[ RadSafe ] " MIT wins $7.5M DoE grant to develop a new generation of adv...
JPreisig at aol.com
JPreisig at aol.com
Fri Sep 23 21:52:57 CDT 2011
From: _jpreisig at aol.com_ (mailto:jpreisig at aol.com)
Seems like an inherently safe advanced reactor design.
Reactor doesn't melt generally.
Have these MIT guys been reading our fast neutron reactor postings
Liquid salt (NaCl) replaces water as a moderator, and thus allows fast
neutrons to be part of the
reactor's operating scenario. More of the reactor fuel will be used up,
thus leaving less long-lived
nuclear waste??? Dr. Stanford, take note of this????
Hope this all works out.
See MIT etc. research folks are really pretty smart and motivated.
They got this research proposal
written and approved, while this type of project was only being discussed
here on radsafe.
Good work, guys.
Regards, Joseph R. (Joe) Preisig, PhD
In a message dated 9/23/2011 9:14:35 A.M. Eastern Daylight Time,
jaro_10kbq at videotron.ca writes:
MIT wins $7.5M DoE grant to develop a new generation of advanced reactors
MIT has been awarded $7.5 million as part of a new initiative by the
Department of Energy (DoE) to support research and development on the next
generation of nuclear technologies. Funded through the DoE’s Nuclear Energy
University Projects (NEUP), the Integrated Research Projects (IRPs) were
established to help ensure that the country maintains a leading role in
nuclear energy research.
The Department of Nuclear Science and Engineering and the MIT Reactor Lab
will work together with their partners at the University of California at
Berkeley (UCB) and the University of Wisconsin at Madison (UW) on the
project over the next three years to develop the path forward to a test
reactor and ultimately a commercial high-temperature salt-cooled reactor,
also called a Fluoride-salt High-Temperature Reactor (FHR).
The FHR is a new reactor concept — about a decade old. It combines
high-temperature graphite-matrix coated particle fuel developed for
high-temperature gas-cooled reactors (fuel failure temperature greater than
1600°C), liquid salt developed for the molten salt reactors (boiling point
greater than 1400°C), and safety systems originate from sodium fast
This new combination of existing technologies creates the possibility of a
large power reactor where catastrophic accidents would not be credible. The
Three Mile Island and the more recent Fukushima accident resulted from
radioactive decay heat generated after the reactors were shut down that
overheated and destroyed fuel. The FHR fuel and coolant combination may
allow decay heat to conduct to the environment without massive fuel failure
even with large-scale structural and system failures.
More on this type of NPP concept here:
You are currently subscribed to the RadSafe mailing list
Before posting a message to RadSafe be sure to have read and understood
the RadSafe rules. These can be found at:
For information on how to subscribe or unsubscribe and other settings
More information about the RadSafe