Tez (Doktora) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2003Thesis (Ph.D.) -- İstanbul Technical University, Energy Institute, 2003Bu çalışma, Sınır Elemanları Yöntemi (Boundary Element Method-BEM) ve Sonlu Elemanlar Yöntemi (Finite Element Method-FEM)'ni birlikte kullanan Bileşik Yöntem (Combined Method), iki boyutlu, iki bölgeli ve iki gruplu nötron difüzyon denklemlerine uygulamak amacıyla gerçekleştirilmiştir. Ele alınan ortamın, fisyon olayının gerçekleştiği reaktör kalbi ve onun etrafını iki taraftan saran yansıtıcıdan oluştuğu varsayılmıştır. Kalp hesaplarında Sonlu Elemanlar Yöntemi; yansıtıcı hesaplarında Lineer Sınır Elemanları kullanılmıştır. Her iki bölge için yapılan işlemlerde, kalp ve yansıtıcı arayüzünde hem akı, he...
In this thesis, a code that can be used to perform 3 dimensional neutronics analysis of nuclear reac...
Tez (Yüksek Lisans) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2001Thesis (M.Sc.) -- İstanbu...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
Tez (Doktora) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2003Thesis (Ph.D.) -- İstanbul Tech...
Tez (Doktora) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2006Thesis (Ph.D.) -- İstanbul Tech...
Originally presented as the first author's thesis (Nucl. Eng.)--Massachusetts Institute of Technolog...
This work deals with the numerical solution of the neutron diffusion equation under conditions, whic...
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Nucl.E.Leaf [174]...
An application of a 3D Boundary Element Method (BEM) coupled with the Response Matrix (RM) technique...
The Boundary Element Method (BEM) has been competing for years with the Finite Element Method (FEM) ...
An application of a 3D Boundary Element Method (BEM), coupled with the Response Matrix (RM) techniqu...
Tez (Yüksek Lisans) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2001Thesis (M.Sc.) -- İstanbu...
The finite element response matrix method has been applied to the solution of the neutron transport ...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
Heterogeneous nuclear reactors require numerical methods to solve the neutron diffusion equation (ND...
In this thesis, a code that can be used to perform 3 dimensional neutronics analysis of nuclear reac...
Tez (Yüksek Lisans) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2001Thesis (M.Sc.) -- İstanbu...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
Tez (Doktora) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2003Thesis (Ph.D.) -- İstanbul Tech...
Tez (Doktora) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2006Thesis (Ph.D.) -- İstanbul Tech...
Originally presented as the first author's thesis (Nucl. Eng.)--Massachusetts Institute of Technolog...
This work deals with the numerical solution of the neutron diffusion equation under conditions, whic...
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Nucl.E.Leaf [174]...
An application of a 3D Boundary Element Method (BEM) coupled with the Response Matrix (RM) technique...
The Boundary Element Method (BEM) has been competing for years with the Finite Element Method (FEM) ...
An application of a 3D Boundary Element Method (BEM), coupled with the Response Matrix (RM) techniqu...
Tez (Yüksek Lisans) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2001Thesis (M.Sc.) -- İstanbu...
The finite element response matrix method has been applied to the solution of the neutron transport ...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
Heterogeneous nuclear reactors require numerical methods to solve the neutron diffusion equation (ND...
In this thesis, a code that can be used to perform 3 dimensional neutronics analysis of nuclear reac...
Tez (Yüksek Lisans) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2001Thesis (M.Sc.) -- İstanbu...
summary:We present a method for solving the equations of neutron transport with discretized energeti...