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Author

Sedat Goluoglu

Other affiliations: University of Tennessee
Bio: Sedat Goluoglu is an academic researcher from Oak Ridge National Laboratory. The author has contributed to research in topics: Criticality & Monte Carlo method. The author has an hindex of 7, co-authored 32 publications receiving 235 citations. Previous affiliations of Sedat Goluoglu include University of Tennessee.

Papers
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Journal ArticleDOI
TL;DR: In this paper, an improved quasi-static method is applied to the time-dependent, three-dimensional neutron transport equation with explicit representation of delayed neutrons, and the resulting new code, which uses a threedimensional, discrete ordinates code (TORT) to solve the static fixed-source equations, is tested using transient benchmark problems.
Abstract: An improved quasi-static method is applied to the time-dependent, three-dimensional neutron transport equation with explicit representation of delayed neutrons. The relevant equations are derived, and the corresponding implementation of the method is presented. The resulting new code, which uses a three-dimensional, discrete ordinates code (TORT) to solve the static fixed-source equations, is tested using transient benchmark problems that are available in the literature. Results obtained with the new time-dependent code, named TDTORT, are in satisfactory agreement with the benchmark problem results.

60 citations

Journal ArticleDOI
TL;DR: Development of the Monte Carlo solution technique and solution methodology as applied in both KENO codes is explained and performance of the codes is demonstrated using published benchmark problems.
Abstract: This paper describes the Monte Carlo codes KENO V.a and KENO-VI in SCALE that are primarily used to calculate multiplication factors and flux distributions of fissile systems. Both codes allow explicit geometric representation of the target systems and are used internationally for safety analyses involving fissile materials. KENO V.a has limiting geometric rules such as no intersections and no rotations. These limitations make KENO V.a execute very efficiently and run very fast. On the other hand, KENO-VI allows very complex geometric modeling. Both KENO codes can utilize either continuous-energy or multigroup cross-section data and have been thoroughly verified and validated with ENDF libraries through ENDF/B-VII.0, which has been first distributed with SCALE 6. Development of the Monte Carlo solution technique and solution methodology as applied in both KENO codes is explained in this paper. Available options and proper application of the options and techniques are also discussed. Finally, performance of the codes is demonstrated using published benchmark problems.

51 citations

01 Jan 1996
TL;DR: In this paper, an improved version of the code TDKENO-M is presented for solving the time-dependent, 3-d Boltzmann Transport Equation with explicit representation of delayed neutrons.
Abstract: This research develops an improved methodology (and corresponding code) for solving the time-dependent, 3-d Boltzmann Transport Equation with explicit representation of delayed neutrons. These improvements are incorporated in a modified version of the code TDKENO, entitled TDKENO-M. Specifically, these improvements are: (1) incorporate the improved quasistatic methodology into an existing quasistatic framework, specifically, include the flux shape derivative in the fixed source term instead of being neglected, also, compute the point kinetics parameters deterministically by their inner product definitions; (2) incorporate a hierarchy of three different integration time intervals for the numerical solution of the coupled set of ordinary differential equations, the shape function is assumed to vary linearly over the largest time interval, the second large time interval is used for determining the point kinetics parameters, finally, the smallest time step is used for solving the point kinetics equations; (3) apply TDKENO-M to benchmark problems to determine the accuracy of the method, particularly, TDKENO-M is applied to 1-D and 3-D benchmark problems to evaluate its capabilities; (4) combine input requirements into a single input file so that TDKENO-M is less cumbersome to execute; (5) develop the ability to restart a calculation at an intermediate problem time; and (6) develop a user-friendly manual for using TDKENO-M which describes in detail the input requirements as well as the output files, subroutines, modules, and the calculational flow.

18 citations

Journal ArticleDOI
TL;DR: In this article, a preliminary design of a Molten chloride salt fast-reactor (MCFR) has been developed using the fast reactor codes DIF3D, PERSENT, GAMSOR, and MC2-3.

11 citations


Cited by
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Proceedings ArticleDOI
23 Aug 1992
TL;DR: Mes premiers remtrciements trout aux auteurs des 206 communications th6matiquts et notes de projet, sans qui ces actes n'auraient 6videmment pas vu le jour.
Abstract: Mes premiers remtrciements trout aux auteurs des 206 communications th6matiquts et notes de projet, sans qui ces actes n'auraient 6videmment pas vu le jour. / Is oat contribu6 h la qualit6 scientifique et ,5 I'hmuog6t~6it6 pr6sentationntlle de leurs articles en refondant les versions iuitiales soumises an comit6 de programme, ea acceptant de suivre les r~gles de pr6sentation indiqu6es, et en nous envoyant parrots plusieurs versions am61ior6es surun point ou sur l'autrc.

824 citations

Journal ArticleDOI
01 May 1978
TL;DR: In this article, the authors have considered the interests of both scientists and practising engineers, in addition to serving the needs of the academia, in order to avoid lengthy and repetitive discussions, that are available in many standard text books on reactor physics.
Abstract: This is cne of the r-are text books written in the discipline of Nuclear Reactor Analysis, where the author has considered the interests of both scientists and practising engineers, in addition to serving the needs of the academia. The most attractive feature of this book is a balanced treatment of theory and practice of the subject matter. The theoretical foundations of the reactor design methods are explained with simplified definitions and relevant practical illustrations. The author scans through quickly the traditional aspects of the so-called reactor physics and takes the reader through the details of the analytical aspects in a conventional manner. Hcwever, there is a definite departure from the classical method of approach in order to avoid lengthy and repetitive discussions, that are available in many standard text books on reactor physics. The chief departure fran tradition is the priority accorded to the treatment of the energy part of the problems as opposed to the spatial Dart normally devoted to by other authors . A similar unorthodox approach has been applied while dealing with the solution of the various equations by giving priority to computer oriented mrethods as opposed to the classical solutions.

507 citations

Journal ArticleDOI
TL;DR: The version 6 of the Standardized Computer Analyses for Licensing Evaluation (SCALE) computer software system developed at Oak Ridge National Laboratory (ORNL) was released in February 2009 as mentioned in this paper.
Abstract: Version 6 of the Standardized Computer Analyses for Licensing Evaluation (SCALE) computer software system developed at Oak Ridge National Laboratory, released in February 2009, contains significant...

159 citations

Journal ArticleDOI
TL;DR: The theory of the 2D/1D method and its implementation in the MPACT code, which has become the whole-core deterministic neutron transport solver for the Consortium for Advanced Simulations of Light Water Reactors (CASL) core simulator VERA-CS are described.

97 citations

Journal ArticleDOI
TL;DR: Improved Quasi-static Method (IQM) as discussed by the authors is a standard tool for the space-time solution of neutron transport problems in multiplying media, where the shape equation is solved on a long time scale, while the amplitude is determined on a short time scale.

85 citations