• Title/Summary/Keyword: excess-3 code

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Design of Extendable BCD-EXCESS 3 Code Convertor Using Quantum-Dot Cellular Automata (확장성을 고려한 QCA BCD-3초과 코드 변환기 설계)

  • You, Young-won;Jeon, Jun-cheol
    • Journal of Advanced Navigation Technology
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    • v.20 no.1
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    • pp.65-71
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    • 2016
  • Quantum-dot cellular automata (QCA) consists of nano-scale cells and demands very low power consumption so that it is one of the alternative technologies that can overcome the limits of scaling CMOS technologies. Typical BCD-EXCESS 3 code converters using QCA have not considered the scalability so that the architectures are not suitable for a large scale circuit design. Thus, we design a BCD-EXCESS 3 code converter with scalability using QCADesigner and verify the effectiveness by simulation. Our structure have reduced 32 gates and 7% of garbage space rate compare with typical URG BCD-EXCESS 3 code converter. Also, 1 clock is only needed for circuit expansion of our structure though typical QCA BCD-EXCESS 3 code converter demands 7 clocks.

An Excess-3 Code Adde $r_{}$tracter Design Decimal Computation (십진수 계산을 위한 3초과 부호 가감산기 설계)

  • 최종화;한선경;유영갑
    • Journal of the Institute of Electronics Engineers of Korea CI
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    • v.40 no.6
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    • pp.32-38
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    • 2003
  • An excess-3 code adde $r_tracter circuit is proposed for human friendly decimal computation. Carry lookahead (CLA) circuitry can be used to enhance decimal computation speed. The proposed excess-3 adde $r_tracter employs improved CLA and compensation circuitry recoding computation delay. The circuitry used for addition is used for subtraction without further modification. Substantial speed improvement is obtained compared to conventional designs.signs.

An Excess-3 Code Carry Lookahead Design for High-Speed Decimal Addition (고속 십진 가산을 위한 3초과 코드 Carry Lookahead설계)

  • 최종화;유영갑
    • Journal of the Institute of Electronics Engineers of Korea CI
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    • v.40 no.5
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    • pp.241-249
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    • 2003
  • Carry lookahead(CLA) circuitry of decimal adders is proposed aiming at delay reduction. The truncation error in calculation of monetary interests may accumulate yielding a substantial amount of errors. Binary Coded Decimal(BCD) additions. for example, eliminate the truncation error in a fractional representation of decimal numbers. The proposed BCD carry lookahead scheme is aiming at the speed improvements without any truncation errors in the addition of decimal fractions. The delay estimation of the BCD CLA is demonstrated with improved performance in addition. Further reduction in delay can be achieved introducing non-weighted number system such as the excess-3 code.

Efficient Design of BCD-EXCESS 3 Code Converter Using Quantum-Dot Cellular Automata (QCA를 이용한 효율적인 BCD-3초과 코드 변환기 설계)

  • You, Young-Won;Jeon, Jun-Cheol
    • Journal of Advanced Navigation Technology
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    • v.17 no.6
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    • pp.700-704
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    • 2013
  • Quantum-dot cellular automata(QCA) is a new technology and it is an one of the alternative high performance over existing complementary metal-oxide semi-conductor(CMOS). QCA is nanoscale device and ultra-low power consumption compared with transistor-based technologies, and various circuits using QCA technology have been proposed. Binary-coded decimal(BCD), which represents decimal digits in binary, is mainly used in electronic circuits and Microprocessor, and it is comfortable in conversion operation but many data loss. In this paper, we present an BCD-EXCESS 3 Code converter which can be efficiently used for subtraction and half adjust. The proposed scheme has efficiently designed considering space and time complexities and minimization of noise, and it has been simulated and confirmed.

Excess Power를 이용한 HSDPA throughput 개선

  • Kim, Tae-Hyun
    • 한국정보통신설비학회:학술대회논문집
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    • 2008.08a
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    • pp.107-111
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    • 2008
  • 3GPP는 사용자의 다운링크 패킷 데이터 Throughput을 높이고,NodeB에 MAC계층을 위치시켜, 사용자의 스케줄링과 재전송을 담당하게 함으로써, 다운링크 패킷의 전송 지연을 감소시키는 HSDPA(High Speed Data Packet Access)기술을 Release 5에서 도입하였다. NodeB에 위치한 MAC-hs 스케줄러는 각각의 사용자에게 가용한 NodeB의 RF power와 code 자원을 제공하며, R99에서 사용했던 Power control을 이용하는 대신, AMC(Adaptive Modulation and Coding)기능을 제공하여 Radio conditions에 따라 전송되는 Data Format을 조정하여 채널환경이 좋은 사용자에게는 높은 data Throughput을 제공하며, 채널환경이 좋지 않은 사용자에게는 낮은 data throughput을 제공하고 있다. 본 고에서는 매 TTI에 스케줄링된 사용자에게 제공하고도, RF power 및 code 자원이 남아 있을 경우, 스케줄러는 남은 자원을 각각의 사용자에게 재 분배하여, 초기에 추정한 HSDPA Throughput보다 향상된 성능을 갖을 수 있음을 설명하였다.

