http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
Islam, Siraj-Ul,Haq, Fazal-I,Tirmizi, Ikram A. The Korean Society for Computational and Applied M 2010 Journal of applied mathematics & informatics Vol.28 No.3
A Numerical scheme based on collocation method using quartic B-spline functions is designed for the numerical solution of one-dimensional modified equal width wave (MEW) wave equation. Using Von-Neumann approach the scheme is shown to be unconditionally stable. Performance of the method is validated through test problems including single wave, interaction of two waves and use of Maxwellian initial condition. Using error norms $L_2$ and $L_{\infty}$ and conservative properties of mass, momentum and energy, accuracy and efficiency of the suggested method is established through comparison with the existing numerical techniques.
Siraj-ul-Islam,Fazal-i-Haq,Ikram A. Tirmizi 한국전산응용수학회 2010 Journal of applied mathematics & informatics Vol.28 No.3
A Numerical scheme based on collocationmethod using quartic B-spline functions is designed for the numerical solution of one-dimensional modified equal width wave (MEW) wave equation. Using Von-Neumann approach the scheme is shown to be unconditionally stable. Performance of the method is validated through test problems including single wave,interaction of two waves and use of Maxwellian initial condition. Using error norms L2 and L1 and conservative properties of mass, momentum and energy, accuracy and efficiency of the suggested method is established through comparison with the existing numerical techniques.
Neutronics analysis of TRIGA Mark II research reactor
Haseebur Rehman,Siraj-ul-Islam Ahmad 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.1
This article presents clean core criticality calculations and control rod worth calculations for TRIGA(Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark coresusing Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysisusing Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, q) and 3-D (r, q, z),using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied usingvarious libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0), Joint Evaluated Fission andFusion File (JEFF-3.1), Japanese Evaluated Nuclear Data Library (JENDL-3.2), and Joint Evaluated File (JEF-2.2) nuclear data. The simulation results showed that the multiplication factor calculated for all thesedata libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134was also calculated with different homogenization approaches. A comparison was made with experimentaland reported Monte Carlo results, and it was found that, using proper homogenization ofabsorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantlyimproved.