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Annual Report of the International Nuclear Energy Research Initiative Osmose Project (FY06).

Description: The goal of the OSMOSE program is to measure the reactivity effect of minor actinides in known neutron spectra of interest to the Generation-IV reactor program and other programs and to create a database of these results for use as an international benchmark for the minor actinides. The results are then compared to calculation models to verify and validate integral absorption cross-sections for the minor actinides. The OSMOSE program includes all aspects of the experimental program--including t… more
Date: August 29, 2007
Creator: Klann, R. T.; Hudelot, J. P.; Drin, N.; Zhong, Z.; Division, Nuclear Engineering & Atomique, Commissariat a l'Energie
Item Type: Refine your search to only Report
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: January 1, 1993
Creator: Klann, R. T. & Picker, B. A., (Jr.)
Item Type: Refine your search to only Article
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.)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Reactivity-Worth Estimates of the Osmose Samples in the Minerve Reactor r1-uo2 Configuration.

Description: An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R1-UO2 core configuration were completed. The reactor model was generated using the REBUS code developed at Argonne National Laboratory. The calculations are based on the specifications for fabrication, so they are considered preliminary until sampling and analysis have been completed on the fabricated samples. The estimates indicate a range of reactivity effect from -22 pcm to +25 pc… more
Date: October 3, 2007
Creator: Klann, R. T. & Perret, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

OSMOSE an Experimental Program for Improving Neutronic Predictions of Advanced Nuclear Fuels.

Description: This report describes the technical results of tasks and activities conducted in FY07 to support the DOE-CEA collaboration on the OSMOSE program. The activities are divided into five high-level tasks: reactor modeling and pre-experiment analysis, sample fabrication and analysis, reactor experiments, data treatment and analysis, and assessment for relevance to high priority advanced reactor programs (such as GNEP and Gen-IV).
Date: October 18, 2007
Creator: Klann, R. T.; Aliberti, G.; Zhong, Z.; Graczyk, D.; Loussi, A.; Division, Nuclear Engineering et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactivity-Worth Estimates of the OSMOSE Samples in the MINERVE Reactor R1-MOX, R2-UO2 and MORGANE/R Configurations.

Description: An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R2-UO2 and MORGANE/R core configuration were completed. The calculation model was generated using the lattice physics code DRAGON. In addition, an initial comparison of calculated values to experimental measurements was performed based on preliminary results for the R1-MOX configuration.
Date: August 3, 2007
Creator: Zhong, Z. & Klann, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Coated Gallium Arsenide Neutron Detectors : Results of Characterization Measurements.

Description: Effective detection of special nuclear materials (SNM) is essential for reducing the threat associated with stolen or improvised nuclear devices. Passive radiation detection technologies are primarily based on gamma-ray detection and subsequent isotope identification or neutron detection (specific to neutron sources and SNM). One major effort supported by the Department of Homeland Security in the area of advanced passive detection is handheld or portable neutron detectors for search and locali… more
Date: September 29, 2006
Creator: Klann, R. T.; Perret, G. & Sanders, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final Report of the International Nuclear Energy Research Initiative Osmose Project (fy01-fy04).

Description: The need for better nuclear data has been stressed by various organizations throughout the world, and results of studies have been published which demonstrate that current data are inadequate for designing the projects under consideration [1] [2]. In particular, a Working Party of the OECD has been concerned with identifying these needs [3] and has produced a detailed High Priority Request List for Nuclear Data. The French Atomic Energy Commissariat (CEA) has also recognized the need for better… more
Date: February 25, 2005
Creator: Klann, R. T.; Perret, G.; Hudelot, J. P.; Drin, N.; Lee, J. & Cao, Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gamma-ray Sptectrometric Characterization of Overpacked CC 104/107 RH-TRU Wastes: Surrogate Tests

Description: Development of the gamma-ray spectrometric technique termed GSAK (Gamma-Ray Spectrometry with Acceptable Knowledge) for the characterization of CC104/107 remote-handled transuranic (RH-TRU) wastes continued this year. Proof-of-principle measurements have been completed on the surrogate RH-TRU waste drums configured earlier this year. The GSAK technique uses conventional gamma-ray spectrometry to quantify the detectable fission product content of overpacked RH-TRU drums. These results are then c… more
Date: April 1, 2000
Creator: Hartwell, John Kelvin; Mc Ilwain, Michael Edward & Klann, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Annual Report of the International Nuclear Research Initiative Osmose Project (FY05).

Description: The goal of the OSMOSE program is to measure the reactivity effect of minor actinides in known neutron spectra of interest to the Generation-IV reactor program and other programs and to create a database of these results for use as an international benchmark for the minor actinides. The results are then compared to calculational models to verify and validate integral absorption cross-sections for the minor actinides. The OSMOSE program includes all aspects of the experimental program -- includi… more
Date: October 3, 2007
Creator: Klann, R. T.; Hudelot, J. P.; Perret, G.; Drin, N.; Division, Nuclear Engineering & Atomique, Commissariat a l'Energie
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Article
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.
Item Type: Refine your search to only Article
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.
Item Type: Refine your search to only Article
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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Gamma-Ray Spectrometric Characterization of Overpacked CC104/107 RH-TRU Wastes: Surrogate Tests

Description: Development of the gamma-ray spectrometric technique termed GSAK (Gamma-Ray Spectrometry with Acceptable Knowledge) for the characterization of CC104/107 remote-handled transuranic (RH-TRU) wastes continued this year. Proof-of-principle measurements have been completed on the surrogate RH-TRU waste drums configured earlier this year. The GSAK technique uses conventional gamma-ray spectrometry to quantify the detectable fission product content of overpacked RH-TRU drums. These results are then c… more
Date: May 1, 2000
Creator: Hartwell, J. K.; Klann, R. T. & McIlwain, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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