Open Access
Issue
EPJ Web of Conf.
Volume 284, 2023
15th International Conference on Nuclear Data for Science and Technology (ND2022)
Article Number 17015
Number of page(s) 4
Section Thermal Neutron Scattering
DOI https://doi.org/10.1051/epjconf/202328417015
Published online 26 May 2023
  1. J. Holmes and M. Zerkle and D.P. Hendricks. (2017).Benchmarking a first-principles thermal neutron scattering law for water ice with a diffusion experiment. EPJ Web of Conferences. 146. 13004. 10.1051/epjconf/ 201714613004. [Google Scholar]
  2. T. Goorley et al., Nucl. Tech., 180, 298 (2012). [CrossRef] [Google Scholar]
  3. D.A. Brown el al., Nuclear Data Sheets,ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELOproject Cross Sections, New Standards and Thermal Scattering Data, 148, 1–142, (2018), URL:https://www.sciencedirect.com/science/article/pii/S009–0375218300206 [Google Scholar]
  4. M.B. Chadwick, M. Herman, P. Obložinsky, et al.,”ENDF/B-VII.1 Nuclear Data for Science and Technology:Cross Sections, Covariances, Fission Product Yields and Decay Data”, Nuclear Data Sheets, 112, pp.2887 – 2996 (2011) [Google Scholar]
  5. N.G. Sjostrand, J. Mednis, T. Nilsson, Arkiv Fysik, Geometric buckling measurements using the pulsed neutron source method, 35, 471-482 (1959) [Google Scholar]
  6. W.M. Lopez, J.R. Beyster, Nuclear Science and Engineering, Measurment of Neutron Diffusion Parameters in Water by the Pulsed Neutron Method, 12:2, 190–202 (1962) [Google Scholar]
  7. S.F. Nassar, G. Murphy, Nuclear Science and Engineering, Pulsed-Neutron Diffusion Parameters in Spherical Water Systems, 35:1, 70–79 (1969) [Google Scholar]
  8. Y. Danon, Rensselaer Polytechnic Institute Cross Section Data Reduction Computer Code (RPIXDR 2.2.2), Rensselaer Polytechnic Institute, Troy, New York (2006). [Google Scholar]
  9. D. Fritz and Y. Danon, NCSP Technical Program Review, Thermal Neutron Cross Section Measurements at the RPI LINAC, (2022), URL: https://ncsp.llnl.gov/program-management/ncsptechnical- program-review/nuclear-criticality-safetyprogram-ncsp-technical-program-review–202 [Google Scholar]
  10. D. Fritz and Y. Danon, Journal of Neutron Research, Enhancement of sub-thermal neutron flux through cold polyethylene, 23, num 2–3, 179–184, (2021), DOI:10.3233/JNR-210010 [Google Scholar]
  11. Los Alamos National Laboratory, New Mexico, NJOY Nuclear Data Processing System Version 2016 (2018) [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.