• Title/Summary/Keyword: length of core

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Nuclear Core Design for a Marine Small Power Reactor (선박용 소형동력로의 노심 핵설계)

  • 최유선;김종채;김명현
    • Journal of Energy Engineering
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    • v.5 no.2
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    • pp.146-152
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    • 1996
  • A small power reactor core of 108 MW$\_$th/ was designed with some design constraints: 2 year refueling cycle length, soluble boron free operation, low power density, and proven fuel assembly design - Uljin 3'||'&'||'4 design specifications. CASMO-3 and KINS-3 was used to evaluate operational capability for power level control via control rods. Cycle length, power peaking factor, M.T.C., and power coefficients were also checked. Designed core loaded with KOFAs satisfied all design goals. We found that much more burnable poisons are to be loaded with axial enrichment zoning. Control rod assemblies should be located at every other assemblies with more than 3 banks. Additional shutdown banks are proposed for the safe plant cooldown, which could be located at core periphery.

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A Study on the Transformer Design considering the Inrush Current Reduction in the Arc Welding Machine

  • Kim, In-Gun;Liu, Huai-Cong;Cho, Su-Yeon;Lee, Ju
    • Journal of Magnetics
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    • v.21 no.3
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    • pp.374-378
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    • 2016
  • The transformer used in an inverter type arc welding machine is designed to use high frequency in order to reduce its size and cost. Also, selecting core materials that fit frequency is important because core loss increases in a high frequency band. An inrush current can occur in the primary coil of transformer during arc welding and this inrush current can cause IGBT, the switching element, to burn out. The transformer design was carried out in $A_P$ method and amorphous core was used to reduce the size of transformer. In addition, sheet coil was used for primary winding and secondary winding coil considering the skin effect. This paper designed the transformer core with an air gap to prevent IGBT burnout due to the inrush current during welding and proposed the optimum air gap length.

Feasibility Study on the Utilization of Mixed Oxide Fuel in Korean 900MWe PWR Core Through Conceptual Core Nuclear Design and Analysis

  • Joo, Hyung-Kook;Kim, Young-Jin;Jung, Hyung-Guk;Sohn, Dong-Seong
    • Nuclear Engineering and Technology
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    • v.29 no.4
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    • pp.299-309
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    • 1997
  • The neutronic feasibility of typical Korean three-loop 900MWe class PWR core loaded with mixed oxide fuels for both annual and 18-month cycle strategies has been investigated as a means for spent fuel management. For this study, a method of determining equivalent plutonium content was developed under the equivalence concept which gives the same cycle length as uranium fuel. Optimal plutonium zoning within the MOX assembly was also designed with the aim of minimizing the peak md power. Conceptual core designs hate hen developed for equilibrium cycle with the following variations: annual and 18-month cycle, 1/3 and full MOX loading schemes, and typical and high moderation lattice. The analysis of key core physics parameters shows that in all cases considered satisfactory core designs seem to be feasible, though addition of control rod system and change in Technical Specification for soluble boron concentration are required for full MOX loading in order to meet the current design requirements.

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Determination of Optimum Batch Size and Fuel Enrichment for OPR1000 NPP Based on Nuclear Fuel Cycle Cost Analysis (OPR1000 발전소의 핵연료 주기비분석을 통한 최적 배취 크기와 핵연료 농축도 결정)

  • Cho, Sung Ju;Hah, Chang Joo
    • Journal of Energy Engineering
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    • v.23 no.4
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    • pp.256-262
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    • 2014
  • Cycle length of domestic nuclear power plants is determined by the demand-supply plan of utility company. The target cycle length is achieved by adjusting the number of feed fuel assembly and fuel enrichment. Traditionally, utility company first select the number of feed fuel assembly and then find out the fuel enrichment to achieve the special cycle length. But it is difficult to find out if this method is most economical than any other combinations of the enrichment and batch size satisfying the same cycle length. In this paper, core depletion calculation is performed to find out the optimum combination of the enrichment and batch size for given target cycle length in terms of fuel cycle cost using commercial core design code; CASMO/MASTER code. To minimize the uncertainty resulting from transition core analysis, levelized fuel cycle cost analysis was applied to the equilibrium cycle core in order to determine the optimum combination. The sensitivity study of discount rate was also carried out to analyze the levelized fuel cycle cost applicable to countries with different discount rates. From the levelized fuel cycle cost analysis results, the combination with smaller batch size and higher fuel enrichment becomes more economical as the discount rate becomes lower. On the other hand, the combination with higher batch size and lower fuel enrichment becomes more economical as the discount rate becomes higher.

Parameterized FFT/IFFT Core Generator for ODFM Modulation/Demodulation (OFDM 변복조를 위한 파라메터화된 FFT/IFFT 코어 생성기)

  • Lee, J.W.;Kim, J.H.;Shin, K.W.;Baek, Y.S.;Eo, I.S.
    • Proceedings of the IEEK Conference
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    • 2005.11a
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    • pp.659-662
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    • 2005
  • A parameterized FFT/IFFT core generator (PFFT_CoreGen) is designed, which can be used as an essential IP (Intellectual Property) in various OFDM modem designs. The PFFT_CoreGen generates Verilog-HDL models of FFT cores in the range of 64 ${\sim}$ 2048-point. To optimize the performance of the generated FFT cores, the PFFT_CoreGen can select the word-length of input data, internal data and twiddle factors in the range of 8-b ${\sim}$ 24-b. Some design techniques for low-power design are considered from algorithm level to circuit level.

