Comparison of measured and calculated neutron and gamma-ray energy spectra behind an in-line shielded duct
Integral experiments that measure the transport of approx. 14 MeV neutrons through a 0.30-m-diameter duct having a length-to-diameter ratio of 2.83 that is partially plugged with a 0.15 m diameter, 0.51 m long shield comprised of alternating layers of stainless steel type 304 and borated polyethylene have been carried out at the Oak Ridge National Laboratory. Measured and calculated neutron and gamma ray energy spectra are compared at several locations relative to the mouth of the duct. The measured spectra were obtained using an NE-213 liquid scintillator detector with pulse shape discrimination methods used to simultaneously resolve neutron and gamma ray events. The calculated spectra were obtained using a computer code network that incorporates two radiation transport methods: discrete ordinates (with P/sub 3/ multigroup cross sections) and Monte Carlo (with continuous point cross sections). The two radiation transport methods are required to account for neutrons that singly scatter from the duct to the detectors. The calculated and measured neutron energy spectra above 850 keV agree with 5 to 50% depending on detector location and neutron energy. The calculated and measured gamma ray energy spectra above 750 keV are also in favorable agreement, approx. 5 to 50%, depending on detector location and gamma ray energy.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5182049
- Report Number(s):
- ORNL/TM-8258; ON: DE82015856
- Country of Publication:
- United States
- Language:
- English
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Comparison of measured and calculated neutron and gamma ray energy spectra behind an in-line shielded duct
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALLOYS
BORON
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DISCRETE ORDINATE METHOD
ELEMENTS
GAMMA SPECTRA
GAMMA TRANSPORT THEORY
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID SCINTILLATION DETECTORS
MATERIALS
MEASURING INSTRUMENTS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SPECTRA
NEUTRON TRANSPORT
NICKEL ALLOYS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
POLYETHYLENES
POLYMERS
POLYOLEFINS
RADIATION DETECTORS
RADIATION STREAMING
RADIATION TRANSPORT
SCINTILLATION COUNTERS
SEMIMETALS
SHIELDING
SPECTRA
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTORS
TRANSPORT THEORY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALLOYS
BORON
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DISCRETE ORDINATE METHOD
ELEMENTS
GAMMA SPECTRA
GAMMA TRANSPORT THEORY
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID SCINTILLATION DETECTORS
MATERIALS
MEASURING INSTRUMENTS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SPECTRA
NEUTRON TRANSPORT
NICKEL ALLOYS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
POLYETHYLENES
POLYMERS
POLYOLEFINS
RADIATION DETECTORS
RADIATION STREAMING
RADIATION TRANSPORT
SCINTILLATION COUNTERS
SEMIMETALS
SHIELDING
SPECTRA
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTORS
TRANSPORT THEORY