We use a package called MCNP Utility for Reactor Evolution (MURE), initially developed by CNRS/IN2P3 labs to study Generation IV reactors.
The evolution of the reactor geometries and configurations of cooling systems as well as different effective factors of metal-hydride performance are also discussed.
Temperature evolution inside the reactor at different times and positions, chemical conversion, thermal power and overall efficiency were analysed for the selected cycles.
Unsteady mass and energy balances are solved to determine the evolution of the reactor temperature and of the outlet gas composition versus time.
Results are reported on the dynamic evolution along the reactor of, fuel conversion, temperature and current distribution, thermodynamic energy conversion efficiency and volumetric power density.
The effects of axial heat transfer in fully-insulated reactors and for insulated reactors with heat-sink inlets are examined for various model systems with either constant or variable rates of heat evolution along the reactor.
The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM).
The effect of different design parameters on characteristic safety variables, referred to as "observable variables," extracted from reactor evolution during accidents, is analyzed, and the concept of "safety design maps" is introduced.
The prediction of the consequences of a runaway reaction in terms of temperature and pressure evolution in a reactor requires the knowledge of the reaction kinetics, thermodynamics and fluid dynamics inside the vessel during venting.
In this lecture I shall focus on the evolution of nuclear reactor containments in India and highlight the design, associated structural and thermal hydraulics safety assessment made over the years for the improvement of containment performance.
