Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energy Covariance Data

2017 ◽  
Vol 187 (2) ◽  
pp. 154-165 ◽  
Author(s):  
Dong Hyuk Lee ◽  
Hyung Jin Shim ◽  
Chang Hyo Kim
2018 ◽  
Vol 4 ◽  
pp. 42 ◽  
Author(s):  
Hiroki Iwamoto ◽  
Alexey Stakovskiy ◽  
Luca Fiorito ◽  
Gert Van den Eynde

This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neutron fraction βeff for critical and subcritical cores of the MYRRHA reactor using the continuous-energy Monte Carlo N-Particle transport code MCNP. The βeff sensitivities are calculated by the modified k-ratio method proposed by Chiba. Comparing the βeff sensitivities obtained with different scaling factors a introduced by Chiba shows that a value of a = 20 is the most suitable for the uncertainty quantification of βeff. Using the calculated βeff sensitivities and the JENDL-4.0u covariance data, the βeff uncertainties for the critical and subcritical cores are determined to be 2.2 ± 0.2% and 2.0 ± 0.2%, respectively, which are dominated by delayed neutron yield of 239Pu and 238U.


2021 ◽  
Vol 154 ◽  
pp. 108099
Author(s):  
Guanlin Shi ◽  
Yuchuan Guo ◽  
Conglong Jia ◽  
Zhiyuan Feng ◽  
Kan Wang ◽  
...  

Author(s):  
Una Baker ◽  
Marat Margulis ◽  
Eugene Shwageraus ◽  
Emil Fridman ◽  
Antonio Jiménez-Carrascosa ◽  
...  

Abstract The Horizon 2020 ESFR-SMART project investigates the behaviour of the commercial-size European Sodium-cooled Fast Reactor (ESFR) throughout its lifetime. This paper reports work focused on the End of Equilibrium Cycle (EOEC) loading of the ESFR, including neutronic analysis, core- and zone-wise reactivity coefficients, and more detailed local mapping of important safety-relevant parameters. Sensitivity and uncertainty analysis on these parameters have also been performed and a detailed investigation into decay heat mapping carried out. Due to the scope of this work the results have been split into three papers. The nominal operating conditions and both zone-wise and local mapping of reactivity coefficients are considered in this paper; the sensitivity and uncertainty analysis are detailed in Margulis et al. [1]; and the decay heat mapping calculations are reported in Jimenez-Carrascosa et al. [2]. The work was performed across four institutions using both continuous-energy Monte Carlo and deterministic reactor physics codes. A good agreement is observed between the methods, verifying the suitability of these codes for simulation of large, complicated reactor configurations; and giving confidence in the results for the most limiting ESFR EOEC core state for safety analysis. The results from this work will serve as basis for the transient calculations planned for the next stage of work on the ESFR, allowing for more in-depth studies to be performed on the multiphysics behaviour of the reactor.


Author(s):  
E. -G. Espinosa–Martínez ◽  
C. Martin-del-Campo ◽  
J. L. Francois ◽  
S. Quezada–García ◽  
A. Vázquez-Rodríguez ◽  
...  

2017 ◽  
Vol 108 ◽  
pp. 113-125 ◽  
Author(s):  
A.-D. Pérez-Valseca ◽  
G. Espinosa-Paredes ◽  
J.L. François ◽  
A. Vázquez Rodríguez ◽  
C. Martín-del-Campo

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