Abstract
Integral experiments that measure the transport of ∼ 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 P3 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 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, ∼ 5–50%, depending on detector location and gamma ray energy.
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R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, G. T. Chapman, and J. S. Tang, Calculated neutron and gamma ray energy spectra from 14 MeV neutrons streaming through an iron duct,Nucl. Sci. Eng. 80:586 (1982).
M. Yamauchi, R. T. Santoro, J. M. Barnes, and R. G. Alsmiller, Jr., Preanalysis of a 14-MeV neutron streaming experiment, ORNL-5866, Oak Ridge National Laboratory (in preparation).
R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., and E. M. Oblow, Calculational Procedures for the analysis of integral experiments for fusion reactor design, ORNL-5777, Oak Ridge National Laboratory (1981).
G. T. Chapman, G. L. Morgan, and J. W. McConnell, The ORNL integral experiments to provide data for evaluating the MFE shielding concepts. Part I: Attenuation measurements, ORNL/TM-7356, Oak Ridge National Laboratory (Aug. 1982).
W. R. Burns and V. V. Verbinski,Nucl. Instrum. Methods 67:181 (1979).
G. T. Chapman, G. L. Morgan, and J. W. McConnell, The use of a small accelerator as a source of 14-MeV neutrons for shielding studies, Proc. Sixth Conf. Applications of Accelerators in Research and Industry, Denton, Texas, Nov. 3–5, 1980.
R. W. Roussin, C. R. Weisbin, J. E. White, N. M. Greene, R. Q. Wright, and J. B. Wright, The CTR processed multigroup cross section library for neutronics studies, ORNL/RSIC-37, Radiation Shielding Information Center, Oak Ridge National Laboratory (1975); also available as DLC-41.
R. A. Lillie, R. G. Alsmiller, Jr., and J. T. Mihalczo,Nucl. Technol. 43:373 (1979).
W. A. Rhoades and F. R. Mynatt, The DOT III two-dimensional discrete ordinates radiation transport code, ORNL/TM-4280, Oak Ridge National Laboratory (1979).
FALSTF, informal notes, CCC-351, Radiation Shielding Information Center, Oak Ridge National Laboratory (1979).
M. B. Emmett, The MORSE Monte Carlo radiation transport code system, ORNL-4972, Oak Ridge National Laboratory (1975).
W. M. Waddell, Jr., PXMORSE, a continuous energy Monte Carlo code, MS thesis, University of Tennessee (1981).
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Santoro, R.T., Alsmiller, R.G., Barnes, J.M. et al. Comparison of measured and calculated neutron and gamma ray energy spectra behind an in-line shielded duct. J Fusion Energ 2, 403–412 (1982). https://doi.org/10.1007/BF01053134
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DOI: https://doi.org/10.1007/BF01053134