• Title, Summary, Keyword: Serpent

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A Study on MT-Serpent Cryptographic Algorithm Design for the Portable Security System (휴대용 보안시스템에 적합한 MT-Serpent 암호알고리즘 설계에 관한 연구)

  • Lee, Seon-Keun;Jeong, Woo-Yeol
    • Journal of the Korea Society of Computer and Information
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    • v.13 no.6
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    • pp.195-201
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    • 2008
  • We proposed that is suitable network environment and wire/wireless communication network, easy of implementation, security level preservation, scalable & reconfigurable to TCP/IP protocol architecture to implement suitable smart card MS-Serpent cryptographic algorithm for smart card by hardware base chip level that software base is not implement. Implemented MT-Serpent cryptosystem have 4,032 in gate counter and 406.2Mbps@2.44MHz in throughput. Implemented MS-Serpent cryptographic algorithm strengthens security vulnerability of TCP/IP protocol to do to rescue characteristic of smart card and though several kind of services are available and keep security about many user in wire/wireless environment, there is important purpose.

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Improved Result on the Pseudorandomness of SPN-type transformations (SPN 블록 암호 구조의 의사 난수성에 대한 향상된 결과)

  • 이원일
    • Journal of the Korea Institute of Information Security & Cryptology
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    • v.14 no.1
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    • pp.91-99
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    • 2004
  • Iwata et al. analyzed the pseudorandomness of the block cipher Serpent which is a SPN-type transformation. In this parer, we introduce a generalization of the results, which can be applied to any SPN-type transformation. For the purpose, we give several explicit definitions and prove our main theorems. We will also apply our theorems to several SPN-type transformations including Serpent, Crypton and Rijndael.

Improved Result on the Pseudorandomness of SPN-type transformation (SPN 구조의 의사 난수성에 대한 향상된 결과)

  • 이원일;홍석희;성재철;이상진
    • Proceedings of the Korea Institutes of Information Security and Cryptology Conference
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    • pp.57-61
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    • 2003
  • Iwata 등은 SPN 구조에 기반한 블록 암호들 중 Serpent에 대한 의사 난수성을 분석하였다 [2]. 그들은 Serpent의 구조를 최대한 보존한 상태에서 의사 난수성을 분석하기 위하여 Serpent의 Diffusion layer의 특성을 그대로 보존하여 일반화 한 후 이론을 전개하였다. 본 논문에서는 Serpent가 취한 Diffusion layer 뿐만 아니라 SPN 구조에 기반한 블록 암호들이 취할 수 있는 임의의 Diffusion layer에 대하여 적용 가능한 일반적인 이론을 도출해낼 것이다.

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Improved Differential-Linear Cryptanalysis Using DLCT (DLCT를 활용한 향상된 차분선형 분석)

  • Kim, Hyunwoo;Kim, Seonggyeom;Hong, Deukjo;Sung, Jaechul;Hong, Seokhie
    • Journal of the Korea Institute of Information Security & Cryptology
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    • v.28 no.6
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    • pp.1379-1392
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    • 2018
  • The complexity of the differential-linear cryptanalysis is strongly influenced by the probability of the differential-linear characteristic computed under the assumption of round independence, linear approximation independence, and uniformity for the trail that does not satisfy differential trail. Therefore, computing the exact probability of the differential-linear characteristic is a very important issue related to the validity of the attack. In this paper, we propose a new concept called DLCT(Differential-Linear Connectivity Table) for the differential-linear cryptanalysis. Additionally, we propose an improved probability computation technique of differential-linear characteristic by applying DLCT. By doing so, we were able to weaken linear approximation independence assumption. We reanalyzed the previous results by applying DLCT to DES and SERPENT. The probability of 7-round differential-linear characteristic of DES is $1/2+2^{-5.81}$, the probability of 9-round differential-linear characteristic of SERPENT is computed again to $1/2+2^{-57.9}$, and data complexity required for the attack is reduced by $2^{0.2}$ and $2^{2.2}$ times, respectively.

THE INVESTIGATION OF BURNUP CHARACTERISTICS USING THE SERPENT MONTE CARLO CODE FOR A SODIUM COOLED FAST REACTOR

  • Korkmaz, Mehmet E.;Agar, Osman
    • Nuclear Engineering and Technology
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    • v.46 no.3
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    • pp.407-412
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    • 2014
  • In this research, we investigated the burnup characteristics and the conversion of fertile $^{232}Th$ into fissile $^{233}U$ in the core of a Sodium-Cooled Fast Reactor (SFR). The SFR fuel assemblies were designed for burning $^{232}Th$ fuel (fuel pin 1) and $^{233}U$ fuel (fuel pin 2) and include mixed minor actinide compositions. Monte Carlo simulations were performed using Serpent Code1.1.19 to compare with CRAM (Chebyshev Rational Approximation Method) and TTA (Transmutation Trajectory Analysis) method in the burnup calculation mode. The total heating power generated in the system was assumed to be 2000 MWth. During the reactor operation period of 600 days, the effective multiplication factor (keff) was between 0.964 and 0.954 and peaking factor is 1.88867.

