JNC has proposed an evolutional concept of fast reactor recycle system for minimising high-level waste (HLW) by adopting an unconventional recycling scheme based on the idea of “rough removal of unnecessary elements” instead of a conventional one as “pure recovery of necessary elements”. The concept was named “ORIENT-cycle” (Optimisation by Removing Impedimental Elements). “Unnecessary elements...

In order to extend the operation life of BN-600 reactor, it is necessary validate operability permanent reactor elements – including neutron reflector that operate under conditions with high damaging doses and temperatures. It can be done through irradiating metal simulating package inside a materials science assembly inserted in BN-600. The paper describes basic characteristics assembly, desig...

In this paper, the Monte Carlo N-Particle extended computer code (MCNP) were used to design a model of European Sodium-cooled Fast Reactor. The multiplication factor, conversion delayed neutrons fraction, doppler constant, control rod worth, sodium void masses for major heavy nuclei, radial and axial power distribution at high burnup are studied. results show that reactor breeds fissile isotope...

This paper gives an account of three projects funded by the European Union that heavily rely on numerical modeling and simulations nuclear reactors: CORTEX project (CORe monitoring Techniques EXperimental validation demonstration), McSAFER (High-Performance Advanced Methods Experimental Investigations for Safety Evaluation Generic Small Modular Reactors), METIS (MEthods Tools Innovations Seismi...

A highly enriched uranium coupled reactor consisting of pulse cores and a laser module is known as one of the reactors for nuclear-pumped laser. Neutronic analysis on a low enriched uranium coupled reactor which consists of pulse cores and a laser module was performed. Calculation results showed that a low enriched uranium coupled reactor could achieve criticality by using several expanded puls...

Neutron diffusion equation is being used to estimate the safety margin of a neutronic parameter. The assessment of safety margin requires variability and uncertainty analysis. When the variation of sensitive parameter is varying in an imprecise manner, the evaluation of safety margin is very difficult using probabilistic analysis. However, fuzzy set theory based approach may be used to estimate...