Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor
The present paper aims to compare the calculated and measured spectra after insertion of candidate materials for the Molten salt reactor/Fluoride cooled high temperature reactor system concept into the LR-0 reactor. The calculation is realized with MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3,...
Main Authors: | , , , , , , , , , , , , |
---|---|
Other Authors: | |
Format: | Article |
Language: | en_US |
Published: |
Elsevier
2017
|
Online Access: | http://hdl.handle.net/1721.1/111160 https://orcid.org/0000-0003-1459-7672 |