Open Access
Issue |
EPJ Web Conf.
Volume 146, 2017
ND 2016: International Conference on Nuclear Data for Science and Technology
|
|
---|---|---|
Article Number | 02021 | |
Number of page(s) | 5 | |
Section | Evaluation | |
DOI | https://doi.org/10.1051/epjconf/201714602021 | |
Published online | 13 September 2017 |
- G. de Saussure, L.C. Leal, R. Perez, N.M. Larson, and M.S. Moore, Nucl. Sci. Eng. 103, 109 (1989) [CrossRef] [Google Scholar]
- N.M. Larson, Updated Users' Guide for SAMMY: Multi-level R-Matrix Fits to Neutron Data Using Bayes's Equations, ENDF-364/R2, Oak Ridge National Laboratory USA (2008). Available at Radiation Safety Information Computational Center (RSICC) as PSR-158 [Google Scholar]
- Stéphane Cathalau, Amal Benslimane, Abdelmajid Maghnouj, and Philippe Fougeras, ”Qualification of the JEFF2.2 Cross Sections in the Epithermal and Thermal Energy Ranges Using a Statistical Approach,” Nucl. Sci. Eng. 121, 326 (1995) [CrossRef] [Google Scholar]
- L.C. Leal, H. Derrien, N.M. Larson, and R.Q. Wright, “R-Matrix Analysis of 235U Neutron Transmission and Cross-Section Measurements in the 0- to 2.25-keV Energy Range”, Nucl. Sci. Eng. 131, 230 (1999) [CrossRef] [Google Scholar]
- M. Fukushima, Y. Kitamura, T. Kugo and S. Okajima, “Benchmark models for criticalities of FCA-IX assemblies with systematically changed neutron spectra”, J. Nucl. Sci. Technol., Published online: Jun (2015) [Google Scholar]
- International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03, OECD Nuclear Energy Agency September 2006 (rev) [Google Scholar]
- NEA/NSC/WPEC/DOC(2011)433, Final Report of WPEC Subgroup 29 on 235U Capture Cross-section in the keV to MeV Energy Region, Nuclear Energy Agency, Organization for Economic Co-operation and Development, 2011 [Google Scholar]
- Y. Danon, “Nuclear Data Measurements at RPI”, 2011 Cross Section Evaluation Working Group Meeting, National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY, November 16, 2011 [Google Scholar]
- M. Jandel et al., “New Precision Measurements of the 235U(n,γ) Cross Section”, Phys. Rev. Lett. 109 (2012) [Google Scholar]
- Carlson A.D. et al. “International Evaluation of Neutron Cross Section Standards”, N. D. S. (2009) 3215-3324 (pg 3291). See also https://www-nds.iaea.org/standards/Data/endf-6-format/std-092_U_235.endf [Google Scholar]
- L. Erradi, A. Santamarina, and O. Litaize, “The Reactivity Temperature Coefficient Analysis in Light Water Moderated UO2 and UO2-PuO2 Lattices”, Nucl. Sci. Eng. 144, 47 (2003) [CrossRef] [Google Scholar]
- R.R. Spencer, J.A. Harvey, N.W. Hill, and L. Weston, Nucl. Sci. Eng. 96, 318 (1987) [CrossRef] [Google Scholar]
- J.A. Harvey, N.W. Hill, F.G. Perey, G.L. Tweed, and L.C. Leal, Proc. Int. Conf. on Nuclear Data for Science and Technology, Mito, Japan, May 30– June 3, 1988 [Google Scholar]
- R. Gwin, R.R. Spencer, R.W. Ingle, J.H. Todd, and S.W. Scoles, Nucl. Sci. Eng. 88, 37 (1984) [CrossRef] [Google Scholar]
- L.W. Weston and J.H. Todd, Nucl. Sci. Eng. 111, 415 (1992) [Google Scholar]
- L.W. Weston and J.H. Todd, Nucl. Sci. Eng. 88, 567 (1984) [CrossRef] [Google Scholar]
- C. Paradela et al. “High accuracy 235U(n,f) data in the resonance region”, The European Physical Journal, Vol. 111 (2016), WONDER-2015 4th International Workshop on Nuclear Data Evaluation for Reactor Application, Aix-en-Provence, France, 5–8 October 2015 [Google Scholar]
- C. Wagemans, P. Schillebeeckx, A.J. Deruyter, and R. “Subthermal Fission Cross Section Measurements for 235U and 239Pu”, Nuclear Data for Science and Technology, p. 91, Mito, Japan (1988) [Google Scholar]
- J.A. Wartena, H. Weigmann, and C. Burkholz, Report IAEA Tecdoc 941, 123 (1987) [Google Scholar]
- H. Weigmann, P. Geltenbort, B. Keck, K. Shrenckenbach, and J.A. Wertena, Proc. Intern. Conf. on The Physics of Reactors, Marseille P1, 133 (1990) [Google Scholar]
- R.B. Perez, G. de Saussure, and E.G. Silver, Nucl. Sci. Eng. 52, 46 (1973) [CrossRef] [Google Scholar]
- G. de Saussure, R. Gwin, L.W. Weston, and R.W. Ingle, “Simultaneous Measurements of the Neutron Fission and Capture Cross Section for 235U for Incident Neutron Energy from 0.4 eV to 3 keV”, ORNL/TM-1804, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory; Oak Ridge, TN (1967) [Google Scholar]
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