Published November 1986 | Version v1
Journal article

Neutron streaming Monte Carlo radiation transport code MORSE-CG

Description

Calculations have been performed using the Monte Carlo code, MORSE-CG, to determine the neutron streaming through various straight and stepped gaps between radiation shield sectors in the conceptual tokamak fusion power plant design STARFIRE. This design calls for ''pie-shaped'' radiation shields with gaps between segments. It is apparent that some type of offset, or stepped gap, configuration will be necessary to reduce neutron streaming through these gaps. To evaluate this streaming problem, a MORSE-to-MORSE coupling technique was used, consisting of two separate transport calculations, which together defined the entire transport problem. The results define the effectiveness of various gap configurations to eliminate radiation streaming

Additional details

Publishing Information

Journal Title
Fusion Technol.
Journal Volume
10
Journal Issue
3
Series
Fusion Technol.
Journal Page Range
424-430
ISSN
0748-1896
CODEN
FUSTE