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Dive into the research topics where Moussa Mahgerefteh is active.

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Featured researches published by Moussa Mahgerefteh.


Nuclear Technology | 1995

Evaluation of the uncertainties in the source distribution for pressure vessel neutron fluence calculations

Alireza Haghighat; Moussa Mahgerefteh; Bojan G. Petrovic

The methodology used to prepare the source for neutron fluence calculation at the reactor pressure vessel is examined, and its effect on the calculated cavity dosimeter reaction rate is evaluated. ...


Nuclear Technology | 1989

Heuristic optimization of pressurized water reactor fuel cycle design under general constraints

Hoju Moon; Samuel H. Levine; Moussa Mahgerefteh

Optimization techniques in fuel management have directed modern fuel cycle designs to use low-leakage loading patterns. Future optimization calculations involving low-leakage patterns must utilize nucleonic models that are both fast operationally and rigorous. A two-dimensional two-group diffusion theory code is developed and lattice homogenization constants are generated using a modified LEOPARD code to fulfill these criteria. Based on these two codes, a heuristic optimization study is performed that considers the general constraints (e.g., spent-fuel storage limit and mechanical burnup limit) given to a utility fuel cycle designer. The optimum cycle length that minimizes the fuel cost is {approximately} 600 effective full-power days for the conditions assumed.


Nuclear Technology | 2006

Genetic algorithm application for burnable poison placement in pwrs with optimized UO2/Gd2O3 fuel pin configurations

Serkan Yilmaz; Kostadin Ivanov; Samuel H. Levine; Moussa Mahgerefteh

In this paper, an efficient genetic algorithm has placed burnable poisons (BPs) into all of the fresh fuel positions in the core employing the optimized BP configurations and techniques developed in two previous papers. Of importance was the previous development of a Kinf filter, which greatly reduced the computational time. The Kinf filter eliminated many of the invalid genotypes/phenotypes before making a precise core depletion analysis. An extensive BP library was generated by the CASMO-4/TABLES-3 codes. The process was automated with a user-friendly program developed for this purpose. The BPs were vendor UO2/Gd2O3 fuel assembly designs used in a reference Three Mile Island Unit 1 core. The optimized UO2/Gd2O3 fuel pin configurations have small residual binding at end of cycle (EOC), and BP loading optimization results with 97.2 ppm soluble boron at EOC while it was 94.4 ppm with the available vendor designs. The result was that optimized UO2/Gd2O3 fuel pin configurations were developed with unique self-shielding properties and residual binding that also provided a 6.89% reduction in the total required Gd amount, providing extra savings in fuel cost.


Nuclear Technology | 2006

Genetic algorithm to optimize the UO2/Gd2O3 fuel pin designs in a pressurized water reactor

Serkan Yilmaz; Kostadin Ivanov; Samuel H. Levine; Moussa Mahgerefteh

An efficient and practical genetic algorithm (GA) was developed to optimize the UO2/Gd2O3 fuel pin burnable poison (BP) configurations for fresh fuel assembly (FA) designs loaded in a pressurized water reactor core. The objective of the optimization was to minimize the residual binding due to residual Gd isotopes in the fuel at the end of cycle (EOC). The GA process for creating new BP designs in a coded form called genotypes is generated randomly resulting in a large number of invalid designs. Each new BP design or genotype created by the new GA must be decoded into its corresponding phenotype so that it can be evaluated with a coupled fuel lattice and core depletion calculation. It is essential that most of the invalid designs be eliminated before performing the precise coupled fuel lattice calculation because of the long CPU time that it takes for this calculation. The elimination was accomplished in the new GA by incorporating a beginning-of-cycle (BOC) Kinf filter. The BOC Kinf filter eliminated most of the invalid new genotypes by assigning a high negative penalty to all genotypes that have a BOC Kinf greater than some limit (1.065) for the reference TMI-1 FA. This filter eliminates the need for performing coupled lattice and core depletion calculations for these genotypes. It accelerated the solution process and allowed evaluation of all new genotypes within one day. In this way, the GA minimized the residual binding using an objective function, which maximized the EOC soluble boron (SB) concentration. In essence, the EOC SB or its equivalent EOC keff was maximized.


Nuclear Technology | 2005

Optimizing the Placement of Burnable Poisons in PWRs

Serkan Yilmaz; Kostadin Ivanov; Samuel H. Levine; Moussa Mahgerefteh

The principal focus of this work is on developing a practical tool for designing the minimum amount of burnable poisons (BPs) for a pressurized water reactor using a typical Three Mile Island Unit 1 2-yr cycle as the reference design. The results of this study are to be applied to future reload designs. A new method, the Modified Power Shape Forced Diffusion (MPSFD) method, is presented that initially computes the BP cross section to force the power distribution into a desired shape. The method employs a simple formula that expresses the BP cross section as a function of the difference between the calculated radial power distributions (RPDs) and the limit set for the maximum RPD. This method places BPs into all fresh fuel assemblies (FAs) having an RPD greater than the limit. The MPSFD method then reduces the BP content by reducing the BPs in fresh FAs with the lowest RPDs. Finally, the minimum BP content is attained via a heuristic fine-tuning procedure. This new BP design program has been automated by incorporating the new MPSFD method in conjunction with the heuristic fine-tuning program. The program has automatically produced excellent results for the reference core, and has the potential to reduce fuel costs and save manpower.


Annals of Nuclear Energy | 2006

Application of genetic algorithms to optimize burnable poison placement in pressurized water reactors

Serkan Yilmaz; Kostadin Ivanov; Samuel H. Levine; Moussa Mahgerefteh


Annals of Nuclear Energy | 2006

Development of enriched Gd-155 and Gd-157 burnable poison designs for a PWR core

Serkan Yilmaz; Kostadin Ivanov; Samuel H. Levine; Moussa Mahgerefteh


Transactions of the american nuclear society | 2004

Optimized innovative burnable poison concepts for advanced PWR fuel management

Serkan Yilmaz; Kostadin Ivanov; Samuel H. Levine; Moussa Mahgerefteh


Transactions of the american nuclear society | 2004

Accuracy evaluation of pin exposure calculations in current LWR core design codes (phase 1)

Chanatip Tippayakul; Samuel H. Levine; Kostadin Ivanov; Robert J. Wolfgang; Moussa Mahgerefteh


Annals of Nuclear Energy | 2008

Accuracy evaluation of pin exposure calculations in current LWR core design codes

Vuyani Xulubana; Chanatip Tippayakul; Kostadin Ivanov; Samuel H. Levine; Moussa Mahgerefteh

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Samuel H. Levine

Pennsylvania State University

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Kostadin Ivanov

Pennsylvania State University

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Serkan Yilmaz

Pennsylvania State University

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Chanatip Tippayakul

Pennsylvania State University

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A. Haghighat

Pennsylvania State University

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Bojan G. Petrovic

Pennsylvania State University

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H.L. Hanshaw

Pennsylvania State University

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John C. Wagner

Oak Ridge National Laboratory

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Vuyani Xulubana

Pennsylvania State University

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