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검색결과 630건 처리시간 0.023초

Gamma Ray Shielding Study of Barium-Bismuth-Borosilicate Glasses as Transparent Shielding Materials using MCNP-4C Code, XCOM Program, and Available Experimental Data

  • Bagheri, Reza;Moghaddam, Alireza Khorrami;Yousefnia, Hassan
    • Nuclear Engineering and Technology
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    • 제49권1호
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    • pp.216-223
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    • 2017
  • In this work, linear and mass attenuation coefficients, effective atomic number and electron density, mean free paths, and half value layer and $10^{th}$ value layer values of barium-bismuth-borosilicate glasses were obtained for 662 keV, 1,173 keV, and 1,332 keV gamma ray energies using MCNP-4C code and XCOM program. Then obtained data were compared with available experimental data. The MCNP-4C code and XCOM program results were in good agreement with the experimental data. Barium-bismuth-borosilicate glasses have good gamma ray shielding properties from the shielding point of view.

단기통 2사이클 압축점화기관의 시뮬레이션 (Simulation of the single-cylinder 2-stroke cycle compression ignition engine)

  • 유병철;김정순
    • 오토저널
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    • 제8권1호
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    • pp.62-74
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    • 1986
  • The simulation of power cycle and unsteady gas exchange processes in the inlet and exhaust systems of the single-cylinder 2-stroke cycle compression ignition engine was studied in this paper. In power cycle process, the single-zone model proposed by Whitehouse and Way was used, and the convective and radiative heat transfer from cylinder contents to surroundings was considered. To solve the equations for gas exchange process, the generalized method of characteristics including area change, friction, heat transfer and entropy gradients was used. Also with the path line calculation, the entropy change along the path line and the variation of specific heat due to the change of temperature and the composition of cylinder gas were considered. As a result of the simulation, the change of pressure and temperature in the cylinder against the crank angle, the rate of net heat release, and the change of properties at each point in the inlet and exhaust pipe against the crank angle were obtained. The engine performances under various operating conditions were also calculated.

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전력통신을 위한 시장 동향 및 발전 전망 (Trends Research and Development View of Power Line Communication)

  • 김지호;이향범
    • 한국정보통신설비학회:학술대회논문집
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    • 한국정보통신설비학회 2008년도 정보통신설비 학술대회
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    • pp.573-578
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    • 2008
  • While going through economic development for several decades, Korea has become an industrialized country, and the development of industrial technology accelerated the advent of the information opportunity era. The recent information oriented society has brought forth the development of new information communication technology that enables anybody to obtain information easily and simply, and recently power line communication technology is being developed that allows the use of the existing power line net-works as they are. Each advanced country that faced up to a riffle effect of power line communication technology that enables us to obtain information easily anywhere at anytime is engaged in fierce competition to be a leader in this technology and to preoccupy the standardization of power line communication technology. At this point, this study is to help Korea take the lead in information communication technology by proposing a direction for the standardization that Korean power line communication technology needs to head for by identifying the trend of the worldwide of power line communication technology.

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A REVIEW OF HELIUM GAS TURBINE TECHNOLOGY FOR HIGH-TEMPERATURE GAS-COOLED REACTORS

  • No, Hee-Cheon;Kim, Ji-Hwan;Kim, Hyeun-Min
    • Nuclear Engineering and Technology
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    • 제39권1호
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    • pp.21-30
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    • 2007
  • Current high-temperature gas-cooled reactors (HTGRs) are based on a closed Brayton cycle with helium gas as the working fluid. Thermodynamic performance of the axial-flow helium gas turbines is of critical concern as it considerably affects the overall cycle efficiency. Helium gas turbines pose some design challenges compared to steam or air turbomachinery because of the physical properties of helium and the uniqueness of the operating conditions at high pressure with low pressure ratio. This report present a review of the helium Brayton cycle experiences in Germany and in Japan. The design and availability of helium gas turbines for HTGR are also presented in this study. We have developed a new throughflow calculation code to calculate the design-point performance of helium gas turbines. Use of the method has been illustrated by applying it to the GTHTR300 reference.

Using Largest Lyapunov Exponent to Confirm the Intrinsic Stability of Boiling Water Reactors

  • Gavilan-Moreno, Carlos J.;Espinosa-Paredes, Gilberto
    • Nuclear Engineering and Technology
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    • 제48권2호
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    • pp.434-447
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    • 2016
  • The aim of this paper is the study of instability state of boiling water reactors with a method based in largest Lyapunov exponents (LLEs). Detecting the presence of chaos in a dynamical system is an important problem that is solved by measuring the LLE. Lyapunov exponents quantify the exponential divergence of initially close state-space trajectories and estimate the amount of chaos in a system. This method was applied to a set of signals from several nuclear power plant (NPP) reactors under commercial operating conditions that experienced instabilities events, apparently each of a different nature. Laguna Verde and Forsmark NPPs with in-phase instabilities, and Cofrentes NPP with out-of-phases instability. This study presents the results of intrinsic instability in the boiling water reactors of three NPPs. In the analyzed cases the limit cycle was not reached, which implies that the point of equilibrium exerts influence and attraction on system evolution.

IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL

  • Chen, Yiren
    • Nuclear Engineering and Technology
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    • 제45권3호
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    • pp.311-322
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    • 2013
  • High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear energy systems. Thanks to its excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels such as HT-9 are considered for in-core applications of advanced nuclear reactors. The harsh neutron irradiation environments at the reactor core region pose a unique challenge for structural and cladding materials. Microstructural and microchemical changes resulting from displacement damage are anticipated for structural materials after prolonged neutron exposure. Consequently, various irradiation effects on the service performance of in-core materials need to be understood. In this work, the fundamentals of radiation damage and irradiation effects of the HT-9 martensitic steel are reviewed. The objective of this paper is to provide a background introduction of displacement damage, microstructural evolution, and subsequent effects on mechanical properties of the HT-9 martensitic steel under neutron irradiations. Mechanical test results of the irradiated HT-9 steel obtained from previous fast reactor and fusion programs are summarized along with the information of irradiated microstructure. This review can serve as a starting point for additional investigations on the in-core applications of ferritic/martensitic steels in advanced nuclear reactors.

Wavelet operator for multiscale modeling of a nuclear reactor

  • Vajpayee, Vineet;Mukhopadhyay, Siddhartha;Tiwari, Akhilanand Pati
    • Nuclear Engineering and Technology
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    • 제50권5호
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    • pp.698-708
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    • 2018
  • This article introduces a methodology of designing a wavelet operator suitable for multiscale modeling. The operator matrix transforms states of a multivariable system onto projection space. In addition, it imposes a specific structure on the system matrix in a multiscale environment. To be specific, the article deals with a diagonalizing transform that is useful for decoupled control of a system. It establishes that there exists a definite relationship between the model in the measurement space and that in the projection space. Methodology for deriving the multirate perfect reconstruction filter bank, associated with the wavelet operator, is presented. The efficacy of the proposed technique is demonstrated by modeling the point kinetics nuclear reactor. The outcome of the multiscale modeling approach is compared with that in the single-scale approach to bring out the advantage of the proposed method.

Control of the pressurized water nuclear reactors power using optimized proportional-integral-derivative controller with particle swarm optimization algorithm

  • Mousakazemi, Seyed Mohammad Hossein;Ayoobian, Navid;Ansarifar, Gholam Reza
    • Nuclear Engineering and Technology
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    • 제50권6호
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    • pp.877-885
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    • 2018
  • Various controllers such as proportional-integral-derivative (PID) controllers have been designed and optimized for load-following issues in nuclear reactors. To achieve high performance, gain tuning is of great importance in PID controllers. In this work, gains of a PID controller are optimized for power-level control of a typical pressurized water reactor using particle swarm optimization (PSO) algorithm. The point kinetic is used as a reactor power model. In PSO, the objective (cost) function defined by decision variables including overshoot, settling time, and stabilization time (stability condition) must be minimized (optimized). Stability condition is guaranteed by Lyapunov synthesis. The simulation results demonstrated good stability and high performance of the closed-loop PSO-PID controller to response power demand.

국가기준점망의 고밀도화를 위한 결합체계 (Junction Schemes for the Densified Control Network)

  • 이영진;이석찬
    • 한국측량학회지
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    • 제7권2호
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    • pp.27-34
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    • 1989
  • 측지 기준점망은 점의 쉬치를 결정하고 지구의 형상을 구하기 위하여 200여년 동안 구성되어 오고 있으며 카 나라의 실정에 적합한 체계를 갖고 있다. 이 논문은 기설망의 정확도가 기지이거나 미지인 경우에 대하여 국가기준점망의 고밀도화를 위한 결합체계를 제시하였다. 부분적으로 $X^TX$=min.의 조건이 만족되는 제약망의 조정개념을 적용하였으며, 변동점의 검출을 위하여 최근 변위측량 분야에서의 측량시기별 분석방법을 도입하였다.

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Evaluation of sequence tracking methods for Compton cameras based on CdZnTe arrays

  • Lee, Jun;Kim, Younghak;Bolotnikov, Aleksey;Lee, Wonho
    • Nuclear Engineering and Technology
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    • 제53권12호
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    • pp.4080-4092
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    • 2021
  • In this study, the performance of sequence tracking methods for multiple interaction events in specific CdZnTe Compton imagers was evaluated using Monte Carlo simulations. The Compton imager consisted of a 6 × 6 array of virtual Frisch-grid CZT crystals, where the dimensions of each crystal were 5 × 5 × 12 mm3. The sequence tracking methods for another Compton imager that consists of two identical CZT crystals arrays were also evaluated. When 662 keV radiation was incident on the detectors, the percentages of the correct sequences determined by the simple comparison and deterministic methods for two sequential interactions were identical (~80%), while those evaluated using the minimum squared difference method (55-59%) and Three Compton method (45-55%) for three sequential interactions, differed from each other. The reconstructed images of a 662 keV point source detected using single and double arrays were evaluated based on their angular resolution and signal-to-noise ratio, and the results showed that the double arrays outperformed single arrays.