Abstract The primary coolant circuit of the high temperature gas-cooled reactor (HTGR) contains trace impurities. A nickel base alloy would corrode when exposed to an atmosphere at a and for long time. protective oxide scale formed by chromium is important factor prevent severe corrosion alloys. Corrosion tests were conducted on Inconel 617, Incoloy 800H, Hastelloy X, T-22, which are commonly u...

In 2018, nuclear energy generated 55% of United States’ and one third the world’s carbon free electricity, making a key tool in efforts to mitigate climate change before 2050. However, current technology, light water reactors (LWRs), is limited 300°C, so it cannot be used decarbonize industrial process heat which accounts for 12% US greenhouse gas emissions. High temperature (HTGRs) can meet hi...

This paper considers the development of a PID control strategy to optimally control the power output of a High Temperature Gas-cooled Reactor (HTGR) power plant. A specific type of HTGR called the Pebble Bed Modular Reactor (PBMR) that utilises a closed recuperative Brayton cycle with helium as working fluid is considered. The power control of this kind of plant is significantly different from ...

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 High-Temperature Gas Cooled Reactor (HTGR) Power Reactors have a layered safety system with the concept of double barrier system. However, quality assurance is required to ensure fulfillment technological analysis weightings on power chamber materials, ratings, fabrication components High- Temperature fuel elements, primary and secondary coolant pressures meet customer requirements be ...

The MCNP5 Monte Carlo code has been frequently used to model HTGRs with explicit geometric representation of fuel compacts or pebbles, including the microscopic fuel kernels within them. The random locations of fuel kernels within each fuel compact or pebble, and of pebbles within the core, however, present difficulties. A new, on-the-fly, stochastic geometry model for MCNP5 has been developed ...

In general, a nuclear core design process is divided into two subsequent phases, namely the fuel lattice phase, and followed by full phase such as for light water reactor (LWR). The optimal parameters obtained from can be used in straightforward manner since neutron mean free path much smaller than assembly dimensions. Unfortunately, above-mentioned favorable situation may not applicable high-t...