Open Access
| Numéro |
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
|
|
|---|---|---|
| Numéro d'article | 02003 | |
| Nombre de pages | 8 | |
| Section | Reactor Surveillance and Plant Life | |
| DOI | https://doi.org/10.1051/epjconf/201610602003 | |
| Publié en ligne | 3 février 2016 | |
- G. Longoni and S. L. Anderson, Reactor Dosimetry Applications Using RAPTOR-M3G: A New Parallel 3-D Radiation Transport Code. 2009. Reactor Dosimetry State of the Art 2008 – Proceedings of the 13th International Symposium on Reactor Dosimetry. World Scientific. Singapore [Google Scholar]
- M. A. Hunter et al., Extension of RAPTOR-M3G to R-Θ-Z Geometry For Use In Reactor Dosimetry Applications. 2009. Reactor Dosimetry State of the Art 2008 – Proceedings of the 13th International Symposium on Reactor Dosimetry. World Scientific. Singapore [Google Scholar]
- ORNL RSICC DLC-185, BUGLE-96 – Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications. March 1996 [Google Scholar]
- B. Petrović and A. Haghighat, New Directional Theta-Weighted (DTW) Differencing Scheme and Reduction of Estimated Pressure Vessel Fluence Uncertainty. 1998. Proceedings of the 9th International Symposium on Reactor Dosimetry. World Scientific. Singapore [Google Scholar]
- ORNL RSICC PSR-145, FERRET – Least Squares Solution to Nuclear Data and Reactor Physics Problems. January 1980 [Google Scholar]
- ORNL RSICC DLC-178, SNLRML – Recommended Dosimetry Cross Section Compendium. July 1994 [Google Scholar]
- USNRC Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence. March 2001 [Google Scholar]
- J. D. Andracheck et al., WCAP-14040-A, Revision 4, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves. May 2004 [Google Scholar]