Nuclear and Burn-Up Characteristics of small molten-salt power rector.
نویسندگان
چکیده
منابع مشابه
Molten-salt Reactor Chemistry
This document summarizes the large program of chemical research and development which led to selection of fuel and coolant compositions for the Molten-Salt Reactor Experiment (MSRE) and for subsequent reactors of this type. Chemical behavior of the LiF-BeFrZrFrUF4 fuel mixture and behavior of fission products during power operation of MSRE are presented. A discussion of the chemical reactions w...
متن کاملDemand driven salt clean-up in a molten salt fast reactor – Defining a priority list
The PUREX technology based on aqueous processes is currently the leading reprocessing technology in nuclear energy systems. It seems to be the most developed and established process for light water reactor fuel and the use of solid fuel. However, demand driven development of the nuclear system opens the way to liquid fuelled reactors, and disruptive technology development through the applicatio...
متن کاملLOW TEMPERATURE MOLTEN SALT SYNTHESIS OF NANO CRYSTALLINE MgAl2O4 POWDER
Abstract: composition of MgO and nano boehmite. The reactant and potassium chloride, as the reaction media, were fired at800-1000 °C at different dwell times (0.5-5 h) in the ambient atmosphere. After washing and filtration, the spinel nanopowder was characterized by X-ray diffraction (XRD), Scanning electron microscopy (SEM), and Brunauer-Emmett-Teller (BET) techniques. It was demonstrated tha...
متن کاملThe Molten Salt Reactor Adventure
A personal history of the development of molten-salt reactors in the United States is presented. The initial goal was an aircraft propulsion reactor, and a molten fluoride-fueled Aircraft Reactor Experiment was operated at Oak Ridge National Laboratory in 1954. In 1956, the objective shifted to civilian nuclear power, and reactor concepts were developed using a circulating UF4-ThF4 fuel, graphi...
متن کاملMolten-salt Reactors—history, Status, and Potential
Molten-salt breeder reactors (MSBR's) are being developed by the Oak Ridge National Laboratory for generating low-cost power while extending the nation's resources of fissionable fuel. The fluid fuel in these reactors, consisting of UF4 and ThF4 dissolved in fluorides of beryllium and lithium, is circulated through a reactor core moderated by graphite. Technology developments over the past 20 y...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
سال: 1990
ISSN: 0004-7120
DOI: 10.3327/jaesj.32.377