Published November 1986
| Version v1
Journal article
Neutron streaming Monte Carlo radiation transport code MORSE-CG
Creators
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
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18033975
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COMPUTER CALCULATIONS; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; RADIATION STREAMING; SHIELDING; SHIELDS; STARFIRE TOKAMAK
- Descriptors DEC
- CLOSED PLASMA DEVICES; COMPUTER CODES; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TRANSPORT THEORY