Neutron streaming Monte Carlo radiation transport code MORSE-CG

Journal Article · Sat Nov 01 04:00:00 EST 1986 · Fusion Technol.; (United States)

OSTI ID:7182338

Halley, A M; Miller, W H

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.

• OSTI ID: 7182338
• Journal Information: Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 10:3; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
COMPUTER CALCULATIONS
COMPUTER CODES
M CODES
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
RADIATION STREAMING
RADIATION TRANSPORT
SHIELDING
SHIELDS
STARFIRE TOKAMAK
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSPORT THEORY