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Simulation of Time Dependent Neutron Transport in Fission Reactors Using Monte-carlo Method
| Content Provider | Semantic Scholar |
|---|---|
| Author | Mohsen, Shayesteh Majid, Shahriari Raeis Ali Gh. R. |
| Copyright Year | 2007 |
| Abstract | In this paper, time dependent neutron transport in fissionable media is simulated by Monte Carlo method, and the neutronic parameters are estimated. In this article, the effective multiplication factor, neutron lifetime, and flux distribution in steady state condition are calculated. The comparison of the results obtained by this method, with those of the experimental measurements and the other calculations have shown that they are in very good agreement. |
| Starting Page | 1 |
| Ending Page | 8 |
| Page Count | 8 |
| File Format | PDF HTM / HTML |
| Alternate Webpage(s) | https://jonsat.aeoi.org.ir/article_749_2dd744a2872f81166aaa12ef31de0b2e.pdf |
| Language | English |
| Access Restriction | Open |
| Content Type | Text |
| Resource Type | Article |