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Systematic methodology for the reduction of uncertainties in transient thermal-hydraulics by using in-bundle measurement data

Description: The development of a systematic methodology for the reduction of uncertainties in transient thermal-hydraulics by using in-bundle measurement data is presented. The adjustment of the system parameters and responses and the reduction in their respective uncertainties is treated as a time-dependent constrained minimization problem. An on-line (i.e., real time) large scale optimization scheme is also outlined. Although formulated within the framework of reactor safety analysis, the proposed method… more
Date: January 1, 1980
Creator: Barhen, J.; Cacuci, D. G.; Wagschal, J. J. & Mullins, C. B.
Partner: UNT Libraries Government Documents Department
open access

VITAMIN E: a multipurpose ENDF/B-V coupled neutron-gamma cross section library

Description: The US Department of Energy Office of Fusion Energy and the Division of Reactor Research and Technology jointly sponsored the development of a coupled fine-group cross section library (VITAMIN-C). The experience gained in the generation, validation, and utilization of the VITAMIN-C library along with its broad range of applicability has led to the request for updating this data set using ENDF/B-V. Additional support in this regard has been provided by the Defense Nuclear Agency (DNA) and by EPR… more
Date: January 1, 1979
Creator: Barhen, J.; Cacuci, D. G.; Ford, W. E., III; Roussin, R. W.; Wagschal, J. J.; Weisbin, C. R. et al.
Partner: UNT Libraries Government Documents Department
open access

VITAMIN-E: an ENDF/B-V multigroup cross-section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology

Description: The Department of Energy (DOE) Office of Fusion Energy (OFE) and the Division of Reactor Research and Technology (DRRT) jointly sponsored the development of a coupled fine-group cross section library. This 171-neutron, 36-gamma-ray group library was based upon ENDF/B-IV and was intended to be applicable to fusion reactor neutronics and LMFBR core and shield analysis. Versions of the library are available from the Radiation Shielding Information Center (RSIC) at the Oak Ridge National Laborary i… more
Date: February 1, 1979
Creator: Weisbin, C. R.; Roussin, R. W.; Wagschal, J. J.; White, J. E. & Wright, R. Q.
Partner: UNT Libraries Government Documents Department
open access

ORACLE: an adjusted cross-section and covariance library for fast-reactor analysis

Description: Benchmark integral-experiment values from six fast critical-reactor assemblies and two standard neutron fields are combined with corresponding calculations using group cross sections based on ENDF/B-V in a least-squares data adjustment using evaluated covariances from ENDF/B-V and supporting covariance evaluations. Purpose is to produce an adjusted cross-section and covariance library which is based on well-documented data and methods and which is suitable for fast-reactor design. By use of suc… more
Date: January 1, 1980
Creator: Yeivin, Y.; Marable, J. H.; Weisbin, C. R. & Wagschal, J. J.
Partner: UNT Libraries Government Documents Department
open access

ZPR-3 Assembly 12 : A Cylindrical Assembly of Highly Enriched Uranium, Depleted Uranium and Graphite With an Average {Sup 235}U Enrichment of 21 Atom %.

Description: Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR crit… more
Date: September 30, 2010
Creator: Lell, R. M.; McKnight, R. D.; Perel, R. L.; Wagschal, J. J.; Division, Nuclear Engineering & Physics, Racah Inst. of
Partner: UNT Libraries Government Documents Department
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