Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology

RO Scarlat, MR Laufer, ED Blandford… - Progress in Nuclear …, 2014 - Elsevier
Abstract Fluoride-salt-cooled, high-temperature reactor (FHR) technology combines the
robust coated-particle fuel of high-temperature, gas-cooled reactors with the single phase …

Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs)

N Zweibaum, G Cao, AT Cisneros, B Kelleher… - Progress in Nuclear …, 2014 - Elsevier
Due to their combination of high-temperature coated-particle fuel, molten salt coolant and
related materials requirements, fluoride-salt-cooled, high-temperature reactors (FHRs) …

Corrosion of Incoloy 800H alloys with nickel cladding in FLiNaK salts at 850 C

Q Dai, XX Ye, H Ai, S Chen, L Jiang, J Liang, K Yu… - Corrosion …, 2018 - Elsevier
The corrosion of 800H alloy with and without Ni-cladding, as well as GH3535 alloy, in
molten FLiNaK salts at 850° C has been investigated. Results show that Cr and Fe are …

[图书][B] Experimental validation of passive safety system models: Application to design and optimization of fluoride-salt-cooled, high-temperature reactors

N Zweibaum - 2015 - search.proquest.com
The development of advanced nuclear reactor technology requires understanding of
complex, integrated systems that exhibit novel phenomenology under normal and accident …

Molten salt reactor salt processing–technology status

GL Fredrickson, G Cao, R Gakhar, TS Yoo - 2018 - osti.gov
This report presents a summary of 752 citations related to molten salt reactor development at
Oak Ridge National Laboratory (ORNL). This effort was initiated with a focused purpose of …

[PDF][PDF] Technical Description of the “Mark 1” Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant

AT Cisneros, JK Choi, AY Chong, M Fratoni, S Hong - Tech. Rep., 2014 - researchgate.net
This report describes the results of work at the University of California, Berkeley (UCB) to
develop an initial pre-conceptual design for a small, modular 236-MWth pebble-bed …

Functional Requirements for the Modeling and Simulation of Advanced (Non-LWR) Reactor Mechanistic Source Term

S Shahbazi, D Grabaskas - 2020 - osti.gov
A number of industry vendors are leading a resurgence in advanced reactor development.
As the assurance of public safety from the accidental release of radionuclides to the …

[PDF][PDF] Design of the Mark-1 pebble-bed, fluoride-salt-cooled, high-temperature reactor commercial power plant

DL Krumwiede, C Andreades, JK Choi… - Proc. of ICAPP …, 2014 - arfc.npre.illinois.edu
DESIGN OF THE MARK-I PEBBLE-BED, FLUORIDE-SALT-COOLED,
HIGHTEMPERATURE REACTOR COMMERCIAL POWER PLANT Page 1 Proceedings of …

[PDF][PDF] Survey and Assessment of Computational Capabilities for Advanced (non-LWR) Reactor Mechanistic Source Term Analysis

S Shahbazi, D Grabaskas, S Thomas, N Andrews… - 2020 - osti.gov
A vital part of the licensing process for advanced (non-LWR) nuclear reactor developers in
the United States is the assessment of the reactor's source term, ie, the potential release of …

[PDF][PDF] The effects of variations in lithium (7li) and uranium (235u) isotope levels on a small fluoride salt-cooled, high-temperature reactor with uo2 fuel pins

H Mohamed, GT Parks - Journal of Nuclear And Related Technologies, 2017 - jnrtmns.net
ABSTRACT Lithium, beryllium, fluoride, FLiBe (66.7 mole% LiF and 33.3 mole% BeFfl has
become the baseline coolant, for fluoride sail-cooled high-tempendure reactors (FHRs) …