Two-step neutronics calculations with Shift and Griffin for advanced reactor systems
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference26 articles.
1. Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code;Boyd;Nucl. Technol.,2019
2. D. Brown, M. Chadwick, R. Capote, A. Kahler, A. Trkov, M. Herman, A. Sonzogni, Y. Danon, A. Carlson, M. Dunn, D. Smith, G. Hale, G. Arbanas, R. Arcilla, C. Bates, B. Beck, B. Becker, F. Brown, R. Casperson, J. Conlin, D. Cullen, M.-A. Descalle, R. Firestone, T. Gaines, K. Guber, A. Hawari, J. Holmes, T. Johnson, T. Kawano, B. Kiedrowski, A. Koning, S. Kopecky, L. Leal, J. Lestone, C. Lubitz, J. Márquez Damián, C. Mattoon, E. McCutchan, S. Mughabghab, P. Navratil, D. Neudecker, G. Nobre, G. Noguere, M. Paris, M. Pigni, A. Plompen, B. Pritychenko, V. Pronyaev, D. Roubtsov, D. Rochman, P. Romano, P. Schillebeeckx, S. Simakov, M. Sin, I. Sirakov, B. Sleaford, V. Sobes, E. Soukhovitskii, I. Stetcu, P. Talou, I. Thompson, S. van der Marck, L. Welser-Sherrill, D. Wiarda, M. White, J. Wormald, R. Wright, M. Zerkle, G. Žerovnik, Y. Zhu, 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 (2018) 1–142. doi:10.1016/J.NDS.2018.02.001.
3. L. Cheng, B. Zhong, H. Shen, Z. Hu, B. Li, Generation of Multigroup Cross Sections with an Improved Monte Carlo Algorithm, Nuclear Science and Engineering 194 (1) (2020) 44–55. arXiv:https://doi.org/10.1080/00295639.2019.1650520, doi:10.1080/00295639.2019.1650520. url: doi: 10.1080/00295639.2019.1650520.
4. S. Choi, K.S. Smith, H. Kim, T. Tak, D. Lee, On the Diffusion Coefficient Calculation in Two-Step Light Water Reactor Core Analysis, Journal of Nuclear Science and Technology 54 (6) (2017) 705–715. arXiv:https://doi.org/10.1080/00223131.2017.1299648, doi:10.1080/00223131.2017.1299648. url: doi: 10.1080/00223131.2017.1299648.
5. On the Use of the Serpent Monte Carlo Code for Few-Group Cross Section Generation;Fridman;Ann. Nucl. Energy,2011
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