As nuclear power expands, technical, economic, political, and environmental analyses of nuclear fuel cycles by simulators increase in importance. To date, however, current tools are often fleet-based rather than discrete and restrictively licensed rather than open source. Each of these choices presents a challenge to modeling fidelity, generality, efficiency, robustness, and scientific transpar...

The local deterioration of the heat transfer at certain elevation fuel rods a water-cooled reactor may occur either in case dry-out liquid film (in BWR) or due to Departure from Nucleate Boiling (DNB, PWR). Under such conditions, sudden cladding temperature escalation take place challenging integrity material i.e., safety barrier. For reliable evaluation features nuclear under nominal accidenta...

The process for developing and qualifying nuclear fuels commercial application requires fundamental material development, characterization, design; out-of-pile testing on unirradiated materials; integral fuel rod irradiations, testing, postirradiation examinations; transient analyses. historical approach depends the generation of large empirical datasets series this ultimately takes ∼20 years—o...

Neutron imaging is an effective nondestructive testing (NDT) technique widely applied to detect structural defects and the enrichment of nuclear fuel elements due its high penetration nuclide-sensitive properties. Since element pellet sealed in cladding, transmission result a superposition two parts. Therefore, attenuation neutrons by cladding interference that must be considered analysis. It n...

2. Nuclear fuel consists of fuel pins that are stacks of uranium oxide or mixed uranium plutonium oxide (MOX) cylindrical ceramic pellets, with diameters of 8–15 mm, that are encapsulated in metallic tubes. The fuel pins are grouped together in fuel assemblies. Each fuel assembly can be handled as a single entity, thus simplifying the fuelling and defuelling of reactors and the subsequent handl...

In this study, the effective reactivity and burnup analyses have been performed for heterogeneous three-dimensional high-temperature gas-cooled thorium reactor (HTGR) which has 60 MWth full core geometry by using continuous-energy multi-purpose Monte Carlo particle transport Serpent code with ENDF/ B-VII data libraries. Nuclear fuel selected as 50 % ThO2+50% RG-PuO2. Firstly, three different qu...

Abstract A primary target towards the clean-up operation of Fukushima disaster is retrieval Molten Core-Concrete Interaction (MCCI) products, presently residing on basement damaged nuclear reactor Units 1–3. MCCI a fusion materials, composed both fuel cladding and neighbouring structural components. Determining currently unknown, physical mechanical properties essential for successful timely re...

To ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While dependences behavior single physical parameters can investigated in single- or separate-effect experiments, and more complex phenomena using integral-effect tests, an entire system as a nuclear power plant core computer code modeling. One most commonly used codes f...

Abstract The US Department of Energy is working with fuel vendors to develop accident tolerant fuels (ATF) for the current fleet light water reactors (LWRs). ATF should be more resilient loss coolant scenarios and help extending life operating LWRs. One proposed concepts use iron-chromium-aluminum (FeCrAl) alloys cladding fuel. A concern in using ferritic FeCrAl that this type may result an inc...