Open Access
| Issue |
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
|
|
|---|---|---|
| Article Number | 01005 | |
| Number of page(s) | 9 | |
| Section | Dosimetry in Research and Test Reactors and in Accelerators | |
| DOI | https://doi.org/10.1051/epjconf/201610601005 | |
| Published online | 03 February 2016 | |
- MCNP – A Gen. Monte Carlo N-Part. Trans. Code, V5, LA-UR-03-1987, Los Al., NM (2003) [Google Scholar]
- M. Franco Jr, Health Phys. Tech., Sandia Nat. Lab. New Mexico, USA [Google Scholar]
- L.M.R Snoj, Calc. of Pow. Dens. with MCNP in TRIGA reac, Int. Conf. Nuc. En. for New Eur. (2006) [Google Scholar]
- D. Vehar, Nuc. Eng., Sandia Nat. Lab., New Mexico, USA [Google Scholar]
- J.J. Bevelacqua. Basic Health Physics:2nd Edition. WILEY-VCH (2010) [Google Scholar]
- E. Baum, H Knox, T. Miller, Nucl. and Iso. Chart of the Nuclides. 16th Ed. 54,60 (2002) [Google Scholar]
- S.G. Kwon, Calc. Neut. and G-Ray Flux-to-Dose-Rate Conv. Fac, Korea At. En. Res. Inst. (1980) [Google Scholar]