Using New Fission Data with the Multi-detector Analysis System for Spent Nuclear Fuel

Conference · Sun Nov 01 00:00:00 EST 1998

OSTI ID:8936

Ramayya, A V; Daniel, A V ^[1]; Beyer, C J ^[2]; Reber, E L; Ter-Akopian, G M; Popeko, G S; Cole, J D; Hamilton, J H; Jewell, J K ^[3]; Drigert, M W; Aryaeinejad, R; Oganessian, Ts Yu

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1. Joint Institute for Nuclear Research
2. Vanderbilt Univ.
3. INEEL

New experiments using an array of high purity germanium detectors and fast liquid scintillation detectors has been performed to observe the radiation emitted from the induced fission of ²³⁵U with a beam of thermal neutrons. The experiment was performed at the Argonne National Laboratory Intense Pulsed Neutron Source. Preliminary observations of the data are presented. A nondestructive analysis system for the characterization of DOE spent nuclear fuel based on these new data is presented.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Environmental Management (EM)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 8936
• Report Number(s): INEEL/CON-98-01126; ON: DE00008936
• Resource Relation: Conference: Perspectives in Nuclear Physics, Paradise Island, Bahamas, 11/13/99 - 11/17/99
• Country of Publication: United States
• Language: English

Related Subjects

07 ISOTOPE AND RADIATION SOURCE TECHNOLOGY
44 INSTRUMENTATION
INCLUDING NUCLEAR AND PARTICLE DETECTORS
66 PHYSICS
Gamma Spectra
Energy Resolution
Spectroscopy
High-Purity GE Detectors
Liquid Scintillation Detectors
Spent Fuels
Uranium 235
Thermal Fission