For more than a year, ECN is engaged in a research programme on transmutation of actinides as well as of fission products by means of respectively fission and neutron capture. It is intended to contribute to international efforts, which evaluate recycling options of the nuclear waste problem. Besides studies on strategy and scenarios, efforts are made to demonstrate possibilities for transmutat...

} The mechanistic smeared cracking model was extended from two to three dimensions (page 2). } Subcontinuum molecular dynamics simulations were used to investigate oxide fuel grain boundary fractures during reactor transients (page 2). } An improved model of bubble and grain boundary interaction was developed (page 2). } Improved descriptions of fission-gas/grain boundary interactions and clust...

Previous Advanced Fuel Cycle Initiative (AFCI) studies were made to assess the effects of the existing accumulation of LWR spent fuel in the United States on the capability to partition/transmute actinides using existing and advanced LWRs. The concept of treating the “oldest fuel first” indicated that significant advantages could be gained in both partitioning, transmutation, and in overall cos...

Taking inventories in reactor cores is critical for understanding their radioactive source terms and establishing the relationship between activity concentration primary loop status of core’s fuel. However, there a niche which simple but accurate conditions nuclide can reliably predict fission gas activities core loop. In this study, efficient model called “Inventories Point Reactor Fission Gas...

Advanced Fuel Cycle Initiative research on transmutation fuels includes mono-nitride ceramic fuel forms, and consists of closely coordinated “hot” actinide and “cold” inert and surrogate fuels work. Matrix and surrogate materials work involves three major components: (1) fuel matrix synthesis and fabrication, (2) fuel performance, and (3) fuel materials modeling. The synthesis and fabrication c...

The present work investigates an appropriate way to calculate the 1700 atomic density changes in the reactor operations. To automate this procedure, a computer program has been designed by C#. This program suggests a way to solve this problem which is based on the solution system of differential equations (Bitman) that it is designed according to Runge-Kutta Fehlberg method. The designed softwa...

The interest in interplanetary space travel has stimulated much discussion on the desirability of using nuclear, rather than chemical, energy for the spacecraft propulsion. Comparisons of the relative merits of various propulsion systems have been extensively discussed in the literature. The results of such studies yield a diversity of conclusions, depending on the assumptions which are made in...

Model-independent reactor isotopic cross sections per fission are determined by global fits of the antineutrino data from High-Enriched Uranium (HEU) rates, Low-Enriched (LEU) and fuel evolution data. Taking account implicit quasi-linear relationship between fractions $^{239}\rm{Pu}$ $^{241}\rm{Pu}$ in LEU data, Inverse-Beta-Decay (IBD) yields their correlations fissionable isotopes $^{235}\rm{...