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
Resource Information
The item 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 represents a specific, individual, material embodiment of a distinct intellectual or artistic creation found in Internet Archive - Open Library.This item is available to borrow from all library branches.
Resource Information
The item 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 represents a specific, individual, material embodiment of a distinct intellectual or artistic creation found in Internet Archive - Open Library.
This item is available to borrow from all library branches.
- 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
- Language
- eng
- Extent
- 1 online resource (iv, 37 leaves)
- 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
- 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
- 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
- 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
- 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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