English (United Kingdom)

https://curated-unify.zendy.io/wp-json/zendy-region/v1/featured_content/oa?rat=en

https://curated-unify.zendy.io/wp-json/zendy-region/v1/highlighted_journal/

Global: Zendy Tools annual

Presents the keyphrase highlighting as premium feature

Keyphrase Highlighting

Presents the summarisation as premium feature

Summarisation

Insights

Presents the pdf analysis as premium feature

PDF Analysis

Presents the zaia usage as premium feature

ZAIA

Global: Zendy Tools monthly

Global: Zendy Plus monthly

Presents the access of premium content as premium feature

Premium Content

Global: Zendy Plus annual

Global: Zendy Free Plan

The activity of an extended 241 Am sample with complex shielding and geometry has been measured by an 80% HPGe detector, after its irradiation by a neutron beam at 10.4 MeV, in order to determine the cross section of the reaction 241 Am(n,2n) 240 Am. Due to the complexity of sample’s geometry, the estimation of the detector’s efficiency has been achieved by MCNP5 Monte Carlo simulations. The simulations have been gradually evolved in order to define the detector model, the experimental setup geometry (geometry definition), the sample’s density and finally the detector’s efficiency for the irradiated 241 Am sample.

Monte Carlo MCNP modeling of a HPGe detector and its efficiency for extended sample geometry