This paper deals with controlling of a semi-batch nonlinear reactor used for chromium sludge regeneration process. The aim is to process the largest amount of chromium filter cake (chromium sludge) in the shortest possible time. The reactor has to be cooled because of strongly exothermic process. For safety reasons the temperature should not exceed 100 °C. In this study the reactor is controlle...

► The new HTGR + MED coupling scheme was proposed. ► KAIST coupling scheme uses PCHE without any intermediate loop. ► KAIST coupling scheme has independent structure between MED and heat sink. ► Water production capacity increases by 258% compared to previous researcher's results. ► Water cost is reduced by 9.0% compared to previous researcher's results. a b s t r a c t a r t i c l e i n f o Th...

Most HWRs currently use natural uranium fuel. Using enriched uranium fuel results in a significant improvement in fuel cycle costs and uranium utilization. On the other hand, reactivity changes of HWRs over the full range of operating conditions from cold shutdown to full power are small. This reduces the required reactivity worth of control devices and minimizes local flux distribution perturb...

This report presents a design concept for a high-capacity decay-heat removal system for the molten-salt cooled Advanced High Temperature Reactor (AHTR) [1]. The design is closely derived from the General Electric S-PRISM reactor, which is a sodium pooltype reactor [2]. The AHTR is distinguished from the S-PRISM by its use of a hightemperature thermal blanket, shown in Fig.1, that allows the ves...

The development and deployment of gas-cooled reactors (GCRs) require flexible modelling simulation tools for a detailed understanding the system behavior in normal operation accidental scenarios. Amongst identified safety-relevant scenarios reactors, outlet plenum flow distribution during operations was ranked to be high importance with low knowledge level phenomenon identification ranking tabl...

The Experimental Breeder Reactor-II (EBR-II) was a 62.5 MWt±20 MWe sodium cooled fast reactor that was operated successfully for 30 years. Over its period of operation a wealth of fuels and materials information originated from EBR-II. Several missions were conducted in EBR-II, all of which yielded new and valuable additions to the world's knowledge base for nuclear materials. Some of the ®rst ...

The paper reports results of MCNP-5 calculations to assess the effect on the Tritium Breeding Ratio (TBR) when integrating a distributed Ion Cyclotron Range of Frequencies (ICRF) antenna in the blanket of DEMO fusion power reactor. The calculations consider different parameters such as the ICRF covering ratio and the type of breeding blanket including the Helium Cooled Pebble Bed (HCPB) and the...