Material Compositions and Number Densities for Neutronics Calculations | Zendy

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Material Compositions and Number Densities for Neutronics Calculations

Author(s) -

D. Thomas

Publication year - 1996

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/891531

Subject(s) - neutron transport , criticality , radiation shielding , electromagnetic shielding , radiation transport , nuclear engineering , computer science , radiation , materials science , neutron , nuclear physics , engineering , physics , monte carlo method , statistics , mathematics , composite material

The purpose of this analysis is to calculate the number densities and isotopic weight percentages of the standard materials to be used in the neutronics (criticality and radiation shielding) evaluations by the Waste Package Development Department. The objective of this analysis is to provide material number density information which can be referenced by future neutronics design analyses, such as for those supporting the Conceptual Design Report

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