Open Access
| Issue |
EPJ Nuclear Sci. Technol.
Volume 2, 2016
|
|
|---|---|---|
| Article Number | 4 | |
| Number of page(s) | 10 | |
| DOI | https://doi.org/10.1051/epjn/e2015-50057-8 | |
| Published online | 15 January 2016 | |
- SCALE: a comprehensive modeling and simulation suite for nuclear safety analysis and design, ORNL (Oak Ridge National Laboratory)/TM-2005/39, vs. 6, 2011 [Google Scholar]
- I.C. Gauld, O.W. Hermann, R.M. Westfall, ORIGEN scale system module to calculate fuel depletion, actinide transmutation, fission product buildup and decay, and associated radiation terms (Oak Ridge National Laboratory, Oak Ridge, Tennessee, 2009) ORNL/TM 2005/39, Version 6, Vol. II, Sect. F7 [Google Scholar]
- Model inventory for radioactive materials, MIRAM 14. NAGRA Technical Report NTB 14-04, NAGRA (National Cooperative for the Disposal of Radioactive Waste), Wettingen, Switzerland, 2014 [Google Scholar]
- H. Maxeiner, M. Vespa, B. Volmert, M. Pantelias, S. Caruso, T. Müller, Development of the inventory for existing and future radioactive wastes in Switzerland: ISRAM & MIRAM, ATW Int. J. Nucl. Power 58, 625 (2013) [Google Scholar]
- NAGRA: model radioactive waste inventory for reprocessing waste and spent fuel, NAGRA Technical report NTB 01-01, NAGRA (National Cooperative for the Disposal of Radioactive Waste), Wettingen, Switzerland, 2002 [Google Scholar]
- NAGRA: Entsorgungsprogramm 2008 der Entsorgungspflichtigen, NAGRA Technical report NTB 08-01, NAGRA (National Cooperative for the Disposal of Radioactive Waste), Wettingen, Switzerland, 2008 [Google Scholar]
- X-5 Monte Carlo Team, MCNP - A general Monte Carlo N-particle transport code, Version 5; Vol. I: Overview and theory, Technical report LA-UR-03-1987, Los Alamos National Laboratory, 2005 [Google Scholar]
- R.A. Forrest, FISPACT-2007: User manual, Technical report, UKAEA FUS 534, EURATOM/UKAEA Fusion Association, 2007 [Google Scholar]
- W.B. Wilson et al., A manual for CINDER’90 version 07.4 codes and data, Technical report LA-UR-07-8412, Los Alamos National Laboratory, 2008 [Google Scholar]
- U. Hesse, K. Hummelsheim, GRSAKTIV-II: Ein Programmsystem zur Berechnung der Aktivierung von Brennelement- und Core-Bauteilen in Vielgruppendarstellung, Technical report GRS-A-3002, Gesellschaft für Anlagen- und Reaktorsicherheit, 2001 [Google Scholar]
- A.T. Luksic, B.D. Reid, Using the ORIGEN-2 computer code for near core activation calculations in Proceedings of the third international conference on high level radioactive waste management ANS Las Vegas, NV (USA), 1992 (1992) [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.