Calculated neutron and gamma-ray energy spectra from 14-MeV neutrons streaming through an iron duct: comparison with experiment
Integral experiments that measure the streaming of approx. 14 MeV neutrons through a 0.30-m-diameter iron duct (L/D approx. 3) imbedded in a concrete shield have been carried out at the Oak Ridge National Laboratory. Calculated and measured neutron and gamma-ray energy spectra are compared at sixteen detector locations on and off the cylindrical axis of the duct. The measured spectra were obtained using an NE-213 liquid scintillator detector with pulse-shape discrimination 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 methodologies are required to properly account for neutrons that single scatter from the duct to the detector. The calculated and measured outgoing neutron energy spectra above 850 keV agree within 5 to 50% depending on detector location and neutron energy. The calculated and measured gamma ray 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:
- 6278922
- Report Number(s):
- ORNL/TM-7878; ON: DE81030626
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BREEDING BLANKETS
BUILDING MATERIALS
CONCRETES
DUCTS
ELEMENTS
ENERGY RANGE
GAMMA SPECTRA
IRON
LIQUID SCINTILLATION DETECTORS
MATERIALS
MEASURING INSTRUMENTS
METALS
MEV RANGE
MEV RANGE 10-100
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SPECTRA
NEUTRON TRANSPORT
RADIATION DETECTORS
RADIATION TRANSPORT
REACTOR COMPONENTS
SCINTILLATION COUNTERS
SHIELDING
SPECTRA
TRANSITION ELEMENTS
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BREEDING BLANKETS
BUILDING MATERIALS
CONCRETES
DUCTS
ELEMENTS
ENERGY RANGE
GAMMA SPECTRA
IRON
LIQUID SCINTILLATION DETECTORS
MATERIALS
MEASURING INSTRUMENTS
METALS
MEV RANGE
MEV RANGE 10-100
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SPECTRA
NEUTRON TRANSPORT
RADIATION DETECTORS
RADIATION TRANSPORT
REACTOR COMPONENTS
SCINTILLATION COUNTERS
SHIELDING
SPECTRA
TRANSITION ELEMENTS