Eigenvalue sensitivity and uncertainty analysis based on a 2-D/1-D whole-core transport code KYADJ

2018 ◽  
Vol 122 ◽  
pp. 185-192 ◽  
Author(s):  
Qu Wu ◽  
Jiankai Yu ◽  
Guanlin Shi ◽  
Xiao Tang ◽  
Yingrui Yu ◽  
...  
Keyword(s):  
Uncertainty Analysis ◽  
Eigenvalue Sensitivity ◽  
Transport Code ◽  
Sensitivity And Uncertainty Analysis

scholarly journals Sensitivity and uncertainty analysis of βeff for MYRRHA using a Monte Carlo technique

2018 ◽  
Vol 4 ◽  
pp. 42 ◽  
Author(s):  
Hiroki Iwamoto ◽  
Alexey Stakovskiy ◽  
Luca Fiorito ◽  
Gert Van den Eynde
Keyword(s):  
Monte Carlo ◽  
Uncertainty Analysis ◽  
Nuclear Data ◽  
Ratio Method ◽  
Delayed Neutron ◽  
Continuous Energy ◽  
A Value ◽  
Transport Code ◽  
Sensitivity And Uncertainty Analysis ◽  
Data Sensitivity

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.

scholarly journals Perturbation Theory-Based Whole-Core Eigenvalue Sensitivity and Uncertainty (SU) Analysis via a 2D/1D Transport Code

2020 ◽  
Vol 2020 ◽  
pp. 1-13
Author(s):  
Ji Ma ◽  
Chen Hao ◽  
Lixun Liu ◽  
Yuekai Zhou
Keyword(s):  
Perturbation Theory ◽  
Uncertainty Analysis ◽  
Cross Sections ◽  
Nuclear Reactor ◽  
Neutron Transport ◽  
Group Structure ◽  
Sensitivity Coefficient ◽  
Numerical Results ◽  
Transport Code ◽  
Sensitivity And Uncertainty Analysis

For nuclear reactor physics, uncertainties in the multigroup cross sections inevitably exist, and these uncertainties are considered as the most significant uncertainty source. Based on the home-developed 3D high-fidelity neutron transport code HNET, the perturbation theory was used to directly calculate the sensitivity coefficient of keff to the multigroup cross sections, and a reasonable relative covariance matrix with a specific energy group structure was generated directly from the evaluated covariance data by using the transforming method. Then, the “Sandwich Rule” was applied to quantify the uncertainty of keff. Based on these methods, a new SU module in HNET was developed to directly quantify the keff uncertainty with one-step deterministic transport methods. To verify the accuracy of the sensitivity and uncertainty analysis of HNET, an infinite-medium problem and the 2D pin-cell problem were used to perform SU analysis, and the numerical results demonstrate that acceptable accuracy of sensitivity and uncertainty analysis of the HNET are achievable. Finally, keff SU analysis of a 3D minicore was analyzed by using the HNET, and some important conclusions were also drawn from the numerical results.

Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation

2016 ◽  
Author(s):  
Yong Liu ◽  
Liangzhi Cao ◽  
Hongchun Wu ◽  
Tiejun Zu ◽  
Qingming He
Keyword(s):  
Uncertainty Analysis ◽  
Cross Section ◽  
Cross Sections ◽  
Indirect Effect ◽  
Sensitivity Coefficient ◽  
Eigenvalue Sensitivity ◽  
Nuclear Cross Section ◽  
Transport Calculation ◽  
Calculation Results ◽  
Sensitivity And Uncertainty Analysis

Accurate nuclear cross-section sensitivity-coefficient evaluation is important for sensitivity and uncertainty analysis, similarity analysis, cross-section adjustment et al. A cross-section perturbation will affect the lattice-physics calculation results through the transport calculation directly and through the resonance calculation indirectly. The indirect effect was found to be important in some cases in the previous studies. To quantify the indirect effect on the lattice-physics calculation results for subgroup resonance calculation method, a sensitivity and uncertainty analysis code COLEUS was developed based the GPT-based method. The eigenvalue sensitivity to non-resonance nuclide cross sections was investigated. Numerical results show that in the traditional LWR, the sensitivity coefficients will be overestimated if implicit sensitivity is neglected. And in the BWR, the implicit sensitivity will become more important along with the temperature rise. But if resonance fission and resonance capture play a coequal role or the background cross section is big, the implicit sensitivity can be small.

Improvement of sensitivity and uncertainty analysis capabilities of generalized response in Monte Carlo code RMC

2021 ◽  
Vol 154 ◽  
pp. 108099
Author(s):  
Guanlin Shi ◽  
Yuchuan Guo ◽  
Conglong Jia ◽  
Zhiyuan Feng ◽  
Kan Wang ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Uncertainty Analysis ◽  
Monte Carlo Code ◽  
Sensitivity And Uncertainty Analysis

Sensitivity and uncertainty analysis of neutronic and kinetic parameters for CERCER and CERMET fueled ADS using SERPENT 2 and ENDF/B-VIII.0

2022 ◽  
Vol 168 ◽  
pp. 108912
Author(s):  
Thanh Mai Vu ◽  
Donny Hartanto ◽  
Thoi Nam Chu ◽  
Nhu Viet Ha Pham ◽  
Thi Hong Bui
Keyword(s):  
Uncertainty Analysis ◽  
Kinetic Parameters ◽  
Sensitivity And Uncertainty Analysis
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