Development of a Methodology for Analysis of the Fe-56 ENDF-B/VI Cross Sections with a Time-of-Flight Experiment

Journal Article · Tue May 24 00:00:00 EDT 2005 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.1945058· OSTI ID:20722608

Wenner, Michael T; Haghighat, Alireza ^[1]; Adams, James M; Carlson, Allan D ^[2]; Grimes, Steven M; Massey, Thomas N ^[3]

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1. Department of Nuclear and Radiological Engineering, University of Florida, Gainesville, FL 32611 (United States)
2. National Institute of Standards and Technology, Gaithersburg, MD 20899 (United States)
3. Department of Physics and Astronomy, Ohio University, Athens, OH 45701 (United States)

This paper discusses a methodology developed for analysis of a time-of-flight (TOF) experiment performed for examination of iron cross sections. The methodology combines measurements from several experimental setups and Monte Carlo simulations. Neutron TOF spectra are obtained via the spherical shell transmission method with iron shells of two thicknesses and using both 15N(p,n) and D(d,n) neutron source interactions at various beam angles. Experimental data were used to determine a source distribution for Monte Carlo Simulations. Comparison of experiments and calculations identified discrepancies over several energy ranges that may be attributed to inaccuracies in the Fe-56 inelastic scattering cross-section. To further investigate this issue, the Fe-56 scattering cross sections were adjusted, and used in the Monte Carlo simulations. The results of these simulations demonstrate that the adjusted cross-sections result in significant reductions (as large as {approx}40%) in the discrepancies between experimental and calculated spectra The adjusted cross-sections were collapsed into a multigroup form and applied to a 1-D Pressure Vessel fluence calculation, which resulted in noticeable effects. Further studies are warranted.

• OSTI ID: 20722608
• Journal Information: AIP Conference Proceedings, Vol. 769, Issue 1; Conference: International conference on nuclear data for science and technology, Santa Fe, NM (United States), 26 Sep - 1 Oct 2004; Other Information: DOI: 10.1063/1.1945058; (c) 2005 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CROSS SECTIONS
DEUTERONS
INELASTIC SCATTERING
IRON
IRON 56
MONTE CARLO METHOD
NEUTRON REACTIONS
NEUTRON SOURCES
NEUTRON SPECTROSCOPY
NEUTRON TRANSPORT THEORY
NEUTRONS
NITROGEN 15
NUCLEAR DATA COLLECTIONS
PRESSURE VESSELS
PROTON-NUCLEON INTERACTIONS
SPHERICAL CONFIGURATION
TIME-OF-FLIGHT METHOD