The International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (MC 2011) is a part of a series of topical meetings organized by the Mathematics and Computation Division of the American Nuclear Society (ANS) and this 2011 version is promoted by the Latin American Section (LAS).
As humankind seeks abundant and environmentally responsible energy in the coming decades, the renaissance of nuclear power will undoubtedly become reality as it is a proven technology and has the potential to generate virtually limitless energy with no greenhouse gas emissions during operations. In addition, basic research and nuclear technology applications in chemistry, physics, biology, agriculture, health and engineering have been showing their importance in the innovation of nuclear technology applications with sustainability.
MC 2011 will provide an international forum to scientists from around the world to present their most recent work and exchange ideas on a powerful class of methodologies extensively used for solving mathematical models of physical phenomena and processes applied to nuclear science and engineering. One of the aims is to promote new research tools and procedures that help link Mathematics, Applied Sciences and Technology. Therefore, the MC 2011 will offer an opportunity for direct information exchange between participants from both academia and industry.
Being held in Brazil, MC 2011 provides a forum to cellebrate the 10th Anniversary of Angra 2 Nuclear Power Unit commercial operation startup on February 1, 2001, located in Angra dos Reis city, state of Rio de Janeiro.
Participation in the MC 2011 will also provide an opportunity to visit Rio de Janeiro, the wonderful city, which is the mosaic of enchantments scattered between the sea and the mountains.
The interdisciplinary MC 2011 technical program will consist of plenary sessions, workshops, parallel oral presentation sessions and
poster sessions.
Papers are solicited in the following subject categories:
- - Computer Code Analysis
- - Fluid Flow & Heat Transfer
- - Inverse Problems & Perturbation Theory
- - Neutral and Charged Particle Transport
- - Nuclear Bio-sciences
- - Nuclear Data Evaluation and Application
- - Nuclear Fuels & Nuclear Chemistry
- - Nuclear Material Sciences
- - Nuclear Reactor Analysis
- - Optimization. Data Assimilation and Artificial Intelligence
- - Shielding and Homeland Security
- - Simulation and Mathematical Methods for Multi-discipline Problems