Half-space albedo problem with modified FN method for linear and quadratic anisotropic scattering
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R. G. Türeci
und
D. Türeci
Abstract
One speed, time independent and homogeneous medium neutron transport equation can be solved with the anisotropic scattering which includes both the linear anisotropic and the quadratic anisotropic scattering properties. Having solved Case’s eigenfunctions and the orthogonality relations among these eigenfunctions, some neutron transport problems such as albedo problem can be calculated as numerically by using numerical or semi-analytic methods. In this study the half-space albedo problem is investigated by using the modified FN method.
Abstract
Die zeitunabhängige Eingruppen-Neutronentransportgleichung kann gelöst werden mit Hilfe der modifizierten FN-Methode für lineare und quadratische anisotrope Streuung. Nach Lösung der Case-Eigenfunktionen und der Orthogonalitätsrelationen zwischen diesen Eigenfunktionen, können einige Neutronentransportprobleme wie z.B. das Albedoproblem berechnet werden mit Hilfe numerischer oder semi-analytischer Methoden. In diesem Beitrag wird das Halbraum-Albedoproblem mit Hilfe der modifizierten F N-Methode näher untersucht.
References
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© 2017 Carl Hanser Verlag GmbH & Co. KG
Artikel in diesem Heft
- Frontmatter
- Best estimate approach for the evaluation of critical heat flux phenomenon in the boiling water reactors
- Coupled neutronic core and subchannel analysis of nanofluids in VVER-1000 type reactor
- PCTRAN enhancement for large break loss of coolant accident concurrent with loss of offsite power in VVER-1000 simulation
- Experimental study of natural circulation flow instability in rectangular channels
- Exerimental method and preliminary studies of the passive containment water film evaporation mass transfer
- Automated generation of burnup chain for reactor analysis applications
- Fission source sampling in coupled Monte Carlo simulations
- Hysteresis phenomenon in nuclear reactor dynamics
- Investigation of neutronic and safety parameters variation in 5 MW research reactor due to U3O8Al fuel conversion to ThO2 + U3O8Al
- Implementation of meso-scale radioactive dispersion model for GPU
- Solution of the multilayer multigroup neutron diffusion equation in cartesian geometry by fictitious borders power method
- Half-space albedo problem with modified FN method for linear and quadratic anisotropic scattering
Artikel in diesem Heft
- Frontmatter
- Best estimate approach for the evaluation of critical heat flux phenomenon in the boiling water reactors
- Coupled neutronic core and subchannel analysis of nanofluids in VVER-1000 type reactor
- PCTRAN enhancement for large break loss of coolant accident concurrent with loss of offsite power in VVER-1000 simulation
- Experimental study of natural circulation flow instability in rectangular channels
- Exerimental method and preliminary studies of the passive containment water film evaporation mass transfer
- Automated generation of burnup chain for reactor analysis applications
- Fission source sampling in coupled Monte Carlo simulations
- Hysteresis phenomenon in nuclear reactor dynamics
- Investigation of neutronic and safety parameters variation in 5 MW research reactor due to U3O8Al fuel conversion to ThO2 + U3O8Al
- Implementation of meso-scale radioactive dispersion model for GPU
- Solution of the multilayer multigroup neutron diffusion equation in cartesian geometry by fictitious borders power method
- Half-space albedo problem with modified FN method for linear and quadratic anisotropic scattering
