Reference 1-GWe D-T reactors; tokamak TR-1, spherical tokamak ST-1 and helical HR-1 reactors, are designed using PEC (Physics Engineering Cost) code, and thier plasma behaviors with Internal Transport Barrier (ITB) operations are analyzed using TOTAL (Toroidal Transport Analysis Linkage) code, which clarifies the requirement of deep penetration of pellet fueling to realize steady-state advanced...

The 250 kW TRIGA Mark II research reactor of the Jožef Stefan Institute (JSI) has been in operation since 1966. The reactor went critical on 30 May 1966. It is a light water reactor, with solid fuel elements in which the zirconium hydride moderator is homogeneously distributed between enriched uranium. The reactor core consists of about 70 fuel elements, which are arranged in an annular lattice...

The study presents the analysis of reusability ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. are taken out from pressurized water reactor CANDU fuels. For this analysis, CANDU-37 having a total fission thermal power 2156 MW is considered 14 cases previous enrichment processes analysed by burning reactor. 3-D time-dependent critical burn up calculat...

Recent measurements of the positron energy spectrum obtained from inverse beta decay interactions of reactor electron antineutrinos show an excess in the 4 to 6 MeV region relative to current predictions. First-principles calculations of fission and beta decay processes within a typical pressurized water reactor core identify prominent fission daughter isotopes as a possible origin for this exc...

European Union’s (EU) (currently 27 Member States) shared-cost research has been organised in Framework Programmes (FP) of durations of 4-5 years since 1984. The 6th European Atomic Energy Community (EURATOM) Framework Programme (2002-06) and the current 7th FP (2007-11) have been allocated a fission research budget respectively of 209 and 287 Million Euro from the European Community (EC). In F...

Knowledge of fuel limits and safety margins in normal and off-normal transients in nuclear power plants remains a constant preoccupation for electricity producers and fuel manufacturers. Accurate determination of such limits, through fuel irradiation testing in the OSIRIS reactor at Saclay is closely linked to the reliability of appropriate instrumentation techniques. Two paths are currently fo...

The Generation IV Pebble Bed Modular Reactor (PBMR) is being considered as a promising concept to produce electricity or process heat with high efficiencies and unique safety features. The PBMR is a high-temperature, helium-cooled, graphite moderated reactor. The fuel elements consist of 6 cm diameter spherical graphite “pebbles” containing each thousands of uranium dioxide microspheres. As the...

Inner-side coatings have been proposed as a complementary solution within the accident tolerant fuel (ATF) framework, to provide enhanced protection for nuclear cladding. Unlike external surface, degradation of irradiated internal cladding surface has not studied extensively. Fission fragments produced during fission is one key players in this degradation. This study aimed estimate minimum thic...

Silicon carbide (SiC) is a competitive candidate material to be used in several advanced and Generation-IV nuclear reactor designs as neutron moderator, fuel coating, cladding, or core structural material. Many studies have been performed investigate the durability of SiC severe environment reactor. However, nature behavior defect induced by irradiation are still not fully understood. This pape...