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Title: Lightweight concrete with enhanced neutron shielding

Abstract

A lightweight concrete containing polyethylene terephthalate in an amount of 20% by total volume. The concrete is enriched with hydrogen and is therefore highly effective at thermalizing neutrons. The concrete can be used independently or as a component of an advanced neutron radiation shielding system.

Inventors:
;
Publication Date:
Research Org.:
Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1324964
Patent Number(s):
9,440,882
Application Number:
13/068,619
Assignee:
JEFFERSON SCIENCE ASSOCIATES, LLC (Newport News, VA) TJNAF
DOE Contract Number:
AC05-84ER40150
Resource Type:
Patent
Resource Relation:
Patent File Date: 2011 May 16
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE

Citation Formats

Brindza, Paul Daniel, and Metzger, Bert Clayton. Lightweight concrete with enhanced neutron shielding. United States: N. p., 2016. Web.
Brindza, Paul Daniel, & Metzger, Bert Clayton. Lightweight concrete with enhanced neutron shielding. United States.
Brindza, Paul Daniel, and Metzger, Bert Clayton. 2016. "Lightweight concrete with enhanced neutron shielding". United States. doi:. https://www.osti.gov/servlets/purl/1324964.
@article{osti_1324964,
title = {Lightweight concrete with enhanced neutron shielding},
author = {Brindza, Paul Daniel and Metzger, Bert Clayton},
abstractNote = {A lightweight concrete containing polyethylene terephthalate in an amount of 20% by total volume. The concrete is enriched with hydrogen and is therefore highly effective at thermalizing neutrons. The concrete can be used independently or as a component of an advanced neutron radiation shielding system.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2016,
month = 9
}

Patent:

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  • A device is described for conducting neutron radiography comprising: an on/off sealed tube neutron generator using solely a deuterium target for emitting relatively low energy neutrons having an energy level of approximately 3 MeV and an unthermalized neutron yield of at least approximately 1x10/sup 10/D-D n/second, a maneuverable inspection head supporting the neutron generator and having moderating fluid therein to thermalize the neutrons emitted from the neutron source, and collimator means for directing the thermalized neutrons to an imaging plane to produce a thermal neutron radiograph.
  • A neutron detector is disclosed which uses the moderating material as the structural support for the neutron detector element. A thin metal liner is affixed to the inside of the plastic moderating material encasement for containing a neutron detecting gas. A high voltage supply is connected to an electrical conductor which extends between the ends of the encasement and serves to furnish output pulses to a pulse counter upon the occurrence of ionization of the counting gas in response to neutron flux through the volume of the detector.
  • A neutron detector is disclosed which uses the moderating material as the structural support for the neutron detector element. A thin metal liner is affixed to the inside of the plastic moderating material encasement for containing a neutron detecting gas. A high voltage supply is connected to an electrical conductor which extends between the ends of the encasement and serves to furnish output pulses to a pulse counter upon the occurrence of ionization of the counting gas in response to neutron flux through the volume of the detector.