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1
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85162297511
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N.M. Larson, "Updated Users' Guide for SAMMY: Multilevel R-Matrix Fits to Neutron Data Using Bayes' Equations," Report ORNL/TM-9179/R7, 2007
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N.M. Larson, "Updated Users' Guide for SAMMY: Multilevel R-Matrix Fits to Neutron Data Using Bayes' Equations," Report ORNL/TM-9179/R7, 2007
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2
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85162296929
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232Th Neutron Resonance Parameters in the Energy Range 0 to 4000 keV," B071.pdf in Proc. of PHYSOR-2006, ANS Topical Meeting on Reactor Physics, Vancouver, Canada, Sep. 2006
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232Th Neutron Resonance Parameters in the Energy Range 0 to 4000 keV," B071.pdf in Proc. of PHYSOR-2006, ANS Topical Meeting on Reactor Physics, Vancouver, Canada, Sep. 2006
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3
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85162288051
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"SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations," NUREG/CR-0200, Rev. 7 (ORNL/NUREG/CSD-2/R7), Vols. I, II, and III, May 2004. Available from the Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725
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"SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations," NUREG/CR-0200, Rev. 7 (ORNL/NUREG/CSD-2/R7), Vols. I, II, and III, May 2004. Available from the Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725
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4
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85162299903
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D. Wiarda and M.E. Dunn, "PUFF-IV: A Code for Processing ENDF Uncertainty Data into Multigroup Covariance Matrices," Report ORNL/TM-2006/147, Oct. 2006
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D. Wiarda and M.E. Dunn, "PUFF-IV: A Code for Processing ENDF Uncertainty Data into Multigroup Covariance Matrices," Report ORNL/TM-2006/147, Oct. 2006
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5
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85162288945
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233U in the Neutron Energy Range from Thermal to 600 eV", Report ORNL/TM-2000/372 and ENDF-365, March 2001
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233U in the Neutron Energy Range from Thermal to 600 eV", Report ORNL/TM-2000/372 and ENDF-365, March 2001
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6
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57049147742
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Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV
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Wiarda D., Arbanas G., Leal L., and Dunn M.E. Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV. Nuclear Data Sheets 109 (2008) 2791
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(2008)
Nuclear Data Sheets
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, pp. 2791
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Wiarda, D.1
Arbanas, G.2
Leal, L.3
Dunn, M.E.4
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7
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85162279684
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235U Neutron Transmission and Cross Sections in the Energy Range 0 to 2.25 keV," Report ORNL/TM-13516, Oak Ridge National Laboratory, Nov. 1997
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235U Neutron Transmission and Cross Sections in the Energy Range 0 to 2.25 keV," Report ORNL/TM-13516, Oak Ridge National Laboratory, Nov. 1997
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8
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85162298650
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235U in the Resolved-Resonance Region", in Proc. PHYSOR 2006, paper C015, ANS Topical Meeting on Reactor Physics, Vancouver, Canada, Sep. 2006
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235U in the Resolved-Resonance Region", in Proc. PHYSOR 2006, paper C015, ANS Topical Meeting on Reactor Physics, Vancouver, Canada, Sep. 2006
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11
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85162295929
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239Pu in the High Energy Range," in Proc. 2007 Nuclear Data Conference, Nice, France
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239Pu in the High Energy Range," in Proc. 2007 Nuclear Data Conference, Nice, France
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12
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85162277361
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238U and Calculated Cross Sections from the Reich-Moore Analysis of Experimental Data in the Neutron Energy Range from 0 keV to 20 keV," Report ORNL/TM-2005/241, Nov. 2005
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238U and Calculated Cross Sections from the Reich-Moore Analysis of Experimental Data in the Neutron Energy Range from 0 keV to 20 keV," Report ORNL/TM-2005/241, Nov. 2005
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13
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85162279580
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Go Chiba, "ERRORJ - A Code to Process Neutron-Nuclide Reaction Cross Section Covariance," Version 2.3, JAEA-Data/Code 2007-007, January 2007
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Go Chiba, "ERRORJ - A Code to Process Neutron-Nuclide Reaction Cross Section Covariance," Version 2.3, JAEA-Data/Code 2007-007, January 2007
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14
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85162296686
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239Pu," to be published as ORNL report
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239Pu," to be published as ORNL report
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15
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85162289973
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eff values for fast and thermal benchmark with covariance data," Inter. Conf. on Physics of Reactors, PHYSOR 2008, Interlaken, Switzerland, Sep. 2008
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eff values for fast and thermal benchmark with covariance data," Inter. Conf. on Physics of Reactors, PHYSOR 2008, Interlaken, Switzerland, Sep. 2008
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