Continous Energy Neutron Cross Section Data Library for MCDC

Variansyah, Ilham;Morgan, Joanna Piper

Description

This is the cross section library for the dynamic neutron transport code MC/DC [github], [documentation]. The data is published as .h5 files and is mono-temperature. This data is produced from data provided by OpenMC and is copmiled for MC/DC's use.This work was supported by the Center for Exascale Monte-Carlo Neutron Transport (CEMeNT) a PSAAP-III project funded by the Department of Energy, grant number: DE-NA003967.

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Metrics

Dataset Index

0.3

FAIR Score

54%

Citations

Mentions

Metrics Over Time

Publication Details

DOI

10.5281/zenodo.10426266

Publisher

Center for Exascale Monte Carlo Neutron Transport (CEMeNT)

Assigned Domain

Subfield

Radiation

Field

Physics and Astronomy

Domain

Physical Sciences

Confidence Score

100%

Source

Open Alex

Normalization Factors

53.85

CTw

1.00

MTw

1.00