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Determination of indoor doses and excess lifetime cancer risks caused by building materials containing natural radionuclides in Malaysia

  • Abdullahi, Shittu;Ismail, Aznan Fazli;Samat, Supian
    • Nuclear Engineering and Technology
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    • v.51 no.1
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    • pp.325-336
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    • 2019
  • The activity concentrations of $^{226}Ra$, $^{232}Th$, and $^{40}K$ from 102 building materials samples were determined using a high-purity germanium (HPGe) detector. The activity concentrations were evaluated for possible radiological hazards to the human health. The excess lifetime cancer risks (ELCR) were also estimated, and the average values were recorded as $0.42{\pm}0.24{\times}10^{-3}$, $3.22{\pm}1.83{\times}10^{-3}$, and $3.65{\pm}1.85{\times}10^{-3}$ for outdoor, indoor, and total ELCR respectively. The activity concentrations were further subjected to RESRAD-BUILD computer code to evaluate the long-term radiation exposure to a dweller. The indoor doses were assessed from zero up to 70 years. The simulation results were $92{\pm}59$, $689{\pm}566$, and $782{\pm}569{\mu}Sv\;y^{-1}$ for indoor external, internal, and total effective dose equivalent (TEDE) respectively. The results reported were all below the recommended maximum values. Therefore, the radiological hazards attributed to building materials under study are negligible.

Homogenization of KMRR Hafnium Control Assembly for 3-D Diffusion Calculation (3차원 중성자 확산계산을 위한 KMRR Hafnium 조정집합체 균질화에 대한 연구)

  • Park, Hang-Bok;Kim, Young-Jin;Kim, Hark-Rho;Lee, Ji-Bok
    • Nuclear Engineering and Technology
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    • v.20 no.4
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    • pp.233-240
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    • 1988
  • The hafnium shroud is used to control the excess reactivity and power distribution in KMRR. The core analysis is performed by the diffusion code VENTURE using the 5 group macroscopic cross sections homogenized for an assembly. Investigated are the applicability of the diffusion calculation by homogenized cross sections to the analysis of control assembly which features unusual geometry such that hafnium shroud surrounds a multiplying medium inside. Comparative calculation is performed for the excess reactivity and power levels by the transport code TWOTRAN. The results show the acceptability of the diffusion calculation by the homogenized cross sections without significant error.

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Parametric study on flexible footing resting on partially saturated soil

  • Singh, Mandeep;Sawant, V.A.
    • Coupled systems mechanics
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    • v.3 no.2
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    • pp.233-245
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    • 2014
  • Coupled finite element analysis is carried out to study the effect of degree of saturation on the vertical displacements and pore water pressures simultaneously by developing a FORTRAN90 code. The finite element formulation adopted in the present study is based upon Biot's consolidation theory to include partially saturated soils. Numerical methods are applied to a two-dimensional plane strain strip footing (flexible) problem and the effect of variable degree of saturation on the response of excess pore water pressure dissipation and settlement of the footing is studied. The immediate settlement in the case of partly saturated soils is larger than that of a fully saturated soil, the reason being the presence of pore air in partially saturated soils. On the other hand, the excess pore water pressure for partially saturated soil are smaller than those for fully saturated soil.

Use of americium as a burnable absorber for VVER-1200 reactor

  • Shelley, Afroza;Ovi, Mahmud Hasan
    • Nuclear Engineering and Technology
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    • v.53 no.8
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    • pp.2454-2463
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    • 2021
  • The objective of this research is to the use of americium (AmO2) as a burnable absorber effectively instead of conventional gadolinium (Gd2O3) for VVER-1200 reactor by analyzing its impacts on reactivity, power peaking factor (PPF), safety factor, and quality of the spent fuel. The assembly is burned to 60 GWd/t by using SRAC-2006 code and JENDL-4.0 data library for finding the optimum amount and effective way of using AmO2 as a burnable absorber. From these studies, it is found that AmO2 can decrease the excess reactivity like Gd2O3 without changing the criticality life span and enrichment of 235U. A homogeneous mixture of the 0.20% AmO2+ 4.95% enriched UO2 fuel rod (model MF-4) decreases the PPF than the reference assembly. The use of AmO2+UO2 in the integral burnable absorber (IBA) rod or the outer layer could also decrease the PPF up to 10 GWd/t but increases rapidly after 30 GWd/t, which could be a safety threat. The fuel temperature coefficient and void coefficient of the model MF-4 are the same as the reference assembly. In addition, 22% of initially loaded Am are burning effectively and contributing to the power production.

Burnable Absorber Design Study for a Passively-Cooled Molten Salt Fast Reactor

  • Nariratri Nur Aufanni;Eunhyug Lee;Taesuk Oh;Yonghee Kim
    • Nuclear Engineering and Technology
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    • v.56 no.3
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    • pp.900-906
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    • 2024
  • The Passively-Cooled Molten Salt Fast Reactor (PMFR) is one of the advanced design concepts of the Molten Salt Fast Reactor (MSFR) which utilizes a natural circulation for the primary loop and aims to attain a long-life operation without any means of fuel reprocessing. For an extended operation period, it is necessary to have enough fissile material, i.e., high excess reactivity, at the onset of operation. Since the PMFR is based on a fast neutron spectrum, direct implementation of a burnable absorber concept for the control of excess reactivity would be ineffective. Therefore, a localized moderator concept that encircles the active core has been envisioned for the PMFR which enables the effective utilization of a burnable absorber to achieve low reactivity swing and long-life operation. The modified PMFR design that incorporates a moderator and burnable absorber is presented, where depletion calculation is performed to estimate the reactor lifetime and reactivity swing to assess the feasibility of the proposed design. All the presented neutronic analysis has been conducted based on the Monte Carlo Serpent2 code with ENDF/B-VII.1 library.