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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