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

Most modern criticality safety Monte Carlo codes have reached a good level of achievement concerning the implemented simulation algorithms. Discrepancies observed on final results (for example performed by different teams with different codes and data) are mainly due to the used nuclear data. Therefore, knowing and controlling the way of processing nuclear data libraries used by these codes is nowadays crucial. Recent MORET code (developed by IRSN) improvements have focused on the development of a prototypic continuous energy version. Indeed, so far, the cross sections used by the MORET code are read from external multi-group libraries. It has been then decided to plan new developments in MORET 5 to control the whole criticality calculation process, from the reading of nuclear data to the Monte Carlo simulation itself. The new features related to this new version will allow performing criticality calculations either with a multi-group or a continuous energy treatment. The goal of this paper is to present the main topics needed to ensure proper development of a continuous energy version of MORET, and the results concerning the use of various multi-group cross sections libraries in MORET.

Using various point wise and multi-group cross section libraries in MORET criticality calculations