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Alterative LEU designs for the FRM-II with power levels of 20-22 MW.

Description: Alternative LEU Designs for the FRM-II have been developed by the RERTR Program at Argonne National Laboratory (ANL) at the request of an FRM-II Expert Group established by the German Federal Government in January 1999 to evaluate the options for using LEU fuel instead of HEU fuel in cores with power levels of 20 MW. The ANL designs would use the same building structure and maintain as many of the HEU design features as practical. The range of potential LEU fuels was expanded from previous stud… more
Date: September 27, 1999
Creator: Hanan, N. A.; Smith, R. S. & Matos, J. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermally induced dispersion mechanisms for aluminum-based plate-type fuels under rapid transient energy deposition

Description: A thermally induced dispersion model was developed to analyze for dispersive potential and determine onset of fuel plate dispersion for Al-based research and test reactor fuels. Effect of rapid energy deposition in a fuel plate was simulated. Several data types for Al-based fuels tested in the Nuclear Safety Research Reactor in Japan and in the Transient Reactor Test in Idaho were reviewed. Analyses of experiments show that onset of fuel dispersion is linked to a sharp rise in predicted strain … more
Date: December 1995
Creator: Georgevich, V.; Taleyarkham, R. P.; Navarro-Valenti, S. & Kim, S. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Production and Characterization of Atomized U-Mo Powder by the Rotating Electrode Process

Description: In order to produce feedstock fuel powder for irradiation testing, the Idaho National Laboratory has produced a rotating electrode type atomizer to fabricate uranium-molybdenum alloy fuel. Operating with the appropriate parameters, this laboratory-scale atomizer produces fuel in the desired size range for the RERTR dispersion experiments. Analysis of the powder shows a homogenous, rapidly solidified microstructure with fine equiaxed grains. This powder has been used to produce irradiation exper… more
Date: September 1, 2007
Creator: Clark, C. R.; Muntifering, B. R. & Jue, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The REBUS-MCNP Linkage.

Description: The Reduced Enrichment Research and Test Reactor (RERTR) Program uses the REBUS-PC computer code to provide reactor physics and core design information such as neutron flux distributions in space, energy, and time, and to track isotopic changes in fuel and neutron absorbers with burnup. REBUS-PC models the complete fuel cycle including shuffling capability. REBUS-PC evolved using the neutronic capabilities of multi-group diffusion theory code DIF3D 9.0, but was extended to apply the continuous … more
Date: April 24, 2009
Creator: Stevens, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RERTR-8 Irradiation Summary Report

Description: The Reduced Enrichment for Research and Test Reactor (RERTR) experiment RERTR-8, was designed to test monolithic mini-fuel plates fabricated via hot isostatic pressing (HIP), the effect of molybdenum (Mo) content on the monolithic fuel behavior, and the efficiency of ternary additions to dispersion fuel particles on the interaction layer behavior at higher burnup. The following report summarizes the life of the RERTR-8 experiment through end of irradiation, including as-run neutronic analysis, … more
Date: December 1, 2011
Creator: Perez, D. M.; Lillo, M. A.; Chang, G. S.; Roth, G. A.; Woolstenhulme, N. E. & Wachs, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Foreign research reactor irradiated nuclear fuel inventories containing HEU and LEU of United States origin

Description: This report provides estimates of foreign research reactor inventories of aluminum-based and TRIGA irradiated nuclear fuel elements containing highly enriched and low enriched uranium of United States origin that are anticipated in January 1996, January 2001, and January 2006. These fuels from 104 research reactors in 41 countries are the same aluminum-based and TRIGA fuels that were eligible for receipt under the Department of Energy`s Offsite Fuels Policy that was in effect in 1988. All fuel … more
Date: December 1, 1994
Creator: Matos, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FY 1995 progress report on the ANS thermal-hydraulic test loop operation and results

Description: The Thermal-Hydraulic Test Loop (THTL) is an experimental facility constructed to support the development of the Advanced Neutron Source Reactor (ANSR) at Oak Ridge National Laboratory (ORNL). The THTL facility was designed and built to provide known thermal-hydraulic (T/H) conditions for a simulated full-length coolant subchannel of the ANS reactor core, thus facilitating experimental determination of FE and CHF thermal limits under expected ANSR T/H conditions. Special consideration was given… more
Date: July 1, 1997
Creator: Siman-Tov, M.; Felde, D. K.; Farquharson, G.; McDuffee, J. L.; McFee, M. T.; Ruggles, A. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Upgrades to the WIMS-ANL code.

Description: The dusty old source code in WIMS-D4M has been completely rewritten to conform more closely with current FORTRAN coding practices. The revised code contains many improvements in appearance, error checking and in control of the output. The output is now tabulated to fit the typical 80 column window or terminal screen. The Segev method for resonance integral interpolation is now an option. Most of the dimension limitations have been removed and replaced with variable dimensions within a compile-t… more
Date: October 14, 1998
Creator: Woodruff, W. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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