The breeding blanket with integrated first wall (FW) is the key nuclear component for power
extraction, tritium fuel sustainability, and radiation shielding in fusion reactors. The ITER …

In this paper, we review the thermal plasma confinement and transport properties observed
and predicted in low aspect ratio tokamaks, or spherical tokamaks (STs), which can depart …

The tritium aspects of the DT fuel cycle embody some of the most challenging feasibility and
attractiveness issues in the development of fusion systems. The review and analyses in this …

A fusion nuclear science facility (FNSF) could play an important role in the development of
fusion energy by providing the nuclear environment needed to develop fusion materials and …

The objective of the ITER TBM Program is to provide the first experimental data on the
performance of the breeding blankets in the integrated fusion nuclear environment. Such …

Abstract The Fusion Nuclear Science Facility (FNSF) is examined here as part of a two step
program from ITER to commercial power plants. This first step is considered mandatory to …

The purpose of this paper is to critically review the testing and qualification strategy for the
DEMO breeding blanket in Europe, identifying the potential risks and weaknesses and …

This paper presents the results of a multi-system codes benchmarking study of the recently
published China Fusion Engineering Test Reactor (CFETR) pre-conceptual design (Wan et …

Recent experiments (Synakowski et al 2004 Nucl. Fusion 43 1648, Lloyd et al 2004 Plasma
Phys. Control. Fusion 46 B477) on the Spherical Tokamak (or Spherical Torus, ST)(Peng …

The DCLL is an attractive breeding blanket concept that leads to a high-temperature (T∼
700° C), high thermal efficiency (η> 40%) blanket system. The key element of the concept is …