Use of a small accelerator as a source of 14-MeV neutrons for shielding studies
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; TRN: 80-019659
- Resource Relation:
- Conference: 6. conference on application of accelerators in research and industry, Denton, TX, USA, Nov 1980
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
NEUTRON TRANSPORT
MEASURING METHODS
POLYETHYLENES
SHIELDING
STAINLESS STEEL-304
COCKCROFT-WALTON ACCELERATORS
EXPERIMENTAL DATA
FAST NEUTRONS
MEV RANGE 10-100
NEUTRON SOURCES
ACCELERATORS
ALLOYS
BARYONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DATA
ELECTROSTATIC ACCELERATORS
ELEMENTARY PARTICLES
ENERGY RANGE
FERMIONS
HADRONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MEV RANGE
NEUTRAL-PARTICLE TRANSPORT
NEUTRONS
NICKEL ALLOYS
NUCLEONS
NUMERICAL DATA
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PARTICLE SOURCES
POLYMERS
POLYOLEFINS
RADIATION SOURCES
RADIATION TRANSPORT
STAINLESS STEELS
STEELS
654003* - Radiation & Shielding Physics- Neutron Interactions with Matter