Monte Carlo and discrete ordinates calculations for 14-MeV neutrons streaming through a stainless steel duct: comparisons with Experiment II

Technical Report · Sun Dec 01 04:00:00 EST 1985

DOI:https://doi.org/10.2172/6413939· OSTI ID:6413939

Santoro, R. T.; Barnes, J. M.; Alsmiller, Jr., R. G.; Drischler, J. D.

Measured and calculated neutron energy spectra from 14-MeV neutrons streaming through stainless steel ducts having length-to-diameter raios of 14.8 and 38.2 are compared in this paper. The measured data were obtained using an NE-213 liquid scintillator and the calculated data were obtained using the Monte Carlo code MCNP and the discrete ordinates code DOT 4.3. For both duct geometries, the spectra calculated using the MCNP code are in reasonable agreement with the measured data ranging from a few percent to a factor of two, depending on the detector location and duct. The spectra calculated using the DOT code are in fair agreement (30%) for cases where the detector is on the duct axis, but are in poor agreement, up to an order of magnitude, when the detector is off axis. 6 refs., 7 figs., 4 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6413939
• Report Number(s): ORNL/TM-9885; ON: DE86004640
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
DATA
DUCTS
ENERGY RANGE
EXPERIMENTAL DATA
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LIQUID SCINTILLATION DETECTORS
MEASURING INSTRUMENTS
MEV RANGE
MEV RANGE 10-100
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SPECTRA
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUMERICAL DATA
RADIATION DETECTORS
RADIATION TRANSPORT
SCINTILLATION COUNTERS
SPECTRA
STAINLESS STEELS
STEELS
THEORETICAL DATA
TRANSPORT THEORY