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An ultra-long-life small safe fast reactor core concept having heterogeneous driver-blanket fuel assemblies

  • Choi, Kyu Jung;Jo, Yeonguk;Hong, Ser Gi
    • Nuclear Engineering and Technology
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    • v.53 no.11
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    • pp.3517-3527
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    • 2021
  • New 80-MW (electric) ultra-long-life sodium cooled fast reactor core having inherent safety characteristics is designed with heterogeneous fuel assemblies comprised of driver and blanket fuel rods. Several options using upper sodium plenum and SSFZ (Special Sodium Flowing Zone) for reducing sodium void reactivity are neutronically analyzed in this core concept in order to improve the inherent safety of the core. The SSFZ allowing the coolant flow from the peripheral fuel assemblies increases the neutron leakage under coolant expansion or voiding. The Monte Carlo calculations were used to design the cores and analyze their physics characteristics with heterogeneous models. The results of the design and analyses show that the final core design option has a small burnup reactivity swing of 618 pcm over ~54 EFPYs cycle length and a very small sodium void worth of ~35pcm at EOC (End of Cycle), which leads to the satisfaction of all the conditions for inherent safety with large margin based on the quasi-static reactivity balance analysis under ATWS (Anticipated Transient Without Scram).

Russian Railways and their Role in the Economic Development of the Russian Federation and International Trade

  • Steklov, Mikhail
    • Journal of the Korean Society for Railway
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    • v.4 no.1
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    • pp.9-15
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    • 2001
  • The railways in Russia is a core of the industrial, trade and technological development. They changed the country for the best affecting all sides of its life. The total length of the railways in Russia is 87,500 km (7% of the World railway network). They account for about a 25% of the World freight and 15% of the passenger traffic. In terms of length of electrified railways Russia is a World leader and in terms of total length of tracks it is second after the USA. Annual freight turnover is the third after the USA and China. (omitted)

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Evaluations of Swaging Process for Rotor Core of Induction Motors (유도전동기 회전자 제작시 압입작업 평가)

  • Park, Sang-Chul
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.17 no.10
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    • pp.21-26
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    • 2016
  • This study evaluates the magnitudes and distributions of contact tangential forces with the swaging depth of punch acting at the contact surfaces between a rotor core slot and a Cu bar during a sequential rotor core swaging process. The effects of the core slot shape on the magnitudes and distributions of the total contact forces were investigated to improve the productivity of the rotor core swaging process. Parametric elastic-plastic numerical analyses were performed using simplified two-dimensional cyclic symmetric plane strain models to evaluate the contact force distributions at the contact surfaces. The numerical analysis results show that the total contact tangential forces increased by about 55% with the adjacent Cu bar swaging process. The length of the core slot is a dominant factor in the core slot design as result of the increased total contact tangential forces during the swaging process of the rotor core.

The Effect of Incidence of Ankle Sprains on Both Leg Length Inequalities and Range of Motion of Ankle Joint in 20's Female University Students (20대 여대생의 양다리길이차이 및 발목관절가동범위가 발목 염좌 발생률에 미치는 영향)

  • Park, Jong-Hang;Jeong, Yeon-Woo;Kim, Tae-won
    • The Journal of Korean Academy of Orthopedic Manual Physical Therapy
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    • v.21 no.1
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    • pp.29-35
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    • 2015
  • Background: The purpose of this study was conducted to investigate the effect of incidence of ankle sprains on both leg length inequalities and range of motion of ankle joint in 20's female university students. Methods: 20's female university students were targeting 32 people attending K university in Gwangju. Both leg length inequality was measured using a tape measure, ranges of motion of ankles was measured using a goniometer. Results: The ankle sprain incidence was quite high, with 56.25% (n=18) for the right ankle, 34.38% (n=11) for the left ankle, and 9.38% (n=3) for both. As for the difference between the ankle sprain incidence and both leg length, the average value of the right leg was $83.08{\pm}3.69$, the average value of the left leg was $84.28{\pm}3.27$, making the right leg shorter than the left by 1.2cm with a higher incidence and showing a positive statistical correlation between the two (p<.05). Also showed that there was a negative statistical correlation between ankle sprain incidences and the inversion range of motion spread of the right ankle (p<.05). Conclusion: The incidence of ankle sprains was higher for the larger the difference between both leg length inequality. In addition, the smaller the inversion range of motion spread of the right ankle, the higher the incidence of ankle sprains. Therefore, The evidence suggests that the incidence of ankle sprains can be reduced by recommending stability and efficient exercises that take into consideration the both leg length as well as the ranges of motion of ankle joints.

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Electromotive Force Characteristics of Current Transformer According to the Magnetic Properties of Ferromagnetic Core

  • Kim, Young Sun
    • Transactions on Electrical and Electronic Materials
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    • v.16 no.1
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    • pp.37-41
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    • 2015
  • The most common structure of the current transformer (CT) consists of a length of wire wrapped many times around a silicon steel ring passed over the circuit being measured. Therefore, the primary circuit of CT consists of a single turn of the conductor, with a secondary circuit of many tens or hundreds of turns. The primary winding may be a permanent part of the current transformer, with a heavy copper bar to carry the current through the magnetic core. However, when the large current flows into a wire, it is difficult to measure its magnitude of current because the core is saturated and the core shows magnetic nonlinear characteristics. Therefore, we proposed a newly designed CT which has an air gap in the core to decrease the generated magnetic flux. Adding the air gap in the magnetic path increases the total magnetic reluctance against the same magnetic motive force (MMF). Using a ferrite core instead of steel also causes the generation of low magnetic flux. These features can protect the magnetic saturation of the CT core compared with the steel core. This technique can help the design of the CT to obtain a special shape and size.