The study of fission yields has a major impact on the characterization and understanding process its applications. products have direct influence amount neutron poisons that limit fuel burnup evaluation decay heat reactor after shutdown. Fission yield represents synthesis experimental theoretical knowledge in order to perform best estimation mass independent product yields. Today, lack correlat...

Two sodium-bonded, single phase (Uo.8PUo_2)C fueled. Type 316 stainless steel clad fuel elements were irradiated in EBR-II at heating rates of ~30 kW/ft to burnups of 3.7 and 5.0 at ." . No clad failures occurred as a result of the irradiation. Total fission gas release from the fuel was low. Thermal stresses in the fuel resulted in fuel splitting upon initial startup and general fuel fragmenta...

Multiphysics solution challenges are legion within the field of nuclear reactor design and analysis. One major issue concerns the coupling between heat and neutron flow (neutronics) within the reactor assembly. These phenomena are usually very tightly interdependent, as large amounts of heat are quickly produced with an increase in fission events within the fuel, which raises the temperature th...

Decay heat (DH) is the produced through a radioactive decay of fission products during or after reactor operation. It known as second largest source power in core fission. Being such strong contributor to power, it should be accurately determined at any time Currently, there are two main approaches for DH estimation used simulation codes. One approach based on careful inventorying all target nu...

In this study, the mass flow in double-strata nuclear fuel cycle is analysed based on mass inventory balance model, and the cost evaluation is carried out. As the commercial reactor fuel cycle, which is assumed to be sustainable in a significantly long term, the following different reactors and fuel cycles are considered: (1) Scheme of light water reactor (LWR-UOX and -MOX) based on sea water u...

The paper presents the results of studies on burning minor actinides (MA) extracted from SNF thermal reactors in a BN-600 reactor, which uses complete set MAs instead traditional nuclear fuel types: uranium and/or plutonium. advantages such approach to MA are that long-lived waste is recycled and energy produced can be used, e.g., generate electricity. Besides, where, reactor with or MOX used f...

Monte Carlo methods for reactor analysis have been in development with the eventual goal of full-core analysis. To attain results with reasonable uncertainties, large computational resources are needed. Variance reduction methods have been developed in order to reduce the computational resources required to obtain results in a practical amount of time. This work seeks to expand research in the ...