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A Conceptual Redesign of an Inter-Building Fuel Transfer Cask

Description: The Inter-Building Fuel Transfer Cask, referred to as the IBC, is a lead shielded cask for transporting subassemblies between buildings on the Argonne National Laboratory-West site near Idaho Falls, Idaho. The cask transports both newly fabricated and spent reactor subassemblies between the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF) and the Hot Fuel Examination Facility (HFEF). The IBC will play a key role in the Integral Fast Reactor (IFR) fuel recycling demonstrat… more
Date: January 1, 1993
Creator: Klann, R. T. & Picker, B. A., (Jr.)
Partner: UNT Libraries Government Documents Department
open access

A Conceptual Redesign of an Inter-Building Fuel Transfer Cask

Description: The Inter-Building Fuel Transfer Cask, referred to as the IBC, is a lead shielded cask for transporting subassemblies between buildings on the Argonne National Laboratory-West site near Idaho Falls, Idaho. The cask transports both newly fabricated and spent reactor subassemblies between the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF) and the Hot Fuel Examination Facility (HFEF). The IBC will play a key role in the Integral Fast Reactor (IFR) fuel recycling demonstrat… more
Date: March 1, 1993
Creator: Klann, R. T. & Picker, B. A., (Jr.)
Partner: UNT Libraries Government Documents Department
open access

Depletion calculations for the McClellan Nuclear Radiation Center.

Description: Depletion calculations have been performed for the McClellan reactor history from January 1990 through August 1996. A database has been generated for continuing use by operations personnel which contains the isotopic inventory for all fuel elements and fuel-followed control rods maintained at McClellan. The calculations are based on the three-dimensional diffusion theory code REBUS-3 which is available through the Radiation Safety Information Computational Center (RSICC). Burnup-dependent cross… more
Date: December 8, 1997
Creator: Klann, R. T. & Newell, D. L.
Partner: UNT Libraries Government Documents Department
open access

A system for fast neutron radiography

Description: A system has been designed and a neutron generator installed to perform fast neutron radiography. With this system, objects as small as a coin and as large as a 19 liter container have been radiographed. The neutron source is an MF Physics A-711 neutron generator which produces 3 x 10[sup 10] neutrons/second with an average energy of 14. 5 MeV. The radiography system uses x-ray scintillation screens and film in commercially available light-tight cassettes. The cassettes have been modified to in… more
Date: April 1, 1997
Creator: Klann, R.T.
Partner: UNT Libraries Government Documents Department
open access

Fast neutron (14.5 MeV) radiography: a comparative study

Description: Fast neutron (14.5 MeV) radiography is a type of non-destructive analysis tool that offers its own benefits and drawbacks. Because cross-sections vary with energy, a different range of materials can be examined with fast neutrons than can be studied with thermal neutrons, epithermal neutrons, or x-rays. This paper details these differences through a comparative study of fast neutron radiography to the other types of radiography available. The most obvious difference among the different types of… more
Date: July 1, 1996
Creator: Klann, R.T.
Partner: UNT Libraries Government Documents Department
open access

A system for fast neutron radiography

Description: A system has been designed and a neutron generator installed to perform fast neutron radiography. With this sytem, objects as small as a coin or as large as a waste drum can be radiographed. The neutron source is an MF Physics A-711 neutron generator which produces 3x10{sup 10} neutrons/second with an average energy of 14.5 MeV. The radiography system uses x-ray scintillation screens and film in commercially available cassettes. The cassettes have been modified to include a thin sheet of plasti… more
Date: May 1, 1996
Creator: Klann, R.T.
Partner: UNT Libraries Government Documents Department
open access

Development of reference materials for SNF NDA systems

Description: The Department of Energy has over 200 different fuel types which will be placed in a geologic repository for ultimate disposal. At the present time, DOE EM is responsible for assuring safe existing conditions, achieving interim storage, and preparing for final disposition. Each task is governed by regulations which dictate a certain degree of knowledge regarding the contents and condition of the fuel. This knowledge and other associated characteristics are referred to as data needs. It is the s… more
Date: February 29, 2000
Creator: Klann, R. T.
Partner: UNT Libraries Government Documents Department
open access

Criticality safety issues in the disposition of BN-350 spent fuel

Description: A criticality safety analysis has been performed as part of the BN-350 spent fuel disposition project being conducted jointly by the DOE and Kazakhstan. The Kazakhstan regulations are reasonably consistent with those of the DOE. The high enrichment and severe undermoderation of this fast reactor fuel has significant criticality safety consequences. A detailed modeling approach was used that showed some configurations to be safe that otherwise would be rejected. Reasonable requirements for desig… more
Date: February 28, 2000
Creator: Schaefer, R. W.; Klann, R. T.; Koltyshev, S. M. & Krechetov, S.
Partner: UNT Libraries Government Documents Department
open access

Determining Pu-239 content by resonance transmission analysis using a filtered reactor beam.

Description: A novel technique has been developed at Argonne National Laboratory to determine the {sup 239}Pu content in EBR-II blanket elements using resonance transmission analysis (RTA) with a filtered reactor beam. The technique uses cadmium and gadolinium filters along with a {sup 239}Pu fission chamber to isolate the 0.3 eV resonance in {sup 239}Pu. In the energy range from 0.1 to 0.5 eV, the total microscopic cross-section of {sup 239}Pu is significantly larger than the cross-sections of {sup 238}U a… more
Date: November 25, 1998
Creator: Klann, R. T.
Partner: UNT Libraries Government Documents Department
open access

Fast neutron radiography research at ANL-W

Description: Thirty-seven different elements were tested for their suitability as converter screens for direct and indirect fast neutron radiography. The use of commercial X-ray scintillator screens containing YTaO{sub 4}, LaOBr:Tm, YTaO{sub 4}:Nb, YTaO{sub 4}:Tm, CaWO{sub 4}, BaSO{sub 4}:Sr, and GdO{sub 2}S:Tb was also explored for direct fast neutron radiography. For the indirect radiographic process, only one element, holmium, was found to be better than copper. Iron was also found to work as well as cop… more
Date: June 1, 1996
Creator: Klann, R.T. & Natale, M.D.
Partner: UNT Libraries Government Documents Department
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