Open Access
Issue |
EPJ Web Conf.
Volume 308, 2024
ISRD 17 – International Symposium on Reactor Dosimetry (Part II)
|
|
---|---|---|
Article Number | 02009 | |
Number of page(s) | 12 | |
Section | Calculational Methods | |
DOI | https://doi.org/10.1051/epjconf/202430802009 | |
Published online | 11 November 2024 |
- W.A. Wieselquist, R.A. Lefebvre, and M. A. Jessee, “SCALE Code System,” ORNL/TM-2005/39, Oak Ridge National Laboratory (2020) [CrossRef] [Google Scholar]
- J.C. Wagner, D.E. Peplow, and S.W. Mosher, “FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport Calculations,” Nuclear Science and Engineering, 176, 37–57 (2014) [CrossRef] [Google Scholar]
- Abilene Christian University Molten Salt Research Reactor Preliminary Safety Analysis Report (08/332022) [Document ML22227A203 retrieved from https://adams.nrc.gov on 09/2022] [Google Scholar]
- E693-12 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E 706(ID), ASTM International (June 2012) [Google Scholar]
- E523-11 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper, ASTM International (July 2011) [Google Scholar]
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.