Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
5497789 | Applied Radiation and Isotopes | 2017 | 15 Pages |
Abstract
A well-defined neutron spectrum is essential for many types of experimental topics and is also important for both calibration and testing of spectrometric and dosimetric detectors. Provided it is well described, such a spectrum can also be employed as a reference neutron field that is suitable for validating selected cross sections. The present paper aims to compare calculations and measurements of such a well-defined spectra in geometrically similar cores of the LR-0 reactor with fuel containing slightly different enrichments (2%, 3.3% and 3.6%). The common feature to all cores is a centrally located dry channel which can be used for the insertion of studied materials. The calculation of neutron and gamma spectra was realized with the MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Only minor differences in neutron and gamma spectra were found in the comparison of the presented reactor cores with different fuel enrichments. One exception is the gamma spectrum in the higher energy region (above 8Â MeV), where more pronounced variations could be observed.
Related Topics
Physical Sciences and Engineering
Physics and Astronomy
Radiation
Authors
Michal Košťál, ZdenÄk MatÄj, FrantiÅ¡ek Cvachovec, VojtÄch Rypar, Evžen Losa, JiÅà Rejchrt, Filip Mravec, Martin VeÅ¡krna,