The possible deployment of Accident Tolerant Fuels (ATF) for currently-operating Light Water Reactors (LWR) has prompted interest in the use Studsvik’s CMS5 code system to support analysis such advanced ATF core designs. Various concepts have been proposed; example, uranium silicide (U 3 Si 2 ) fuel, together with iron-based (FeCrAl) cladding. purpose this work is showcase application system, w...

Nuclear power remains a contentious issue for many. Its proponents point towards it being a cost-competitive, feasible route for meeting our ever growing appetite for energy, with relatively low greenhouse gas emissions (Nature Mater. 7, 679; 2008). Those against a nuclear-led energy policy cite concerns over the devastating impact a nuclear incident can have, as well as the complex scientific ...

The utilization of clean energy is a matter of primary importance for sustainable development as well as a vital approach for solving worldwide energy-related issues. If the low utilization rate of nuclear fuel, nuclear proliferation, and insufficient nuclear safety can be solved, nuclear fission energy could be used as a sustainable and low-carbon clean energy form for thousands of years, prov...

BISON finite element method fuel performance simulations were conducted using an existing automated process that couples the Fuels Irradiation & Physics Database (FIPD) and Integral Fast Reactor Materials Information System database by writing input files comparing output to post-irradiation pin profilometry measurements contained within databases. The importance of this work is demonstrate...

Fuel cladding and structural components made of zirconium alloys, used in light heavy water nuclear reactors, exhibit, during normal operation, significant in-reactor deformation. Fast Fourier Transform (FFT) simulations have been conducted on large grain aggregates to simulate the behavior recrystallized Zircaloy-4. Original constitutive equations proposed account, at microscopic scale, for th...

Abstract The diffusivity values of C in pure Zr and containing dissolved O (Zr(O)) were determined a temperature range 623–1023 K for 923–1123 Zr(O) from depth profiles obtained by glow-discharge emission spectroscopy. decreased as the concentration increased that 15 at % was two orders magnitude smaller than Zr. One-dimensional numerical calculations Fick’s diffusion equation with Soret effect...