Neutron streaming through diagnostic penetrations in a fusion reactor shield
Technical Report
·
OSTI ID:5435346
Monte Carlo calculations of neutron fluxes were made for several types of diagnostic penetrations in a realistic fusion reactor shield, and the results compared with classical streaming theory. Calculations and theory agreed well in straight penetrations, but calculated neutron transport in penetrations with elbows was higher than predicted by theory.
- Research Organization:
- GA Technologies, Inc., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76ET51011
- OSTI ID:
- 5435346
- Report Number(s):
- GA-A-16844; ON: DE84005323
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
RADIATION FLUX
RADIATION STREAMING
RADIATION TRANSPORT
SHIELDING
THERMONUCLEAR REACTORS
TRANSPORT THEORY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
RADIATION FLUX
RADIATION STREAMING
RADIATION TRANSPORT
SHIELDING
THERMONUCLEAR REACTORS
TRANSPORT THEORY