The Resource An investigation of the feasibility of a method for measuring thermal neutron absorption cross sections using the AGN-201 reactor, George J. Jenkins, Jr. and Herbert B. Richter

An investigation of the feasibility of a method for measuring thermal neutron absorption cross sections using the AGN-201 reactor, George J. Jenkins, Jr. and Herbert B. Richter

Label
An investigation of the feasibility of a method for measuring thermal neutron absorption cross sections using the AGN-201 reactor
Title
An investigation of the feasibility of a method for measuring thermal neutron absorption cross sections using the AGN-201 reactor
Statement of responsibility
George J. Jenkins, Jr. and Herbert B. Richter
Creator
Contributor
Subject
Language
eng
Summary
The feasibility of measuring thermal neutron absorption cross section from the results of first-order reactor perturbation theory was investigated. Techniques were developed for this measurement utilizing the AGN-201 reactor of the U. S. Naval Postgraduate School. These techniques were evaluated by measurement of the thermal absorption cross section of indium using gold-197 as a standard. The result obtained was 194.4 plus or minus 2.3 barns. A comparison with the most recently published value of this cross section, 196 plus or minus 5 barns, demonstrates the feasibility of the method for obtaining improved precision for the measurement of the cross sections of selected materials. (Author)J
Additional physical form
Also available in print.
Cataloging source
AD#
http://library.link/vocab/creatorName
Jenkins, George J
Dissertation note
Thesis (M.S. in Physics)--Naval Postgraduate School, January 1965.
Government publication
federal national government publication
Illustrations
illustrations
Index
no index present
Literary form
non fiction
Nature of contents
  • dictionaries
  • bibliography
  • theses
http://library.link/vocab/relatedWorkOrContributorName
  • Richter, Herbert B
  • Naval Postgraduate School (U.S.)
http://library.link/vocab/subjectName
  • Neutron cross sections
  • Thermal neutrons
  • Perturbation (Mathematics)
  • Neutrons
  • Fast neutrons
  • Gold
  • Radioisotopes
  • Measurement
  • Indium
  • Errors
  • Materials
  • Neutron flux
  • Mathematical analysis
  • Cadmium
Label
An investigation of the feasibility of a method for measuring thermal neutron absorption cross sections using the AGN-201 reactor, George J. Jenkins, Jr. and Herbert B. Richter
Link
Instantiates
Publication
Note
  • Thesis Advisor(s): Handle, Harry E
  • "January 1965."
  • Description based on title screen as viewed on June 2, 2010
  • DTIC Descriptor(s): (Neutron Cross Sections, Thermal Neutrons), (Research Reactors, Reactor Feasibility Studies), Fast Neutrons, Gold, Radioactive Isotopes, Measurement, Perturbation Theory, Neutron Capture, Indium, Standards, Errors, Materials, Neutron Flux, Mathematical Analysis, Cadmium, Reactor Shielding Materials, Computer Programming, Foils (Materials), Reactor Control, Reactor Kinetics, Reactor Start Up Sources
  • DTIC Identifier(s): AGN-201 Reactors
Bibliography note
Includes bibliographical references (p. 32)
Color
black and white
Extent
1 online resource (iv, 37 leaves)
File format
one file format
Form of item
online
Governing access note
"Approved for public release, distribution unlimited"--Cover
Note
US Navy (USN) authors.
Specific material designation
remote
System details
  • Mode of access: World Wide Web
  • System requirements: Adobe Acrobat Reader
Label
An investigation of the feasibility of a method for measuring thermal neutron absorption cross sections using the AGN-201 reactor, George J. Jenkins, Jr. and Herbert B. Richter
Link
Publication
Note
  • Thesis Advisor(s): Handle, Harry E
  • "January 1965."
  • Description based on title screen as viewed on June 2, 2010
  • DTIC Descriptor(s): (Neutron Cross Sections, Thermal Neutrons), (Research Reactors, Reactor Feasibility Studies), Fast Neutrons, Gold, Radioactive Isotopes, Measurement, Perturbation Theory, Neutron Capture, Indium, Standards, Errors, Materials, Neutron Flux, Mathematical Analysis, Cadmium, Reactor Shielding Materials, Computer Programming, Foils (Materials), Reactor Control, Reactor Kinetics, Reactor Start Up Sources
  • DTIC Identifier(s): AGN-201 Reactors
Bibliography note
Includes bibliographical references (p. 32)
Color
black and white
Extent
1 online resource (iv, 37 leaves)
File format
one file format
Form of item
online
Governing access note
"Approved for public release, distribution unlimited"--Cover
Note
US Navy (USN) authors.
Specific material designation
remote
System details
  • Mode of access: World Wide Web
  • System requirements: Adobe Acrobat Reader

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