Kevin R Robb

TL;DR: In this paper, the impact of fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions was analyzed. But the authors focused on the impact on the nuclear power station's fuel performance.

TL;DR: In response to the accident at the Fukushima Daiichi nuclear power station in Japan, the U.S. Nuclear Regulatory Commission (NRC) and Department of Energy agreed to jointly sponsor an accident reconstruction study as a means of assessing severe accident modeling capability of the MELCOR code as mentioned in this paper.

TL;DR: Fluoride salt-cooled high-temperature Reactors (FHRs) are an emerging reactor class with potentially advantageous performance characteristics, and fully passive safety as mentioned in this paper, and the development path needed to address the challenges.

TL;DR: In this paper, simple scoping models that can be used to evaluate ATF performance under severe accident conditions have been developed The methodology provides a fundamental technical basis (aka metric) based on the thermodynamic boundary for evaluating performance relative to that of traditional Zr-based claddings.

TL;DR: In this article, an experimental facility is described to support the development of the fluoride-salt-cooled high-temperature reactor concept, which is capable of operating at up to 700°C and incorporates a centrifugal pump to circulate FLiNaK salt through a removable test section.