SuperCritical
Water- cooled nuclear reactors are a 4th generation reactors that
use light water coolant at temperature higher than its critical level. Uniform
and non-uniform axial heat flux profiles applied with a range of alternative
fuels such as thorium dioxide, uranium dicarbide, uranium nitride etc.
There are two
reactor basic arrangements for SuperCritical Water cooled Nuclear Reactors(SCWRs)-A
fuel was deemed fit it the fuel centerline temperature remained lower than
1850oC.
Uranium dioxide was the main choice for its wide and traditional use as
a nuclear fuel. Although several studies have concluded that fuel centerline temperature
can significantly exceed the industry acceptable limit. Unconventional fuels
like mixed oxide, thoria, uranium dicarbide, uranium nitride and uranium carbide.
Uniform and non-uniform axial heat flux profiles were applied, non-uniform
profiles included- upstream cosine, cosine and downstream cosine. The sheath
materials chosen were Inconel 600, Inconel 718 and stainless steel 304. A
shielding material is acceptable if the outer sheath temperature is below
850oC.
SCWR is using
SuperCritical Water as a reactor coolant. It is a light water and above its critical
point. Various fossil fuel based plants are using this water as a working fluid
for the turbine. Major thermodynamic cycle options for direct cycles SCWR are
with no-reheat and single reheat. Direct cycles are allowed with increased
coolant factors such as high temperature and pressure. The no-reheat cycle SCW
exits the channel and enters into the turbine. The single reheat cycle is
obtained by using Steam-Reheat channels.
Significance of
Sheath materials
Sheath material is
suitable for SCWR use if the temperature remains below the design limit specified
at 850oC. The main choice for sheath material is zirconium alloy for its high
mechanical strength and outstanding neutron transparency. Although when the
temperature increases to 500oC, it is steeply corroded. Therefore zirconium
alloy is unfit as a sheath material because the coolant temperature vary from
350oC to 625oC.
Other sheath
materials are- alloy Inconel 600, Inconel 71 and stainless steel 304. Inconel alloys
are nickel based high temperature materials offering high mechanical strength,
hot and cold workability and supreme corrosion resistance. With increase in
temperature above 750oC, alloy 718 attains significant reduction in its yield
stress and tensile strength. Stainless steel 304 is selected for offering good
corrosion resistance but its structural strength is very low and wall thickness
needs considerable increase. It is not fit as the thermal efficiency and
neutron economy would be significantly reduced. Following the review, Inconel
600 is the main sheath material.
For fuel supply,
MOX is the perfect option as it is developed from irradiated UO2 and Thoria is special
because it is a non-uranium based fuel. The fuel centerline temperature
industry limit goes beyond only by MOX fuel. To make this fuel suitable for
advanced reactors, fuel bundle design changes are required or channel power
should be reduced. Thoria, uranium nitride and uranium carbide are possible
SCWR nuclear fuels because their fuel centerline temperatures remain lower than
850oC. Thoria offers an additional benefit due to reduced dependence on uranium
reserves.