Nucleonic analysis of a preliminary design for the ETF neutral-beam-injector duct shielding
Conference
·
OSTI ID:7072474
A nucleonic analysis of the Engineering Test Facility Neutral-Beam-Injector duct shielding has been made using a hybrid Monte Carlo/discrete-ordinates method. This method used Monte Carlo to determine internal and external boundary surface sources for a subsequent discrete-ordinates calculation of the neutron and gamma-ray transport through the shield. The analysis also included determination of the energy and angular distribution of neutrons and gamma rays entering the duct from the torus plasma chamber. Confidence in the hybrid method and the results obtained were provided through a comparison with three-dimensional Monte Carlo results.
- Research Organization:
- Los Alamos Scientific Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7072474
- Report Number(s):
- LA-UR-80-2926; CONF-801011-59
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BEAM TRANSPORT
DISCRETE ORDINATE METHOD
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
IONIZING RADIATIONS
MONTE CARLO METHOD
NEUTRAL BEAM SOURCES
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
RADIATION TRANSPORT
RADIATIONS
SHIELDING
THERMONUCLEAR REACTORS
TOKAMAK ETF
TOKAMAK TYPE REACTORS
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BEAM TRANSPORT
DISCRETE ORDINATE METHOD
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
IONIZING RADIATIONS
MONTE CARLO METHOD
NEUTRAL BEAM SOURCES
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
RADIATION TRANSPORT
RADIATIONS
SHIELDING
THERMONUCLEAR REACTORS
TOKAMAK ETF
TOKAMAK TYPE REACTORS