Open Access
| Numéro |
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
|
|
|---|---|---|
| Numéro d'article | 04005 | |
| Nombre de pages | 9 | |
| Section | Cross Sections, Nuclear Data and Uncertainties | |
| DOI | https://doi.org/10.1051/epjconf/201610604005 | |
| Publié en ligne | 3 février 2016 | |
- G. Longoni, S. L. Anderson, World Scientific Publishing Co. Pte. Ltd., 722–732 (2009) [Google Scholar]
- D. T. Ingersoll, J. E. White, R. Q. Wright, H. T. Hunter, C. O. Slater, N. M. Greene, R. E. MacFarlane, R. W. Roussin, ORNL-6795 (1994) [Google Scholar]
- J. E. White, D. T. Ingersoll, R. Q. Wright, H. T. Hunter, C. O. Slater, N. M. Greene, R. E. MacFarlane, R. W. Roussin, ORNL-6795, NUREG/CR-6214, Revision 1 (1999) [Google Scholar]
- J. M. Risner, D. Wiarda, M. E. Dunn, T. M. Miller, D. E. Peplow, B. W. Patton, NUREG/CR-7045, ORNL/TM-2011/12 (2011) [Google Scholar]
- F. A. Alpan, Journal of ASTM International, 548–560 (2012) [Google Scholar]
- J. F. Carew, K. Hu, A. Aronson, A. Prince, G. Zamonsky, NUREG/CR-6115, BNL-NUREG-52395 (2001) [Google Scholar]
- V. McLane and Members of the Cross Section Evaluation Working Group, BNL-NCS-17541, (1996) [Google Scholar]
- M.B. Chadwick, P. Oblozinsky, M. Herman et al, Nuclear Data Sheets, 107, pp. 2931–3060, (2006) [NASA ADS] [CrossRef] [Google Scholar]
- F. A. Alpan, A. Haghighat, Nuclear Science and Engineering, 149, No. 1, pp. 51–64 (2005) [CrossRef] [Google Scholar]
- BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis, FPN-P9H6-002, ENEA (2007) [Google Scholar]
- SCALE 6.0: “Modular Code System for Performing Criticality and Shielding Analyses for Licensing Evaluation with ORIGEN-ARP”, CCC-750 (January 2009) (available from the Radiation Safety Information Computational Center (RSICC), Oak Ridge National Laboratory) [Google Scholar]
- J. D. Andrachek et al, WCAP-14040-A, Rev. 4, Westinghouse Electric Company LLC (2004) [Google Scholar]