Published December 1989 | Version v1
Journal article

Monte Carlo analysis of heavy water Helium-3 and lead as materials for nuclear fusion reactor breeder blankets

  • 1. McMaster Univ., Hamilton, ON (Canada). Dept. of Engineering Physics

Description

A multipurpose 3-dimensional Monte Carlo neutron transport code, HEMCNT has been used to calculate neutronic parameters of interest for multi-regioned fusion reactors and neutron shields consisting of heavy water, lead, and Helium-3. Output system parameters include: a) neutron flux Φ(r,E), b)neutron leakage spectrum c) equipartition between the number of nuclear reactions and the heat released by each material, normalized per source neutron d) reaction rates and e) power density rates. (author)

Additional details

Publishing Information

Journal Title
Tokyo Denki Daigaku Kogakubu Kenkyu Hokoku
Journal Issue
no.37
Series
Tokyo Denki Daigaku Kogakubu Kenkyu Hokoku.
ISSN
0389-617X
CODEN
RPFUD