Estimation of Continuous Distribution of Iterated Fission Probability Using an Artificial Neural Network with Monte Carlo-Based Training Data

Estimation of Continuous Distribution of Iterated Fission Probability Using an Artificial Neural Network with Monte Carlo-Based Training Data

The Monte Carlo neutron transport method is used to accurately estimate various quantities, such as k-eigenvalue and integral neutron flux. However, in the case of estimating a distribution of a desired quantity, the Monte Carlo method does not typically provide continuous distribution. Recently, th...

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Bibliographic Details
Main Authors: Delgersaikhan Tuya, Yasunobu Nagaya
Format: Article
Language:English
Published: MDPI AG 2023-11-01
Series:Journal of Nuclear Engineering
Subjects:
iterated fission probability
continuous distribution
Monte Carlo neutron transport
artificial neural network
machine learning
Online Access:https://www.mdpi.com/2673-4362/4/4/43

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