• Title/Summary/Keyword: cross section core

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Cross section generation for a conceptual horizontal, compact high temperature gas reactor

  • Junsu Kang;Volkan Seker;Andrew Ward;Daniel Jabaay;Brendan Kochunas;Thomas Downar
    • Nuclear Engineering and Technology
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    • v.56 no.3
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    • pp.933-940
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    • 2024
  • A macroscopic cross section generation model was developed for the conceptual horizontal, compact high temperature gas reactor (HC-HTGR). Because there are many sources of spectral effects in the design and analysis of the core, conventional LWR methods have limitations for accurate simulation of the HC-HTGR using a neutron diffusion core neutronics simulator. Several super-cell model configurations were investigated to consider the spectral effect of neighboring cells. A new history variable was introduced for the existing library format to more accurately account for the history effect from neighboring nodes and reactivity control drums. The macroscopic cross section library was validated through comparison with cross sections generated using full core Monte Carlo models and single cell cross section for both 3D core steady-state problems and 2D and 3D depletion problems. Core calculations were then performed with the AGREE HTR neutronics and thermal-fluid core simulator using super-cell cross sections. With the new history variable, the super-cell cross sections were in good agreement with the full core cross sections even for problems with significant spectrum change during fuel shuffling and depletion.

응력-침투 연계 해석에 의한 필 댐의 최적 설계

  • Park, Chun-Sik;Lee, Jun-Suk;Kim, Jong-Hwan
    • Proceedings of the Korean Geotechical Society Conference
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    • 2010.03a
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    • pp.862-870
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    • 2010
  • This thesis has been researched on optimized design method for the total cross section of embankment considering the fact that the size of embankment cross section is directly related with economic efficiency when dam designing. In general, embankment cross section of fill dam is either determined by cohesion and angle of internal friction, a strength parameter of embankment materials or by permeability of embankment. Therefore the size of embankment cross section depending on strength parameter of embankment materials was determined by using MIDAS-GTS program through stress-seepage coupled analysis at the time of fill dam design. As a result, determination of embankment cross section was more affected by the size of central core and permeability rather than by slope stability by shear strength and it was revealed that in case of embankment height being over 20m, stability against infiltration and slope action could be secured only when embankment slope is at least over 1:2.5. In addition, it was also revealed that in case of making the size of central core exceeding specification standard, total cross section of embankment could be reduced considerably and at the time of embankment design, adequate size and appropriateness of embankment cross section could be determined with referring the table suggested by this study.

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Optimum formation method of curved core cross section of silica fiber (실리카 광섬유 코어의 곡률단면 형성 최적화 방법)

  • Kim, Se-Min;Kim, Seung-Hwan;Lee, Seung-Hun;Hwang, Seok-Hyeon;Kim, Mi-Gyeong;HwangBo, Chang-Gwon;Kim, Gyeong-Heon
    • Proceedings of the Optical Society of Korea Conference
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    • 2009.10a
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    • pp.288-289
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    • 2009
  • We report an optimum fabrication condition for formation of concave lens shaped core cross-section of silica single-mode fibers with hydrofluoric (HF) acid solutions and arc discharge. A desired depth of curved cross-section of the silica fiber core and its surface smoothness were obtained with optimized concentration of the HF solution, etching time, and arc discharge condition.

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MGGC2.0: A preprocessing code for the multi-group cross section of the fast reactor with ultrafine group library

  • Kui Hu;Xubo Ma;Teng Zhang;Xuan Ma;Zifeng Huang;Yixue Chen
    • Nuclear Engineering and Technology
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    • v.55 no.8
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    • pp.2785-2796
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    • 2023
  • How to generate the precise broad group cross section is important for the fast reactor design. In this study, a fast reactor multi-group cross-section generation code MGGC2.0 are developed in-house for processing ultrafine group MATXS format library. Validation and verification are performed for MGGC2.0 code by applying the benchmarks of ICSBEP handbook, and the results of MGGC2.0 agree well with that of MCNP. The consistent PN method with critical buckling search is in good agreement that condensed with TWODANT flux and flux moment for the inner core and outer core region. For the radial blanket and reflector, two region approximation method has been applied in MGGC2.0 by using collision Probability Method neutron flux solver. The RBEC-M benchmark was used to verify the power distribution calculation, and the relative error of power distribution comparison with the reference are less than 0.8% in the fuel region and the maximum relative error is 5.58% in the reflector region. Therefore, the precise broad cross section can be generated by MGGC2.0 for fast reactor.

Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis

  • Nguyen, Tung Dong Cao;Lee, Hyunsuk;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • v.53 no.9
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    • pp.2788-2802
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    • 2021
  • Multigroup cross section (MG XS) generation by the UNIST in-house Monte Carlo (MC) code MCS for fast reactor analysis using nodal diffusion codes is reported. The feasibility of the approach is quantified for two sodium fast reactors (SFRs) specified in the OECD/NEA SFR benchmark: a 1000 MWth metal-fueled SFR (MET-1000) and a 3600 MWth oxide-fueled SFR (MOX-3600). The accuracy of a few-group XSs generated by MCS is verified using another MC code, Serpent 2. The neutronic steady-state whole-core problem is analyzed using MCS/RAST-K with a 24-group XS set. Various core parameters of interest (core keff, power profiles, and reactivity feedback coefficients) are obtained using both MCS/RAST-K and MCS. A code-to-code comparison indicates excellent agreement between the nodal diffusion solution and stochastic solution; the error in the core keff is less than 110 pcm, the root-mean-square error of the power profiles is within 1.0%, and the error of the reactivity feedback coefficients is within three standard deviations. Furthermore, using the super-homogenization-corrected XSs improves the prediction accuracy of the control rod worth and power profiles with all rods in. Therefore, the results demonstrate that employing the MCS MG XSs for the nodal diffusion code is feasible for high-fidelity analyses of fast reactors.

