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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)

Paper

Single Channel Design Based on Artificial Intelligence for Molten Salt Reactors

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

Paper

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)

Paper