Comparison of calculated and experimental neutron attenuation and streaming data for fusion reactor design
Integral experiments that measure the neutron and gamma-ray energy spectra resulting from the attenuation of approx. 14 MeV T(D,n)/sup 4/He reaction neutrons in laminated slabs of stainless steel type 304, borated polyethylene, and a tungsten alloy (Hevimet) and from neutrons streaming through a 30-cm-diameter iron duct (L/D = 3) imbedded in a concrete shield have been performed at the Oak Ridge National Laboratory. The facility, NE-213 liquid scintillator detector system, and experimental techniques used to obtain the measured data are described. The two-dimensional discrete ordinates radiation transport codes, calculational models, and nuclear data used in the analysis of the experiments are reviewed.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5053497
- Report Number(s):
- CONF-800950-2; TRN: 80-015871
- Resource Relation:
- Conference: 11. symposium on fusion technology, Oxford, UK, 15 Sep 1980
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CONCRETES
NEUTRON TRANSPORT THEORY
POLYETHYLENES
STAINLESS STEEL-304
THERMONUCLEAR REACTORS
TUNGSTEN ALLOYS
DISCRETE ORDINATE METHOD
GAMMA SPECTRA
LIQUID SCINTILLATION DETECTORS
SHIELDING
ALLOYS
BUILDING MATERIALS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MEASURING INSTRUMENTS
NICKEL ALLOYS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
POLYMERS
POLYOLEFINS
RADIATION DETECTORS
SCINTILLATION COUNTERS
SPECTRA
STAINLESS STEELS
STEELS
TRANSPORT THEORY
700105* - Fusion Energy- Plasma Research- Plasma Kinetics-Theoretical- (-1987)