Karyotype Analysis of Korean Spotted Serpent Head [Channa argus (Cantor); Channiformes, Channidae] (한국산 가물치[Channa argus (Cantor);가물치목, 가물치과]의 핵형분석)

  • 이석우;이영재
    • The Korean Journal of Zoology
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    • v.29 no.2
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    • pp.75-78
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    • 1986
  • Karyotypes of Korean spotted serpent head [Channa argus (Cantor)] were analyzed to obtain a basic information on the cytogenetics of this fish. Diploid chromosome numbers were found to be 48, of which 2 were submetacentric, 10 were submeta- or subtelocentric, and 26 were acro- or telocentric chromosomes without notably hetermorphic sex chromosomes. Cytogenetical implications of the results are discussed.

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Neutronic analysis of fuel assembly design in Small-PWR using uranium mononitride fully ceramic micro-encapsulated fuel using SCALE and Serpent codes

  • Hakim, Arief Rahman;Harto, Andang Widi;Agung, Alexander
    • Nuclear Engineering and Technology
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    • v.51 no.1
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    • pp.1-12
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    • 2019
  • One of proposed Accident Tolerant Fuel (ATF) concept is fully ceramic micro-encapsulated fuel (FCMF). FCMF using uranium mononitride (UN) has better safety aspects than $UO_2$ pellet fuel although it might not have a better neutronic performance due to the presence of matrix and high neutron-induced interaction of $^{14}N$. Before implementing UN-FCMF technology in Small-PWR, further research must be taken place to make sure the proposed design of fuel assembly has inherent safety features and maintain the fuel performance. This study focusses on the neutronic analysis of UN-FCMF based fuel assembly using Serpent and SCALE codes. It is shown in the proposed fuel assembly design has inherent safety features with respect to the fuel temperature reactivity coefficient, void reactivity coefficient, and moderator temperature reactivity coefficient. It is noted that the use of FCMF leads to a lower ratio of burnup to $^{235}U$ enrichment ratio compared to the $UO_2/Zr$ fuel.

A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber

  • Yu, Hwanyeal;Yahya, Mohd-Syukri;Kim, Yonghee
    • Nuclear Engineering and Technology
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    • v.48 no.2
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    • pp.318-329
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    • 2016
  • Reducing critical boron concentration in a commercial pressurized water reactor core offers many advantages in view of safety and economics. This paper presents a preliminary investigation of a reduced-boron pressurized water reactor core to achieve a clearly negative moderator temperature coefficient at hot zero power using the newly-proposed "Burnable absorber-Integrated Guide Thimble" (BigT) absorbers. The reference core is based on a commercial OPR1000 equilibrium configuration. The reduced-boron ORP1000 configuration was determined by simply replacing commercial gadolinia-based burnable absorbers with the optimized BigT-loaded design. The equilibrium cores in this study were directly searched via repetitive Monte Carlo depletion calculations until convergence. The results demonstrate that, with the same fuel management scheme as in the reference core, application of the BigT absorbers can effectively reduce the critical boron concentration at the beginning of cycle by about 65 ppm. More crucially, the analyses indicate promising potential of the reduced-boron OPR1000 core with the BigT absorbers, as its moderator temperature coefficient at the beginning of cycle is clearly more negative and all other vital neutronic parameters are within practical safety limits. All simulations were completed using the Monte Carlo Serpent code with the ENDF/B-VII.0 library.

NUCLEAR DATA UNCERTAINTY PROPAGATION FOR A TYPICAL PWR FUEL ASSEMBLY WITH BURNUP

  • Rochman, D.;Sciolla, C.M.
    • Nuclear Engineering and Technology
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    • v.46 no.3
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    • pp.353-362
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    • 2014
  • The effects of nuclear data uncertainties are studied on a typical PWR fuel assembly model in the framework of the OECD Nuclear Energy Agency UAM (Uncertainty Analysis in Modeling) expert working group. The "Fast Total Monte Carlo" method is applied on a model for the Monte Carlo transport and burnup code SERPENT. Uncertainties on $k_{\infty}$, reaction rates, two-group cross sections, inventory and local pin power density during burnup are obtained, due to transport cross sections for the actinides and fission products, fission yields and thermal scattering data.

Physics study for high-performance and very-low-boron APR1400 core with 24-month cycle length

  • Do, Manseok;Nguyen, Xuan Ha;Jang, Seongdong;Kim, Yonghee
    • Nuclear Engineering and Technology
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    • v.52 no.5
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    • pp.869-877
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    • 2020
  • A 24-month Advanced Power Reactor 1400 (APR1400) core with a very-low-boron (VLB) concentration has been investigated for an inherently safe and high-performance PWR in this work. To develop a high-performance APR1400 which is able to do the passive frequency control operation, VLB feature is essential. In this paper, the centrally-shielded burnable absorber (CSBA) is utilized for an efficient VLB operation in the 24-month cycle APR1400 core. This innovative design of the VLB APR1400 core includes the optimization of burnable absorber and loading pattern as well as axial cutback for a 24-month cycle operation. In addition to CSBA, an Er-doped guide thimble is also introduced for partial management of the excess reactivity and local peaking factor. To improve the neutron economy of the core, two alternative radial reflectors are adopted in this study, which are SS-304 and ZrO2. The core reactivity and power distributions for a 2-batch equilibrium cycle are analyzed and compared for each reflector design. Numerical results show that a VLB core can be successfully designed with 24-month cycle and the cycle length is improved significantly with the alternative reflectors. The neutronic analyses are performed using the Monte Carlo Serpent code and 3-D diffusion code COREDAX-2 with the ENDF/B-VII.1.