Neutron attenuation in the laser ducts of an inertial-confinement fusion reactor

Technical Report · Sun Nov 01 04:00:00 EST 1981

DOI:https://doi.org/10.2172/5222643· OSTI ID:5222643

Augustine, F. Jr.

This report deals with the problem of neutron streaming through the laser beam ducts of an inertial confinement fusion power plant. The neutron flux through these ducts must be attenuated by a factor of 10/sup 12/ to meet radiological safety limits. The problem is dealt with by using mirrors to bend the path of the laser beam while cutting off a line of sight path for neutrons. The Monte Carlo Code MCNP was used to analyze the two mirror SOLASE design, which only attenuated the neutron flux by a factor of 10/sup 3/. The Westinghouse design, initially assuming four mirrors, attenuated the neutron flux by 10/sup 4/ per mirror bend, and hence only three mirror bends were needed. Further studies also revealed that the large length/diameter ratio of the ducts and the thinner mirror design were crucial to the large attenuation. It may also be possible to develop a two mirror system, at 10/sup 6/ attenuation per mirror bend, utilizing improvements such as point cross overs, a second flux trap, and acute column-to-column angles. Further studies are needed to check this possibility.

• Research Organization: Rensselaer Polytechnic Inst., Troy, NY (USA). Dept. of Nuclear Engineering
• DOE Contract Number: AC02-77ET51010
• OSTI ID: 5222643
• Report Number(s): WFPS-TME-81-031; ON: DE82007195
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
ATTENUATION
HAZARDS
HEALTH HAZARDS
LASER FUSION REACTORS
MIRRORS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
OPTICAL SYSTEMS
RADIATION FLUX
RADIATION HAZARDS
RADIATION TRANSPORT
SAFETY
THERMONUCLEAR REACTORS