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A Near-Term-Deployable Salt-Cooled Advanced Nuclear Reactor
Huali Wu, Francesco Carotti, Michael Young, Mohamed Abou Dbai, Raluca O. Scarlat
Department of Engineering Physics, Nuclear Engineering
http://heatandmass.ep.wisc.edu/
ABSTRACT KEY SYSTEM COMPONENTS
THE INTEGRATED RESEARCH PROJECTSRESEARCH FOCUS I:
TRITIUM TRANSPORTRESEARCH FOCUS II:
FREEZING TRANSIENTS
EXTERNAL LINKS
PREVIOUS EXPERIENCES
The Fluoride-Salt-Cooled High-Temperature
Reactor (FHR) is an advanced nuclear reactor
concept that combines high temperature
fluoride salt coolants with solid fuel elements
containing ceramic fuel micro particles and a
Nuclear Air-Brayton Combined Cycle (NACC).
NACC allows for base-load, power peaking
with natural gas, and heat processing
applications.
Tritium control is important in FHR design
because Tritium is created from neutron
irradiation of molten salt and it will permeate
through metal at FHR operation temperature.
Another focus of our research regards the
freezing and overcooling transients of fluoride
salt, in which the coolant solidifies or becomes
highly viscous as it approaches freezing
around 459ºC.
Adapted from (UCBTH-12-003, 2013)
LARGE TRITIUM PRODUCTION
Tritium is produced by neutron
irradiation with Li and Be in FHR
coolant, and it produces 1,000 to
10,000 times more tritium than a PWR.
TO WHAT EXTENT CAN GRAPHITE FUEL BE AN EFFECTIVE AND
REMOVABLE TRITIUM SINK IN THE FHR?
SYSTEM TRANSPORT
Tritium is produced in the core,
absorbed on graphite, and may leak
to air through metallic heat
exchangers
(Atsumi, 2011)
DIFFUSION MECHANISM IN GRAPHITE
Tritium diffuses through open pores
and could be trapped on crystalline
surfaces.
INCREASED RETENTION WITH IRRADIATION
Neutron irradiation will increase tritium
retention in graphite.(Atsumi, 2009)
Heat and Mass Transport Group – UW-Madison
HEATandMASS.ep.wisc.edu
UC-Berkeley FHR Website
FHR.nuc.berkeley.edu
Energy from Thorium
energyfromthorium.com
Oak Ridge National
Laboratory FHR Websitehttp://www.ornl.gov/science-discovery/nuclear-science/research-
areas/reactor-technology/advanced-reactor-concepts/fluoride-salt-
cooled-high-temperature-reactors
International Thorium Energy
Organization
www.itheo.org
In 2011, Department of Energy (DOE) initiated a 3 year Integrated
Research Project (IRP I) involving universities (University of
Wisconsin-Madison, University of California-Berkeley and MIT) and
National lab (ORNL) to develop the technical basis to design,
develop, and license a commercially attractive FHR.
The new project (IRP II), supported by DOE starting in 2015,
involving more universities and resources, shows the intention to
pursue the development of FHR as a safe future source of energy.
NON-EQUILIBRIUM FREEZING SUPER-
COOLING PHENOMENON
Cooling rate, nucleation sites and
purity of the salt also affects freezing
phenomena
HOW DOES THE FREEZING AFFECT THE FLOW IN A PIPE AND IN THE
NATURAL CIRCULATION SYSTEM?
FREEZING POINT
Freezes at 459ºC and FHRs operate in the temperature range of
600ºC to 700ºC, and the ultimate heat sink is ambient air or water
(Kelleher, 2014)
EQUILIBRIUM FREEZING PHASE
DIAGRAM
Freezing temperature and
phenomenology depends on
composition
(Romberger, 1972)
2 - A COMPACT HIGH-
TEMPERATURE, LOW-PRESSURE
CORE
3 - UNIQUE PROPERTIES OF FLUORIDE
MOLTEN SALT AS A HEAT TRANSFER FLUID 4 – PASSIVE SAFETY SYSTEMS RELY
ON NATURAL CIRCUALTION COOLING
5- COMMERICIALLY
AVAILABLE TECHNOLOGIES
AND EASY TO COUPLE WITH
OTHER ENERGY SOURCES
• Micro-particles encapsulate fuel with low
failure rates up to 1600oC.
• Graphite pebble fuel elements host the
micro-particles, and provide accident
scenario temperatures < 1000oC.
• This fuel technology has been
developed for gas-cooled reactors since
1960s.
• Heterogeneous mixed pebble-bed in
an annular core design
• High thermal density (23 MW/m3) of
the core and low pressures allows the
core to be smaller and cheaper.
• Flibe (2LiF-BeF2) as a coolant of the
reactor.
• Unique heat transfer properties.
• Limited corrosion and low vapor
pressure.
• Good neutron physics behavior inside
the reactor.
• Successfully used during Molten Salt
Rector Experiment (1960s-1970s)
• Challenges connected to its toxicity,
tritium generation, and its high freezing
point (459ºC).
• Coolant properties enable inherent
safety features of the FHR design.
• High operating temperatures, 600-
700ºC, allowing high thermal
efficiency (42% at baseload and
65% peaking; compared to 34%
conventional nuclear).
• Natural gas co-firing enables
power peaking, opening a new
part of the electricity market for
nuclear plants.
• Natural circulation cooling systems (“DRACS”) rely
on buoyancy as the driving force.
• A fluidic diode is used to restrict parasitic flow during
normal operation of the reactor and to passively
activate natural circulation upon pump failure.
• DRACS were demonstrated for liquid-metal cooled
reactors (since 1960s), and they are more compact
for salts due to more effective coolant properties.
1 - A ROBUST FUEL DESIGN
3.5 m vessel diameter (rail transportable)
The Pebble Bed Fluoride-Salt Cooled, High-Temperature Reactor (PB-FHR)
236 MWth
100 MWe base-load
242 MWe peaking
Molten Salt Reactor
Experiment (MSRE)
ORNL (1960s) - Power
reactor using molten salt
technology successfully
operated for 5 years.
Aircraft Reactor Experiment
(1946-1961) – High power
density reactor designed to
be placed inside an aircraft
to power the turbines.
Very High Temperature
Reactors (VHTR)
introduced the concept
of pebble-bed core
design.
(ORNL/TM-2009/181,2010)
(Stacy, Susan M, INL)
(Stefan Kühn, Deutschland)
(Kelleher, 2013)
(UCBTH-14-002, 2014)
(UCBTH-14-002, 2014)
(UCBTH-14-002, 2014)
(UCBTH-14-002, 2014)
(UCBTH-14-002, 2014)
April 9th 2015