Nondestructive assay technique for /sup 233/U and /sup 235/U in mixed samples [electronic resource].
- Published:
- Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1979.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: 7 : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- Individual fissile isotopes in small samples of mixed /sup 233/U and /sup 235/U can be determined using thermal neutron interrogation with delayed and prompt neutron detection. The technique is rapid (< 10 min.), nondestructive, and can obtain precisions of 1%. (DLC)
- Report Numbers:
- E 1.99:conf-790602-70
conf-790602-70 - Subject(s):
- Other Subject(s):
- Uranium 233
- Radiometric Analysis
- Uranium 235
- Delayed Neutrons
- Fissile Materials
- Neutron Detection
- Nondestructive Analysis
- Prompt Neutrons
- Actinide Isotopes
- Actinide Nuclei
- Alpha Decay Radioisotopes
- Baryons
- Chemical Analysis
- Detection
- Elementary Particles
- Even-Odd Nuclei
- Fermions
- Fission Neutrons
- Fissionable Materials
- Hadrons
- Heavy Nuclei
- Isomeric Transition Isotopes
- Isotopes
- Minutes Living Radioisotopes
- Neutrons
- Nuclei
- Nucleons
- Quantitative Chemical Analysis
- Radiation Detection
- Radioisotopes
- Uranium Isotopes
- Years Living Radioisotopes
- Note:
- Published through SciTech Connect.
01/01/1979.
"conf-790602-70"
ANS annual meeting, Atlanta, GA, USA, 3 Jun 1979.
Allen, E.J.; McNeany, S.R. - Funding Information:
- W-7405-ENG-26
View MARC record | catkey: 14398346