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Use of a small accelerator as a source of 14-MeV neutrons for shielding studies

Conference ·
OSTI ID:6837056
; ;
It is important in calculating complex shields such as those proposed for the fusion reactors to ascertain that the neutron cross-section data sets used in the calculations are as accurate as possible and that the calculational methods used to transport the neutrons are as reliable as practical. To assure that both these criteria are met, a project at the Oak Ridge National Laboratory (ORNL) is being conducted in which a small accelerator is used to provide 14-MeV neutrons via the T(d,n)/sup 4/He reaction and an NE-213 detector is used to measure the neutron and gamma-ray pulse-height spectra of the radiations transported through and/or created in very thick laminated shields of stainless steel (type 304) and borated polyethylene.
Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
6837056
Report Number(s):
CONF-801111-18
Country of Publication:
United States
Language:
English

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Related Subjects

654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACCELERATORS
ALLOYS
BARYONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COCKCROFT-WALTON ACCELERATORS
CORROSION RESISTANT ALLOYS
DATA
ELECTROSTATIC ACCELERATORS
ELEMENTARY PARTICLES
ENERGY RANGE
EXPERIMENTAL DATA
FAST NEUTRONS
FERMIONS
HADRONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MEASURING METHODS
MEV RANGE
MEV RANGE 10-100
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SOURCES
NEUTRON TRANSPORT
NEUTRONS
NICKEL ALLOYS
NUCLEONS
NUMERICAL DATA
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PARTICLE SOURCES
POLYETHYLENES
POLYMERS
POLYOLEFINS
RADIATION SOURCES
RADIATION TRANSPORT
SHIELDING
STAINLESS STEEL-304
STAINLESS STEELS
STEELS