Publications (11) View all
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Article: Moderator temperature effects on reactivity of HEU core of MNSR
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ABSTRACT: In this article we report on analyses that were performed to investigate the influence of cross section differences among libraries released by various centers on reactivity of Miniature Neutron Source Reactors. The 3D model of the core was developed with WIMS-D and PRIDE codes and six cross section libraries were used including JENDL-3.2, JEF-2.2, JEFF-3.3, ENDF/B-VI and ENDF/B-VII, and IAEA library. It was observed that all the libraries predict the reactivity within 10%, with IAEA library giving minimum reactivity worth, and JEF-2.2 data library resulted in highest worth.Annals of Nuclear Energy 11/2012; 49(1):207-211. · 0.90 Impact Factor -
Article: A new stochastic technique for Painlevé equation-I using neural network optimized with swarm intelligence.
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ABSTRACT: A methodology for solution of Painlevé equation-I is presented using computational intelligence technique based on neural networks and particle swarm optimization hybridized with active set algorithm. The mathematical model of the equation is developed with the help of linear combination of feed-forward artificial neural networks that define the unsupervised error of the model. This error is minimized subject to the availability of appropriate weights of the networks. The learning of the weights is carried out using particle swarm optimization algorithm used as a tool for viable global search method, hybridized with active set algorithm for rapid local convergence. The accuracy, convergence rate, and computational complexity of the scheme are analyzed based on large number of independents runs and their comprehensive statistical analysis. The comparative studies of the results obtained are made with MATHEMATICA solutions, as well as, with variational iteration method and homotopy perturbation method.Computational Intelligence and Neuroscience 01/2012; 2012:721867. -
Article: Optimization of core reload pattern for PARR-1 using evolutionary techniques
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ABSTRACT: A procedure for searching optimum loading pattern to ensure safe and efficient reactor utilization was established for Pakistan Research Reactor-1 (PARR-1). A 6 × 5 core of PARR-1 consisting of 24 standard fuel elements, 5 control fuel elements and one flux trap was used in the study. The optimum loading schemes for maximum cycle length and maximum thermal flux in the flux trap were recommended using the developed methodology.Nuclear Engineering and Design 10/2010; 240(10):2831–2835. · 0.76 Impact Factor -
Article: Influence of evaluated data of fission product poisons on criticality
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ABSTRACT: The main objective of this research is to study the influence of cross-section differences of fission product poisons among various newly released evaluated cross-section libraries ENDFB-VI.8, JENDL3.2, JEF2.2, IAEA, ENDFB-VII and JEFF3.1 on criticality of an MTR type research reactor. The effect of cross-sections of poisons on the reactivity was studied with the help of WIMSD and CITATION codes. Various cross-section libraries were used in SARC (System for Analysis of Reactor Core) code for the fuel cycle analysis. It was found that the negative reactivity induced due to 135Xe for the equilibrium core is around 36.00 mk whereas for 149Sm it ranges from 6.65 to 7.06 mk. The three libraries (JENDL3.2, IAEA and ENDFB-VII) resulted in small increase in the Xenon worth as compared to the other three libraries. For Samarium, JEFF3.1 gives the highest worth whereas ENDFB-VI.8 gives the least worth among the six libraries.Progress in Nuclear Energy 03/2009; 51(2):334-338. · 0.85 Impact Factor -
Article: Beryllium as reflector of MNSR
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ABSTRACT: The article deals with beryllium reflector effects on criticality of a miniature neutron source reactor, and the study of these effects for various cross-section evaluations. D-shape plates of beryllium are added on top of the reactor core to enhance reactivity of the system during operation. Fuel cycle analysis was carried out using SARC code. It was observed that reactivity effects of a particular thickness of beryllium remain nearly same during the whole life of the core. Up to 11% differences were observed between measured and calculated results for various libraries. The nearest match with the measured results was found for JENDL-3.2 library having maximum deviation of 5%.Annals of Nuclear Energy 09/2008; 35(9):1708-1712. · 0.90 Impact Factor
