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Title: In-line assay monitor for uranium hexafluoride

Abstract

An in-line assay monitor for determining the content of uranium-235 in a uranium hexafluoride gas isotopic separation system is provided which removes the necessity of complete access to the operating parameters of the system for determining the uranium-235 content. The monitor is intended for uses such as safeguard applications to assure that weapons grade uranium is not being produced in an enrichment cascade. The method and monitor for carrying out the method involve cooling of a radiation pervious chamber connected in fluid communication with the selected point in the system to withdraw a specimen and solidify the specimen in the chamber. The specimen is irradiated by means of an ionizing radiation source of energy different from that of the 185 keV gamma emissions from the uranium-235 present in the specimen. Simultaneously, the gamma emissions from the uranium-235 of the specimen and the source emissions transmitted through the sample are counted and stored in a multiple channel analyzer. The uranium-235 content of the specimen is determined from the comparison of the accumulated 185 keV energy counts and the reference energy counts. The latter is used to measure the total uranium isotopic content of the specimen. The process eliminates the necessity ofmore » knowing the system operating conditions and yet obtains the necessary data without need for large scintillation crystals and sophisticated mechanical designs.« less

Inventors:
 [1]
  1. (Knoxville, TN)
Issue Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
OSTI Identifier:
863934
Patent Number(s):
4278886
Assignee:
United States of America as represented by United States (Washington, DC) ORNL
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
in-line; assay; monitor; uranium; hexafluoride; determining; content; uranium-235; gas; isotopic; separation; provided; removes; necessity; complete; access; operating; parameters; intended; safeguard; applications; assure; weapons; grade; produced; enrichment; cascade; method; carrying; involve; cooling; radiation; pervious; chamber; connected; fluid; communication; selected; withdraw; specimen; solidify; irradiated; means; ionizing; source; energy; 185; kev; gamma; emissions; simultaneously; transmitted; sample; counted; stored; multiple; channel; analyzer; determined; comparison; accumulated; counts; reference; latter; measure; total; process; eliminates; knowing; conditions; obtains; data; scintillation; crystals; sophisticated; mechanical; designs; scintillation crystals; multiple channel; operating conditions; fluid communication; radiation source; ionizing radiation; operating condition; uranium hexafluoride; operating parameters; mechanical design; isotopic separation; scintillation crystal; chamber connected; kev energy; channel analyzer; method involve; gas isotopic; hexafluoride gas; in-line assay; operating parameter; assay monitor; kev gamma; /250/

Citation Formats

Wallace, Steven A. In-line assay monitor for uranium hexafluoride. United States: N. p., 1981. Web.
Wallace, Steven A. In-line assay monitor for uranium hexafluoride. United States.
Wallace, Steven A. Thu . "In-line assay monitor for uranium hexafluoride". United States. https://www.osti.gov/servlets/purl/863934.
@article{osti_863934,
title = {In-line assay monitor for uranium hexafluoride},
author = {Wallace, Steven A.},
abstractNote = {An in-line assay monitor for determining the content of uranium-235 in a uranium hexafluoride gas isotopic separation system is provided which removes the necessity of complete access to the operating parameters of the system for determining the uranium-235 content. The monitor is intended for uses such as safeguard applications to assure that weapons grade uranium is not being produced in an enrichment cascade. The method and monitor for carrying out the method involve cooling of a radiation pervious chamber connected in fluid communication with the selected point in the system to withdraw a specimen and solidify the specimen in the chamber. The specimen is irradiated by means of an ionizing radiation source of energy different from that of the 185 keV gamma emissions from the uranium-235 present in the specimen. Simultaneously, the gamma emissions from the uranium-235 of the specimen and the source emissions transmitted through the sample are counted and stored in a multiple channel analyzer. The uranium-235 content of the specimen is determined from the comparison of the accumulated 185 keV energy counts and the reference energy counts. The latter is used to measure the total uranium isotopic content of the specimen. The process eliminates the necessity of knowing the system operating conditions and yet obtains the necessary data without need for large scintillation crystals and sophisticated mechanical designs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1981},
month = {1}
}

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