Open Access
Issue |
EPJ Web Conf.
Volume 308, 2024
ISRD 17 – International Symposium on Reactor Dosimetry (Part II)
|
|
---|---|---|
Article Number | 06008 | |
Number of page(s) | 11 | |
Section | Dosimetry in Test and Research Reactors | |
DOI | https://doi.org/10.1051/epjconf/202430806008 | |
Published online | 11 November 2024 |
- D.R. Redhouse (2022), E.S. Lum, J. Koglin, “Radiation Characterization Summary: WSMR- Molly G at the 6-Inch and 24-Inch Irradiation Locations,” SAND2022-13797, Sandia National Laboratories, Albuquerque, NM, October 2022 [Google Scholar]
- ASTM E720-16 - “Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics,” ASTM Standard, Published 2016 [Google Scholar]
- IRDFF-II (2014), v1.03, March 3, 2014, https://www-nds.iaea.org/IRDFF/ [Google Scholar]
- MCNP - “A General Monte Carlo N-Particle Transport Code, Version 6.1,” LA-UR-03-1987, Los Alamos, NM, April 2003 [Google Scholar]
- K. R. DePriest (2004) and P. J. Griffin, “NuGET User’s Guide: Revision 0,” SAND2004-1567, Sandia National Laboratories, Albuquerque, NM, April 2004 [Google Scholar]
- K. R. DePriest (2006), P. J. Cooper, E. J. Parma, “MCNP/MCNPX Model of the Annular Core Research Reactor,” SAND Report SAND2006-3067, Sandia National Laboratories, Albuquerque, NM, May 2006 [CrossRef] [Google Scholar]
- L. B. Engle (1962), P. C. Fisher, Los Alamos Report LAMS-2642, 1962 [Google Scholar]
- P. C. Fisher (1964), L. B. Engle, “Delayed Gammas from Fast-Neutron Fission of Th232, U233, U235, U238, and Pu239,” Physical Review, Vol. 134, Number 4B, pp. B796–B816, 25 May 1964 [CrossRef] [Google Scholar]
- P. J. Griffin (1994a), J. G. Kelly, and J.W. VanDenburg, “User’s Manual for SNL-SAND-II Code,” SAND93-3957, April 1994 [CrossRef] [Google Scholar]
- P. J. Griffin (1994b), J. G. Kelly, and D. W. Vehar, “Updated Neutron Spectrum Characterization of SNL Baseline Reactor Environments,” SAND93-2554, April 1994 [Google Scholar]
- P. J. Griffin (2011a), C. D. Peters, and D. W. Vehar, “Recommended Neutron Dosimetry Cross Sections for the Characterization of Neutron Fields,” RADECS 2011 Proceedings, 2011 [Google Scholar]
- W.N. McElroy (1967), S. Berg, T. Crockett, R. G. Hawkins, “A Computer-Automated Iterative Method for Neutron Flux Spectra Determination by Foil Activation, Vol. II: SAND-II (Spectrum Analysis by Neutron Detectors II) and Associated Codes,” AFWL-TR-67-41, September 1967 [Google Scholar]
- E. J. Parma (2014), T. J. Quirk, L. L. Lippert, P. J. Griffin, G. E. Naranjo, and S. M. Luker, “Radiation Characterization Summary: ACRR 44-Inch Lead-Boron Bucket Located in the Central Cavity onf the 32-Inch Pedestal at the Core Centerline (ACRR-LB44-CC-32-cl),” SAND13-3406, April 2013 [Google Scholar]
- F. W. Stallmann (1985), “LSL-M2: A Computer Program for Least-Squares Logarithmic Adjustment of Neutron Spectra,” NUREG/CR-4349, ORNL/TM-9933, March 1985 [Google Scholar]
- A. Trkov, P.J. Griffin, S.P. Simakov, et al., “IRDFF-IJ: A New Neutron Metrology Library,” Nuclear Data Sheets, Vol. 163, pg. 1–108, January 2020 [CrossRef] [Google Scholar]
- D. Loaiza, D. Gehman (2006), “End of an Era for the Los Alaomos CCritical Experiments Facility: History of Critical Assemblies and Experiments (1946-2004)”, Annuals of Nuclear Energy, Vol. 33, pg. 1339–1359, September 2006 [CrossRef] [Google Scholar]
- H.C. Paxton (1983), “A History of Critical Experiments at Pajarito Site”, Los Alamos National Laboratory, lA-9685-H, March 1983 [CrossRef] [Google Scholar]
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