Comparison of measured and calculated neutron and gamma ray energy spectra behind an in-line shielded duct

Journal Article · Wed Dec 01 04:00:00 EST 1982 · J. Fusion Energy; (United States)

DOI:https://doi.org/10.1007/BF01053134· OSTI ID:5497990

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

Integral experiments that measure the transport of about 14 MeV neutrons through a 0.30-mdiameter 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 continous 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 within 5-50% depending on detector location and neutron energy. The calculated and measured gamma ray energy spectra above 750 keV are also in favorable agreement, about 5-50%, depending on detector location and gamma ray energy.

• Research Organization: Oak Ridge National Laboratory, Oak Ridge, Tennessee 37830
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5497990
• Journal Information: J. Fusion Energy; (United States), Journal Name: J. Fusion Energy; (United States) Vol. 2:6; ISSN JFEND
• Country of Publication: United States
• Language: English

Related Subjects

654002 -- Radiation & Shielding Physics-- Shielding Calculations & Experiments-- (-1987)
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALLOYS
CALCULATION METHODS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COMPUTER CODES
CORROSION RESISTANT ALLOYS
DISCRETE ORDINATE METHOD
DUCTS
ELECTRONIC CIRCUITS
ENERGY SPECTRA
GAMMA SPECTRA
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
NEUTRON TRANSPORT THEORY
NICKEL ALLOYS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PHOTON TRANSPORT
POLYETHYLENES
POLYMERS
POLYOLEFINS
PULSE CIRCUITS
PULSE SHAPERS
RADIATION DETECTORS
RADIATION TRANSPORT
SCINTILLATION COUNTERS
SHIELDS
SPECTRA
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
TRANSPORT THEORY