• 제목/요약/키워드: Multi-physics coupling

검색결과 27건 처리시간 0.025초

Angular Dispersion-type Nonscanning Fabry-Perot Interferometer Applied to Ethanol-water Mixture

  • Ko, Jae-Hyeon;Kojima, Seiji
    • Journal of the Optical Society of Korea
    • /
    • 제13권2호
    • /
    • pp.261-266
    • /
    • 2009
  • The angular dispersion-type non-scanning Fabry-Perot was applied to an ethanol-water mixture in order to investigate its acoustic properties such as the sound velocity and the absorption coefficient. The scattered light from the mixture was analyzed by using the charge-coupled-device area detector, which made the measurement time much shorter than that obtained by using the conventional scanning tandem multi-pass Fabry-Perot interferometer. The sound velocity showed a deviation from ultrasonic sound velocities at low temperatures accompanied by the increase in the absorption coefficient, indicating acoustic dispersion due to the coupling between the acoustic waves and some relaxation process. Based on a simplified viscoelastic theory, the temperature dependence of the relaxation time was obtained. The addition of water molecules to ethanol reduced the relaxation time, consistent with dielectric measurements. The present study showed that the angular dispersion-type Fabry-Perot interferometer combined with an area detector could be a very powerful tool in the real-time monitoring of the acoustic properties of condensed matter.

Evaluating the Catalytic Effects of Carbon Materials on the Photocatalytic Reduction and Oxidation Reactions of TiO2

  • Khan, Gulzar;Kim, Young Kwang;Choi, Sung Kyu;Han, Dong Suk;Abdel-Wahab, Ahmed;Park, Hyunwoong
    • Bulletin of the Korean Chemical Society
    • /
    • 제34권4호
    • /
    • pp.1137-1144
    • /
    • 2013
  • $TiO_2$ composites with seven different carbon materials (activated carbons, graphite, carbon fibers, single-walled carbon nanotubes, multi-walled carbon nanotubes, graphene oxides, and reduced graphene oxides) that are virgin or treated with nitric acid are prepared through an evaporation method. The photocatalytic activities of the as-prepared samples are evaluated in terms of $H_2$ production from aqueous methanol solution (photo-catalytic reduction: PCR) and degradation of aqueous pollutants (phenol, methylene blue, and rhodamine B) (photocatalytic oxidation: PCO) under AM 1.5-light irradiation. Despite varying effects depending on the kinds of carbon materials and their surface treatment, composites typically show enhanced PCR activity with maximum 50 times higher $H_2$ production as compared to bare $TiO_2$. Conversely, the carbon-induced synergy effects on PCO activities are insignificant for all three substrates. Colorimetric quantification of hydroxyl radicals supports the absence of carbon effects. However, platinum deposition on the binary composites displays the enhanced effect on both PCR and PCO reactions. These differing effects of carbon materials on PCR and PCO reactions of $TiO_2$ are discussed in terms of physicochemical properties of carbon materials, coupling states of $TiO_2$/carbon composites, interfacial charge transfers. Various surface characterizations of composites (UV-Vis diffuse reflectance, SEM, FTIR, surface area, electrical conductivity, and photoluminescence) are performed to gain insight on their photocatalytic redox behaviors.

Jacobian-free Newton Krylov two-node coarse mesh finite difference based on nodal expansion method

  • Zhou, Xiafeng
    • Nuclear Engineering and Technology
    • /
    • 제54권8호
    • /
    • pp.3059-3072
    • /
    • 2022
  • A Jacobian-Free Newton Krylov Two-Nodal Coarse Mesh Finite Difference algorithm based on Nodal Expansion Method (NEM_TNCMFD_JFNK) is successfully developed and proposed to solve the three-dimensional (3D) and multi-group reactor physics models. In the NEM_TNCMFD_JFNK method, the efficient JFNK method with the Modified Incomplete LU (MILU) preconditioner is integrated and applied into the discrete systems of the NEM-based two-node CMFD method by constructing the residual functions of only the nodal average fluxes and the eigenvalue. All the nonlinear corrective nodal coupling coefficients are updated on the basis of two-nodal NEM formulation including the discontinuity factor in every few newton steps. All the expansion coefficients and interface currents of the two-node NEM need not be chosen as the solution variables to evaluate the residual functions of the NEM_TNCMFD_JFNK method, therefore, the NEM_TNCMFD_JFNK method can greatly reduce the number of solution variables and the computational cost compared with the JFNK based on the conventional NEM. Finally the NEM_TNCMFD_JFNK code is developed and then analyzed by simulating the representative PWR MOX/UO2 core benchmark, the popular NEACRP 3D core benchmark and the complicated full-core pin-by-pin homogenous core model. Numerical solutions show that the proposed NEM_TNCMFD_JFNK method with the MILU preconditioner has the good numerical accuracy and can obtain higher computational efficiency than the NEM-based two-node CMFD algorithm with the power method in the outer iteration and the Krylov method using the MILU preconditioner in the inner iteration, which indicates the NEM_TNCMFD_JFNK method can serve as a potential and efficient numerical tool for reactor neutron diffusion analysis module in the JFNK-based multiphysics coupling application.

