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Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code
Ghaderi Mazaher, M ; Sharif University of Technology | 2019
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- Type of Document: Article
- DOI: 10.1016/j.anucene.2019.02.045
- Publisher: Elsevier Ltd , 2019
- Abstract:
- Transient analysis which is vital in safety analysis requires a reliable calculation method. Most valid tools use diffusion theory with many approximations by now. However, the Monte Carlo method inherently overcomes these approximations and accurately calculates the parameters of a reactor. In this paper, a new time-dependent transport approach is described to simulate the nuclear reactor dynamic correctly using the MCNPX code. In this approach the fundamental parameters of a nuclear reactor like multiplication factor (K eff ) and mean generation time (t G ) are calculated using MCNPX code. They are then employed in the formulas to compute neutron population, proportional to K eff , during a generation time as well as precursors are decayed. Based on the approach, a dynamic Monte Carlo code namely DMCNP (Dynamical MCNPX code) is developed for a time-dependent simulation of particle tracking in an arbitrary geometry, considering the thermal-hydraulic feedbacks. The effects of temperature on cross section and density are applied at each time steps. Several test problems such as TWIGL, LMW, LRA and C5G7 are examined to assess the performance of the method. © 2019 Elsevier Ltd
- Keywords:
- Doppler Feedback ; MCNPX code ; Mean generation time ; Monte Carlo method ; Multiplication factor ; Thermal-hydraulic feedback ; Time-dependent transport ; Transient analysis ; Codes (symbols) ; Nuclear reactors ; Doppler ; Generation time ; MCNPX code ; Thermal hydraulics ; Monte Carlo methods
- Source: Annals of Nuclear Energy ; Volume 130 , 2019 , Pages 240-249 ; 03064549 (ISSN)
- URL: https://www.sciencedirect.com/science/article/pii/S0306454919301203