Monte Carlo model for reactor core calculations in three dimensional geometry (in German)
Journal Article
·
· Atomkernenergie, v. 21, no. 4, pp. 279-289
OSTI ID:4375223
A model in three dimensions for the neutron transport problems is presented. This model deals with reactor systems with complicated arrangements of materials. The model utilizes the multigroup Monte Carlo techniques to provide a numerical solution of the Boltzmann-transport equation. Two different scattering kernels, namely the transport approximation and linear anisotropy, are considered. As a variance reducing method the model uses the statistical weights for the absorption. In addition to the calculation of the neutron spectra, the model predicts different reactor parameters that are important to reactor physics such as the absorption rate in the core and reflector, the life-time of the prompt neutrons, the fast fission factor and the reactivity. The applications of the model to PRG different core configurations showed good agreement with the experimental results. (GE)
- Research Organization:
- Univ., Kiel
- NSA Number:
- NSA-29-012060
- OSTI ID:
- 4375223
- Journal Information:
- Atomkernenergie, v. 21, no. 4, pp. 279-289, Journal Name: Atomkernenergie, v. 21, no. 4, pp. 279-289; ISSN ATKEA
- Country of Publication:
- Germany
- Language:
- German
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