Open Access
Issue
EPJ Web Conf.
Volume 308, 2024
ISRD 17 – International Symposium on Reactor Dosimetry (Part II)
Article Number 04004
Number of page(s) 8
Section Nuclear Data, Uncertainties and Adjustment
DOI https://doi.org/10.1051/epjconf/202430804004
Published online 11 November 2024
  1. U.S. Nuclear Regulatory Commission, “Reactor Pressure Vessel Fluence Evaluation Methodology for Extended Beltline Locations,” NUREG/CR-7286, May 2022 [Google Scholar]
  2. U.S. Nuclear Regulatory Commission, “Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data,” NUREG/CR-7045, September 2011 [Google Scholar]
  3. C. Konno, K. Ochiai, S. Ohnishi, “Insufficient self-shielding correction in VITAMIN- B6,” Prog. Nucl. Sci. Technol., 1, 32–35 (2011) [CrossRef] [Google Scholar]
  4. C. Konno, et al., “Important Remarks on Latest Multigroup Libraries,” Prog. Nucl. Sci. Technol., 2, 341–345 (2011) [CrossRef] [Google Scholar]
  5. B. T. Rearden and M. A. Jessee, Editors. “SCALE 6.2: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design; Includes ORIGEN and AMPX, ORNL/TM-2005/39 Version 6.2,” Oak Ridge National Laboratory, April 2016 [Google Scholar]
  6. R. E. MacFarlane, et al., The NJOY Nuclear Data Processing System, Version 2016. United States: N. p., 2017. Web. DOI: 10.2172/1338791 [CrossRef] [Google Scholar]
  7. Nuclear Data Sheets, Volume 107, Issue 12, pp. 2931–3060, December 2008 [Google Scholar]
  8. RSICC Peripheral Shielding Routine PSR-317, “TRANSX 2.15: Code system to Produce Neutron, Photon, and Particle Transport Tables for Discrete-Ordinates and Diffusion Codes from Cross Sections in MATXS Format,” Radiation Safety Information Computational Center, Oak Ridge National Laboratory (ORNE), December 1995 [Google Scholar]
  9. ORNE Report ORNL/TM-13204, “H. B. Robinson-2 Pressure Vessel Benchmark,” (NUREG/CR-6453), February 1998 [Google Scholar]
  10. C. Konno, et al., “Effect of IAEA Patch for TRANSX 2.15.” 20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018 [Google Scholar]
  11. C. J. Werner, et al., “MCNP6.2 Release Notes”, Los Alamos National Laboratory, report LA-UR-18-20808 (2018) [CrossRef] [Google Scholar]
  12. RSICC Computer Code Collection CCC-650, “DOORS 3.2a, One- Two- and Three Dimensional Discrete Ordinates Neutron/Photon Transport Code System,” Radiation Safety Information Computational Center, Oak Ridge National Laboratory (ORNE), May 2007 [Google Scholar]
  13. ORNE Report ORNL/TM-13204, “H. B. Robinson-2 Pressure Vessel Benchmark,” (NUREG/CR-6453), February 1998 [Google Scholar]
  14. Westinghouse Report WCAP-18124-NP-A, Rev. 0, “Fluence Determination with RAPTOR-M3G and FERRET,” July 2018. (Available from the U.S. NRC Website as Accession No. ML18204A010.) [Google Scholar]

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