Abstract
Full-core reactor dynamics calculation involves the coupled modelling of thermal hydraulics and the time-dependent behaviour of core neutronics. The reactor time constants include prompt neutron lifetimes, neutron reproduction times, effective delayed neutron fractions and the corresponding decay constants, typically divided into six or eight precursor groups. The calculation of these parameters is traditionally carried out using deterministic lattice transport codes, which also produce the homogenised few-group constants needed for resolving the spatial dependence of neutron flux. In recent years, there has been a growing interest in the production of simulator input parameters using the stochastic Monte Carlo method, which has several advantages over deterministic transport calculation. This paper reviews the methodology used for the calculation of reactor time constants. The calculation techniques are put to practice using two codes, the PSG continuous-energy Monte Carlo reactor physics code and MORA, a new full-core Monte Carlo neutron transport code entirely based on homogenisation. Both codes are being developed at the VTT Technical Research Centre of Finland. The results are compared to other codes and experimental reference data in the CROCUS reactor kinetics benchmark calculation.
| Original language | English |
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| Title of host publication | Proceedings of the International Youth Nuclear Congress 2008 |
| Number of pages | 10 |
| Publication status | Published - 2008 |
| MoE publication type | A4 Article in a conference publication |
| Event | International Youth Nuclear Congress, IYNC 2008 - Interlaken, Switzerland Duration: 20 Sept 2008 → 26 Sept 2008 |
Conference
| Conference | International Youth Nuclear Congress, IYNC 2008 |
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| Abbreviated title | IYNC 2008 |
| Country/Territory | Switzerland |
| City | Interlaken |
| Period | 20/09/08 → 26/09/08 |