem in a rectangular slab was calculated and compared with the commercial CFD code results. That result shows a good agreement with the CFD result. And the RPI Air-water experiments were simulated to assess the two-phase turbulence model in the multi-dimensional component. The first calculated distribution or void-fraction is highly dispersed and diffusive. It was revealed that the main reason is undesirable stratification force in a horizontal stratified flow regimes. Therefore the horizontally stratified flow regime is deleted because the stratified flow regime is not expected in multi-dimensional flow. With the modification of the flow regime, the predicted flow patterns and void fraction profiles are in good agreement with the measured data.

Performance Analysis of FEC for Low Power Wireless Sensor Networks (저전력 무선 센서 네트워크를 위한 FEC 성능 분석)

  • Lee, Min-Goo;Park, Yong-Guk;Jung, Kyung-Kwon;Yoo, Jun-Jae;Sung, Ha-Gyeong
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 한국해양정보통신학회 2010년도 춘계학술대회
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    • pp.882-885
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    • 2010
  • In view of the severe energy constraint in sensor networks, it is important to use the error control scheme of the energy efficiently. In this paper, we presented FEC (Forward Error Correcting) codes in terms of their power consumption. One method of FEC is RS (Reed-Solomon) coding, which uses block codes. RS codes work by adding extra redundancy to the data. The encoded data can be stored or transmitted. It could have errors introduced, when the encoded data is recovered. The added redundancy allows a decoder to detect which parts of the received data is corrupted, and corrects them. The number of errors which are able to be corrected by RS code can determine by added redundancy. We could predict the lifetime of RS codes which transmitted at 32 byte a 1 minutes. RS(15, 13), RS(31, 27), RS(63, 57), RS(127,115), and RS(255,239) can keep the days of 138, 132, 126, 111, and 103 respectively.

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