Suggested
research topics for molten salt reactors
The following is a partial list
of research topics that could have a substantial improvement in the prospects
for a commercially viable product.
Thermostat negative temperature
control. The point
of this topic is to end up with a strong negative temperature coefficient
even at high temperatures and with low fission product burden.
neutron poison rods are actuated
by temperature response
need to develop a design that
is compatible chemically and good for neutron economy and for waste management
All carbon composite
primary system. The point of this research idea is to be able to
operate at high enough temperature (~900°C) for a direct cycle gas turbine
or (~1050°C) to make hydrogen by thermo chemical water splitting cycle.
We are speaking of vessel, piping, pumps and heat exchangers.
allows higher temperature
avoid corrosion of metal alloys
better tritium control with
SiC layer
can SiC be used to improve
the neutron damage characteristics of graphite? The problem is thermal
stresses and de-bonding due to differential thermal expansion
Alternative salt formulations.
The point of this research is to avoid the problems listed below with Li and
Be.
Li results in tritium production
and lithium µ is expensive
Be is expensive and hazardous
to work with due to inhalation toxicity. Look at NaF, ZrF4,
look at solubility enhancement, corrosion, neutron loss.
Safeguard and non proliferation
analyses in use of Th-U-233 cycle.
The point of this topic is to understand proliferation issues.
make most or all of fuel once
started up (CR~1)
maybe start up on reactor
minor actinides (Pu and higher); get credit for taking on this material
rather than paying for enriched U
Centrifuge for noble and
semi-noble metal separations. The
point of this work is to improve the outlook for extraction and handling of
the precipitating fission products to enhance waste management strategies.
base on continuous flow contactor
incorporate into pump
Waste form and assay study.
This topic emphasizes waste management, a vital aspect of nuclear energy.
estimate assay (carry over
of actinides) with each class of waste, e.g., gaseous, noble and semi-noble
metals and valence two and three products with reductive extraction. Consider
Bi carry over and resulting Po-210.
waste form: fluoride for interim
and substitute fluorapatite for permanent storage
Plant description, size,
undergrounding, cost, systems. Economic considerations are important
motivators to develop this new nuclear power system.
change out time for graphite
vs. core size
salt formulation
underground design considerations
cost analysis preliminaries
power conversion cycle
System assessment along
lines of NERI-2002 proposal. What
is known about the molten salt reactor is decades old. Bringing up to date
the database is vital to resurrecting the molten salt reactor development.