Five Euratom projects launched since 2017 in support of the development ESNII/Generation-IV reactor systems are briefly presented paper terms key objectives, results, and recommendations for future. These focus on various aspects following systems: Sodium Fast Reactor, Gas Cooled Supercritical Water Molten Salt Reactor. The does not consider EU focused Gen-IV technologies based use heavy metals...

Thermal stratification phenomena are very common in pool type reactor systems, such as the liquid-salt cooled Advanced High Temperature Reactor (AHTR) and liquid-metal cooled fast reactor systems. It is important to accurately predict the temperature and density distributions both for design optimization and accident analysis. Current reactor system analysis codes only provide lumped-volume bas...

This report documents the work completed on the X-PREX facility under NEUP Project 11-3172. This project seeks to demonstrate the viability of pebble fuel handling and reactivity control for fluoride salt-cooled high-temperature reactors (FHRs). The research results also improve the understanding of pebble motion in helium-cooled reactors, as well as the general, fundamental understanding of lo...

An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet plant availability a challenging issue assumes complex studies involving numerous neutronic analyses based on Monte Carlo simulations with MCNP code. Two different concepts are now candidates be implemented as driver for DEMO fusion reactor: WCLL (Water-Cooled Lithium L...

The high temperature gas-cooled reactor (HTGR) is a graphite moderated, helium cooled reactor with ceramiccoated fuel particles (TRISO fuel particles). The HTGR is inherently safe and expected to be applied to various industrial fields such as electric generation, hydrogen production, etc. with high efficiencies. It is also recognized as a representative advanced nuclear system for the future. ...

In power station practice, work is extracted from expanding steam in three stages namely High Pressure(HP), Intermediate Pressure(IP) and Low Pressure(LP) turbines. During the expansion process in the LP turbine, the steam cools down and at some stages, it nucleates to become a two-phase mixture. It is well-acknowledged in the literature that the nucleating and wet stages in steam turbines are ...

This paper summarizes a study of the implications of a technology-neutral regulation for advanced nuclear power plant designs and proposes a predominately rationalist approach to future nuclear plant regulations. The current body of regulations has been developed and evolved over the past 50 years with consideration of the knowledge and incidents experienced from operation of the Light Water Re...

This study (1) investigates the neutronic characteristics of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR); (2) compares the PB-AHTR neutronic performance against those of the alternative design options of He-cooled high temperature reactors using either pebble (PBMR) or prismatic (VHTR) fuel and against a liquid-salt cooled design version of the latter (LS-VHTR); (3) studies the p...

The Next Generation Nuclear Plant (NGNP) Project and the Nuclear Hydrogen Initiative (NHI) are U.S. Department of Energy programs that are responsible for the research, development, and testing of high-temperature gas-cooled nuclear reactor technologies and thermally driven hydrogen production methods. The two programs are related, in that the nuclear reactor will provide high-temperature heat,...