![SciELO - Brasil - Finite Element Method with Spectral Green's Function in Slab Geometry for Neutron Diffusion in Multiplying Media and One Energy Group Finite Element Method with Spectral Green's Function in SciELO - Brasil - Finite Element Method with Spectral Green's Function in Slab Geometry for Neutron Diffusion in Multiplying Media and One Energy Group Finite Element Method with Spectral Green's Function in](https://minio.scielo.br/documentstore/2179-8451/PPzrzf354R5fxQxWQHVgKVk/d42627140afbf2c3577edcb42b5867035b514c49.jpg)
SciELO - Brasil - Finite Element Method with Spectral Green's Function in Slab Geometry for Neutron Diffusion in Multiplying Media and One Energy Group Finite Element Method with Spectral Green's Function in
![Full article: A Krylov–Schur solution of the eigenvalue problem for the neutron diffusion equation discretized with the Raviart–Thomas method Full article: A Krylov–Schur solution of the eigenvalue problem for the neutron diffusion equation discretized with the Raviart–Thomas method](https://www.tandfonline.com/na101/home/literatum/publisher/tandf/journals/content/tnst20/2017/tnst20.v054.i10/00223131.2017.1344577/20170830/images/tnst_a_1344577_m0017.gif)
Full article: A Krylov–Schur solution of the eigenvalue problem for the neutron diffusion equation discretized with the Raviart–Thomas method
![Solution of different geometries reflected reactors neutron diffusion equation using the homotopy perturbation method - ScienceDirect Solution of different geometries reflected reactors neutron diffusion equation using the homotopy perturbation method - ScienceDirect](https://ars.els-cdn.com/content/image/1-s2.0-S2211379718322538-gr2.jpg)
Solution of different geometries reflected reactors neutron diffusion equation using the homotopy perturbation method - ScienceDirect
![SOLVED: The one-dimensional neutron diffusion equation with a (plane) source is -D (d^2φ(x))/(d x^2)+K^2 D φ(x)=Q δ(x) where φ(x) is the neutron flux, Q δ(x) is the (plane) source at x=0, and SOLVED: The one-dimensional neutron diffusion equation with a (plane) source is -D (d^2φ(x))/(d x^2)+K^2 D φ(x)=Q δ(x) where φ(x) is the neutron flux, Q δ(x) is the (plane) source at x=0, and](https://cdn.numerade.com/ask_previews/24abc57b-2a00-408c-9feb-2740e70e7963_large.jpg)
SOLVED: The one-dimensional neutron diffusion equation with a (plane) source is -D (d^2φ(x))/(d x^2)+K^2 D φ(x)=Q δ(x) where φ(x) is the neutron flux, Q δ(x) is the (plane) source at x=0, and
![PDF] The Solution of Two-Dimensional Neutron Diffusion Equation with Delayed Neutrons | Semantic Scholar PDF] The Solution of Two-Dimensional Neutron Diffusion Equation with Delayed Neutrons | Semantic Scholar](https://d3i71xaburhd42.cloudfront.net/2b840d4d6abee15c51274793ee92161ed7a4e266/5-Table4-1.png)
PDF] The Solution of Two-Dimensional Neutron Diffusion Equation with Delayed Neutrons | Semantic Scholar
![Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At. - ppt download Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At. - ppt download](https://slideplayer.com/8948357/27/images/slide_1.jpg)