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Advances in MCNP for Reactor Calculations

R. B. Wilkerson (LANL), G. W. McKinney (LANL), C. J. Josey (LANL), M. E. Blood (LANL), J. D. Galloway (LANL), J. C. Armstrong (LANL), H. R. Trellue (LANL)

Single Channel Design Based on Artificial Intelligence for Molten Salt Reactors

Mehmet Turkmen (Univ. of Illinois), Kathryn D. Huff (Univ. of Illinois)

Development of FRENDY Nuclear Data Processing Code: Generation Capability of Multi-group Cross Sections from ACE File

Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency)


Discussion

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