Open Access
Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
---|---|---|
Article Number | 17005 | |
Number of page(s) | 11 | |
Section | Nuclear Criticality Safety | |
DOI | https://doi.org/10.1051/epjconf/202124717005 | |
Published online | 22 February 2021 |
- ANSI/ANS-8.1-2014, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors American Nuclear Society (2014). [Google Scholar]
- N6.1-1964, A., Safety Standard for Operations with Fissionable Materials Outside Reactors. American Nuclear Society and The American Society of Mechanical Engineers (1964). [Google Scholar]
- N16.1-1969, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors. American Nuclear Society (1969). [Google Scholar]
- N16.1-1975/ANS-8.1, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors. American Nuclear Society (1975). [Google Scholar]
- ANSI/ANS-8.1-1983, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors. American Nuclear Society (1983). [Google Scholar]
- ANSI/ANS-8.1-1998, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors. American Nuclear Society (1998). [Google Scholar]
- SCALE Code System, M.A. Jessee and B.T Rearden, Editors. Oak Ridge National Laboratory: Oak Ridge, Tennessee. p. 2747 (2017). [Google Scholar]
- D.A. Brown et al., “ENDF/B-VIII. 0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-Project Cross Sections, New Standards and Thermal Scattering Data.” Nuclear Data Sheets. 148: pp. 1–142 (2018). [Google Scholar]
- A.-W Group, ANS-8.1 Calculations-2005: Argonne National Laboratory (ANL) Approach and Methodology (2005). [Google Scholar]
- C.F. Weber and C.M. Hopper, Application of the Pitzer Method for Modeling Densities of Actinide Solutions in the SCALE Code System. Nuclear Technology, 153(1): p. 1-8 (2006). [Google Scholar]
- S.E. Parkey, K.R.E., and C. F. Weber, “Comparison of Uranyl Nitrate Solution Modeling Methods,” in Proc. Nuclear Criticality Safety Division Topl. Mtg. Knoxville, TN (2005). [Google Scholar]
- H. Clark, H., “Subcritical Limits for Plutonium Systems”. Nuclear Science and Engineering. 79(1): pp. 65–84 (1981). [Google Scholar]
- H. Clark, “Subcritical Limits for Uranium-233 U Systems.” Nuclear Science and Engineering. 81 (1982). [Google Scholar]
- H.K. Clark, “Subcritical limits for Uranium-235 Systems.” Nuclear Science and Engineering. 81(3): pp. 351–378 (1982). [Google Scholar]
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