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 Plus annual

Presents the access of premium content as premium feature

Premium Content

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 Plus monthly

Global: Zendy Tools annual

Global: Zendy Tools monthly

Global: Zendy Free Plan

A guide for the use of a new version of the Morse Monte Carlo Multigroup neutron and gamma ray transport code with combinatorial geometry is presented. This version is in current use for neutronics studies of blankets and shields for fusion power reactors designs. A benchmark problem treating a cell calculation for a fusion reactor blanket and shield design , is presented. The modifications introduced to the different routines, the deck organization for the CDC-7600 computer system, a sample problem input and output, and a set of recommendations are given.

Version of the MORSE multigroup transport code for fusion reactors blankets and shields studies