Comparison of calculated and experimental neutron attenuation and streaming data for fusion reactor design

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:5053497

Santoro, R T; Alsmiller, Jr, R G; Barnes, J M; Chapman, G T

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
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700105* -- Fusion Energy-- Plasma Research-- Plasma Kinetics-Theoretical-- (-1987)
ALLOYS
BUILDING MATERIALS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONCRETES
CORROSION RESISTANT ALLOYS
DISCRETE ORDINATE METHOD
GAMMA SPECTRA
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID SCINTILLATION DETECTORS
MATERIALS
MEASURING INSTRUMENTS
NEUTRON TRANSPORT THEORY
NICKEL ALLOYS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
POLYETHYLENES
POLYMERS
POLYOLEFINS
RADIATION DETECTORS
SCINTILLATION COUNTERS
SHIELDING
SPECTRA
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTORS
TRANSPORT THEORY
TUNGSTEN ALLOYS