Seismic behavior of steel reinforced concrete (SRC) joints with new-type section steel under cyclic loading

  • Wang, Qiuwei;Shi, Qingxuan;Tian, Hehe
    • Steel and Composite Structures
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    • v.19 no.6
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    • pp.1561-1580
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    • 2015
  • No significant improvement has been observed on the seismic performance of the ordinary steel reinforced concrete (SRC) columns compared with the reinforced concrete (RC) columns mainly because I, H or core cross-shaped steel cannot provide sufficient confinement for core concrete. Two improved SRC columns by constructing with new-type section steel were put forward on this background: a cross-shaped steel whose flanges are in contact with concrete cover by extending the geometry of webs, and a rotated cross-shaped steel whose webs coincide with diagonal line of the column's section. The advantages of new-type SRC columns have been proved theoretically and experimentally, while construction measures and seismic behavior remain unclear when the new-type columns are joined onto SRC beams. Seismic behavior of SRC joints with new-type section steel were experimentally investigated by testing 5 specimens subjected to low reversed cyclic loading, mainly including the failure patterns, hysteretic loops, skeleton curves, energy dissipation capacity, strength and stiffness degradation and ductility. Effects of steel shape, load angel and construction measures on seismic behavior of joints were also analyzed. The test results indicate that the new-type joints display shear failure pattern under seismic loading, and steel and concrete of core region could bear larger load and tend to be stable although the specimens are close to failure. The hysteretic curves of new-type joints are plumper whose equivalent viscous damping coefficients and ductility factors are over 0.38 and 3.2 respectively, and this illustrates the energy dissipation capacity and deformation ability of new-type SRC joints are better than that of ordinary ones with shear failure. Bearing capacity and ductility of new-type joints are superior when the diagonal cross-shaped steel is contained and beams are orthogonal to columns, and the two construction measures proposed have little effect on the seismic behavior of joints.

A New Flyback Converter Using the Cross Flux of Transformer (교차 자속을 이용한 새로운 플라이백 컨버터)

  • Ku, Bok-Jae;Kim, Hyo-Seon;Park, Sung-Jun;Park, Seong-Mi
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.28 no.9
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    • pp.73-82
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    • 2014
  • This research proposes a new type of flyback converter topology based on magnetic circuit sharing. The proposed flyback topology uses a transformer involving shared magnetic flux, and its characteristic is magnetic flux cancelation by cross magnetic flux in the magnetic flux-sharing part of the core. The new topology aims to reduce the volume of transformer by reducing the cross section of the core. Compared to conventional converters using only 1 transformer, its circuit configuration involving the serial input and parallel output of 2 flyback coils allowed increased converter insulation strength. In addition, the adoption of interleaved switching method achieved the improvement of output voltage ripple, while magnetic circuit sharing reduced by 50% the cross section of core where magnetic circuit was shared.

DEVELOPMENT OF CALCULATION METHOD OF SENSITIVITIES FOR LIGHT WATER REACTORS

  • Takeda, Toshikazu;Foad, Basma
    • Nuclear Engineering and Technology
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    • v.45 no.6
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    • pp.753-758
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    • 2013
  • A new method of calculating sensitivity coefficients of core characteristics relative to infinite-dilution cross sections has been developed. Conventional sensitivity coefficients are evaluated for the changes of effective cross sections which are dependent on individual models of core and cell. Therefore a correction has been derived to the conventional sensitivity coefficients based on the perturbation theory. The accuracy of the present method has been verified by comparing numerical results of sensitivity coefficients with a reference Monte-Carlo method.

Study on rectangular concrete-filled steel tubes with unequal wall thickness

  • Zhang, Yang;Yu, Chen-Jiang;Fu, Guang-Yuan;Chen, Bing;Zhao, She-Xu;Li, Si-Ping
    • Steel and Composite Structures
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    • v.22 no.5
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    • pp.1073-1084
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    • 2016
  • Rectangular concrete-filled steel tubular columns with unequal wall thickness were investigated in the paper. The physical centroid, the centroidal principal axes of inertia, and the section core were given. The generalized bending formula and the generalized eccentric compression formula were deduced, and the equation of the neutral axis was also provided. The two rectangular concrete-filled steel tubular stub specimens subjected to the compression load on the physical centroid and the geometric centroid respectively were tested to verify the theoretical formulas.

A Study of the Applicability of Cross-Section Method for Cut-Slope Stability Analysis (개착사면의 안정성 해석을 위한 횡단면 기법의 활용성 고찰)

  • Cho, Tae-Chin;Hwang, Taik-Jean;Lee, Guen-Ho;Cho, Kye-Seong;Lee, Sang-Bae
    • Tunnel and Underground Space
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    • v.22 no.1
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    • pp.43-53
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    • 2012
  • Stability of cut-slope, the orientation and dimension of which are gradually changed, has been analyzed by employing the cross-section method capable of comprehensibly considering the lithological, structural and mechanical characteristics of slope rock. Lithological fragility is investigated by inspecting the drilled core logs and BIPS image has been taken to delineate the rock structure. Engineering properties of drilled-core including the joint shear strength have been also measured. Potential failure modes of cut-slope and failure-induced joints are identified by performing the stereographic projection analysis. Traces of potential failure-induced joints are drawn on the cross-section which depicts the excavated geometry of cut-slope. Considering the distribution of potential plane failure-induced joint traces blocks of plane failure mode are hypothetically formed. The stabilities and required reinforcements of plane failure blocks located at the different excavation depth have been calculated to confirm the applicability of the cross-section method for the optimum cut-slope design.