Iterative solution of the neutron transport equation by means of diffusion techniques
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5081838
In the framework of the solution of the transport equation by means of diffusion techniques, an iterative procedure is presented that permits us to calculate the point-dependent diffusion coefficient, D/sub k/(k = x,y,z), by use of standard diffusion codes. Numerical comparisons show that this procedure attains a flux distribution much closer to the transport distribution after one iteration than the classical diffusion flux. The time of the calculation is about twice that required by classical diffusion. 8 figures.
- Research Organization:
- CNEN, Rome
- OSTI ID:
- 5081838
- Journal Information:
- Nucl. Sci. Eng.; (United States), Vol. 65:3
- Country of Publication:
- United States
- Language:
- English
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