Fission Reactor Analysis

Principal Investigator: Greenspan

This program is concerned primarily with the behavior of neutrons
in thermal and fast fission reactors and includes such topics as
neutron diffusion and slowing down, criticality, numerical methods,
and transport theory. A wide range of research activity is carried
out in this area. It includes conception, design and analysis of
advanced reactors such as novel concepts of power reactors (see
paper), reactors for the transmutation of nuclear waste (see paper)
and reactors for space exploration (see paper); conception and analysis
of advanced nuclear fuel cycles (see paper), including proliferation
resistant multi-recycling of the nuclear fuel; Investigation of
possibilities for improving the design and performance of Light-Water
Reactors (see paper); Development of improved computational methods
for core design and analysis (see paper); development of intelligent
methods for the optimization of the design of nuclear systems (see
paper); criticality safety analysis (see paper); as well as radiation
shielding design optimization (see paper) and design of facilities
for medical applications of nuclear radiation (see paper). We are
actively involved in the Generation-IV, Nuclear Energy Research
Initiative, Nuclear Engineering Education Research and Advanced
Fuel Cycle Initiative programs of DOE as well as in the NASA space
nuclear power program. We have research collaboration with National
Laboratories including Lawrence Berkeley National Laboratory, Lawrence
Livermore National Laboratory, Los Alamos National Laboratory, Argonne
National Laboratory, Idaho National Laboratory and Oak-Ridge National
Laboratory. Professor Vujic
is also involved in this project.