The ANS M&C 2017 meeting will take place in Jeju, Korea, which is a beautiful semi-tropical island providing a relaxing and friendly environment. The reactor physics and computational science division (RPCSD) of the Korean Nuclear Society (KNS) will host the conference with the support of the strong nuclear industry of Korea in which 24 power reactors are operating to supply about 35% of the national electricity production. The subject areas span not only the traditional transport and reactor physics analysis methods, but also computational thermal-hydraulics, materials science and fusion to reflect the remarkable advances in the computational methods in various fields of nuclear science and engineering. Four-page extended summaries are solicited in 12 subject areas (see right).

  • All the classical subjects in each subject area are considered within the scope of the conference. In addition, there will be subjects of special interest as listed in the Technical Program/Subjects menu. After the conference, selected papers will be published in a special issue of the KNS journal of Nuclear Engineering and Technology.

  • The conference will be held at the International Convention Center Jeju which is a top-notch convention facility located in the Jungmun resort complex housing wonderful hotels and amusement facilities at the gorgeous southern seafront of Jeju. Please join the conference to present your work to the worldwide nuclear engineering mathematics & computation community and to enjoy the opportunity of relaxation.

  • The template of the two-column extended summaries can be in the DOWNLOAD tab on the right. Please limit the summary to 4 pages and submit your summary by October 15, 2016.

Click here for the complete Call for Papers.


  • Final Call for PapersFebruary 8, 2016
  • Extended Summary DueOctober 29, 2016
  • Review ResultsDecember 17, 2016
  • Full Paper DueFebruary 18, 2017
  • Early Registration DueMarch 4, 2017
  • MeetingApril 16, 2017


  • Deterministic Transport Methods and Applications
  • Monte Carlo Methods and Applications
  • Nuclear Data Evaluation and Assimilation of Integral Experiments
  • Subcritical System Analysis Methods
  • Uncertainty Quantification and Sensitivity Analysis
  • General Reactor Analysis Methods and Applications
  • Computational Fluid Dynamics
  • Computational Nuclear Thermal-Hydraulics
  • Multiphysics Power Reactor Simulation
  • Computational Materials Science
  • Modeling and Simulation for Fusion Energy Systems
  • High Performance Computing for Nuclear Applications