Characterization of Boron Carbide (B4C and Boron Nitride (BN) by Neutron Irradiation and Neutron Radiography
Abstract
Analyze and model the born carbide and boron nitride material response to the thermal and 14 MeV neutrons and provide recommendations to improve the neutron absorption characteristics of the material based on geometry, thickness, composition, etc. Furthermore we will use the well~known code MCNP to model any of the anticipated results with actual experimental data. The TRIGA Mark II reactor will be one of the two sources of neutrons for this study. The neutrons are extracted from the core are well collimated by a neutron waveguide. A mechanical shutter at the entrance of the waveguide will allow the neutron beam to be turned on and off while the reactor is maintained at a constant power.The second neutron source will be 14 MeV neutron generator (MP 320) from Thermo Scientific, to hold samples in place. This sample holder will be utilized for both the thermal neutron and 14 MeV neutron experiments.Neutron radiography will be performed on the various boron samples and pictures will be taken for various image times to ascertain the homogeneity of the boron on a much finer resolution as with a neutron detector. The Nuclear Engineering Teaching Laboratory (NETL) is very well suited to perform experiment on born carbide and boron nitride on various thicknesses and geometries using neutron irradiation and neutron radiography. Homogeneity of neutron shielding material samples will be determined by measuring transmission of a well collimated neutron beam through the sample material at multiple locations on the sample.
Document Details
- Document Type
- DoD Grant Award
- Publication Date
- Aug 08, 2016
- Source ID
- N000141612316
Entities
People
- Sheldon Landsberger
Organizations
- Office of Naval Research
- United States Navy
- University of Texas at Austin