Application of a new neutronics/thermal-hydraulics coupled code for steady state analysis of light water reactors

  • Safavi, Amir;Esteki, Mohammad Hossein;Mirvakili, Seyed Mohammad;Arani, Mehdi Khaki
    • Nuclear Engineering and Technology
    • /
    • 제52권8호
    • /
    • pp.1603-1610
    • /
    • 2020
  • Due to ever-growing advancements in computers and relatively easy access to them, many efforts have been made to develop high-fidelity, high-performance, multi-physics tools, which play a crucial role in the design and operation of nuclear reactors. For this purpose in this study, the neutronic Monte Carlo and thermal-hydraulic sub-channel codes entitled MCNP and COBRA-EN, respectively, were applied for external coupling with each other. The coupled code was validated by code-to-code comparison with the internal couplings between MCNP5 and SUBCHANFLOW as well as MCNP6 and CTF. The simulation results of all code systems were in good agreement with each other. Then, as the second problem, the core of the VVER-1000 v446 reactor was simulated by the MCNP4C/COBRA-EN coupled code to measure the capability of the developed code to calculate the neutronic and thermohydraulic parameters of real and industrial cases. The simulation results of VVER-1000 core were compared with FSAR and another numerical solution of this benchmark. The obtained results showed that the ability of the MCNP4C/COBRA-EN code for estimating the neutronic and thermohydraulic parameters was very satisfactory.

유체-구조 상호작용을 적용한 튜브다발의 유체탄성불안정성 과도적 전산해석 (Multi-Physics Simulations of Fluidelastic Instability for Tube Bundles in Cross-Flow)

  • 이민형;김용찬
    • 대한기계학회논문집B
    • /
    • 제28권2호
    • /
    • pp.174-180
    • /
    • 2004
  • Failure of tube bundles due to excessive flow-induced vibrations continues to affect the performance of nuclear power plant Early experimental studies concentrated on rigid structures and later investigators dealt with elastic structures because of their importance in many engineering fields. On the other hand, much less numerical work has been carried out, because of the numerical complexity associated with the problem. Conventional approaches usually decoupled the flow solution from the structural problem. The present numerical study proposes the methodology in analyzing the fluidelastic instability occurring in tube bundles by coupling the Computational fluid Dynamics (C%) with the tube equation of motions. The motion of the structures is modeled by a spring-damper-mass system that allows transnational motion in two directions (a two-degree-of-freedom system). The fluid motion and the cylinder response are solved in an iterative way, so that the interaction between the fluid and the structure can be accounted for property. The aim of the present work is to predict the fluidelstic instability of tube bundles and the associated phenomena, such as the response of the cylinder, the unsteady lift and drag on the cylinder, the vortex shedding frequency.

메타버스와 메타피직스의 영화적 순환 (Cinematic Circulation of Meta-verse and Meta-physics)

  • 심광현
    • 트랜스-
    • /
    • 제12권
    • /
    • pp.81-106
    • /
    • 2022
  • 메타버스 시스템이 향후 초연결 사회의 촉매가 될 수 있을지는 인공지능 기술과 마찬가지로 연관 기술의 발전 속도와 사회적 활용 범위의 확장 여부에 달려 있다. 이 글에서는 이런 현실화 과정의 문제를 괄호치고, 기술 발전이 가속화될 경우 이 복합적인 기술-사회의 짝패구조가 영화의 미래와 연관된 인지생태학적 변화와 관련된 몇 가지 철학적-정치적 논점에 한정해 논의해 보고자 한다. 흔히 메타버스의 핵심은 '몰입도'에 있다고 보지만 인지생태학적으로 보면 한 장의 그림이나 사진의 몰입도는 '재현의 정확성'보다는 그것이 주는 메시지의 맥락적 연결성에 달려 있다는 점을 환기해 보면 정확한 판단은 아니다. 이런 맥락에서 볼 때 메타버스의 진정한 잠재력은 새로운 자연적-사회적-기술적 짝패구조의 형성 속에서 활성화될 인간 뇌의 다중지능적 연결 능력(증강-시뮬레이션, 외부-내부의 교차)의 변화라는 인지생태학적인 맥락에서 파악할 필요가 있다. 그리고 이런 인지생태학적 잠재력은 이미 오래 전부터 [현실의 모순/갈등(M1)-->허구적 변형을 통한 영화적 해결책(M2)-->관객의 소원-성취 욕망에 의한 선택적 해석(M3)-->현실의 변화(M1']라는 삼중 미메시스의 영화적 순환 과정에서 부분적으로 실현되어 왔다. 따라서 메타버스 시스템의 진정한 잠재력은 현실적인 분리/문제들과 이상적인 연결/해결 사이의 영화적 순환을 더욱 확장하고 심화시킬 수 있는가에 달려 있다. 이런 측면에서 보자면 발전된 메타버스는 피직스-메타피직스의 이상적 순환의 현대적인 기술적 버전으로 비유될 수 있을 것이다

Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator

  • Abdelhameed, Ahmed Amin E.;Chaudri, Khurrum Saleem;Kim, Yonghee
    • Nuclear Engineering and Technology
    • /
    • 제52권12호
    • /
    • pp.2699-2708
    • /
    • 2020
  • Helical-coil steam generator (HCSG) technology is a major design candidate for small modular reactors due to its compactness and capability to produce superheated steam with high generation efficiency. In this paper, we investigate the feasibility of the passively autonomous power maneuvering by coupling the 3-D transient multi-physics of a soluble-boron-free (SBF) core with a time-dependent HCSG model. The predictor corrector quasi-static method was used to reduce the cost of the transient 3-D neutronic solution. In the numerical system simulations, the feedwater flow rate to the secondary of the HCSGs is adjusted to extract the demanded power from the primary loop. This varies the coolant temperature at the inlet of the SBF core, which governs the passively autonomous power maneuvering due to the strongly negative coolant reactivity feedback. Here, we simulate a 100-50-100 load-follow operation with a 5%/minute power ramping speed to investigate the feasibility of the passively autonomous load-follow in a 450 MWth SBF PWR. In addition, the passively autonomous frequency control operation is investigated. The various system models are coupled, and they are solved by an in-house Fortran-95 code. The results of this work demonstrate constant steam temperature in the secondary side and limited variation of the primary coolant temperature. Meanwhile, the variations of the core axial shape index and the core power peaking are sufficiently small.