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Tuya, D.; Nagaya, Yasunobu
Journal of Nuclear Engineering (Internet), 4(4), p.691 - 710, 2023/11
The Monte Carlo method is used to accurately estimate various quantities such as k-eigenvalue and integral neutron flux. However, when a distribution of a quantity is desired, the Monte Carlo method does not typically provide continuous distribution. Recently, the functional expansion tally and kernel density estimation methods have been developed to provide continuous distribution. In this paper, we propose a method to estimate a continuous distribution of a quantity using artificial neural network (ANN) model with Monte Carlo-based training data. As a proof of concept, a continuous distribution of iterated fission probability (IFP) is estimated by ANN models in two systems. The IFP distributions by the ANN models were compared with the Monte Carlo-based data and the adjoint angular neutron fluxes by the PARTISN code. The comparisons showed varying degrees of agreement or discrepancy; however, it was observed that the ANN models learned the general trend of the IFP distributions.
Nakajima, Ken; ; Yamamoto, Toshihiro; ; Suzaki, Takenori
Journal of Nuclear Science and Technology, 31(11), p.1160 - 1170, 1994/11
Times Cited Count:7 Percentile:56.56(Nuclear Science & Technology)no abstracts in English
Obu, Makoto; ; Sakurai, Takeshi; Iijima, Susumu; *; Osugi, Toshitaka
JAERI-M 90-052, 52 Pages, 1990/03
no abstracts in English
Journal of Nuclear Science and Technology, 13(2), p.58 - 73, 1976/02
Times Cited Count:2no abstracts in English
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Journal of Inorganic and Nuclear Chemistry, 36(5), p.1141 - 1146, 1974/05
Times Cited Count:12no abstracts in English