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Role of simulant material in nuclear reactor
1. Presentation on Seminar
"ROLE OF SIMULANT MATERIAL IN NUCLEAR REACTOR”
Submitted By: Under the guidance of:
Nikunj Patel Dr. R.K.Duchaniya
2017PMT5480 Associate Professor
Submitted to
Department of Metallurgical & Materials Engineering
Malaviya National Institute of Technology, Jaipur
2. Abstract
Corium stimulant material is very important for study of safety in
nuclear reactor. Corium’s four properties are important are melting
point,density, specific heat and thermal conductivity.
Nuclear accident occurred due to un-availibility of corium cooling
are three mile island accident, fukushima daichi accident and
Chernobyl accident.
In vessel and ex vessel are main method for cooling of corium. Ex
vessel is having three types of method which are top flooding,
bottom flooding and indirect cooling.
ZrO2,MgO and CaO are mixed in different mole percentage and
change in material properties are examined by XRD,FTIR,DTA and
SEM.
Oxidation effect in invessel cooling are examined.Sodum
borosilicate glass taken as stimulant material. It is heated upto
1200° C by thermit reacton and temperature are measured by
thermocouple at central, half radius and near wall.
CaO and B2O3 are heated at temperature of 1200°C and
temperature are measured for porous zone and solid zone.
CaO B2O3 and glass taken and its effect due to corium
volume,composition, nozzle diameter, inlet pressure are studied.
3. Corium
Corium(fuel containing material) or lava like fuel
containing material is created in nuclear reactor core
during nuclear meltdown. Corium material depends
on the design type of reactor, specifically on materials
used in control rods, coolant and reactor vessel
structural materials. It is most dangerous and most
radioactive, lava flow material in human history.
4. Corium important property
Some properties of corium is essential and that are
melting point, thermal conductivity, density and
specific heat. Role of this properties in nuclear reactor
are described below:
1. Melting point
2. Thermal conductivity
3. Density
4. Specific heat
5. Nuclear accident
Nuclear accident can be prevented by corium cooling.
Accident due to unavailibity of corium cooling are
three mile island accident, Chernobyl accident and
fukushima daichi. Corium is cooling material and cool
down nuclear reactor.
17. Oxidation effect on invessel cooling
The oxidation rate does not depend on the concentration of
the reducing agents(such as steel) in the melt, and these
concentration change with oxidation. The convection
ensures fast melt mixing accompanied by the even
distribution of temperature and component concentration
in the pool. In the experimental conditions, it leads to
transport of reducing agent to the pool surface at velocity
which is much higher than the velocity of oxidant supply.
In general case, depends on the intensity of gas convection
in the atmosphere above, chemical form of oxidant supply
can be assumed for the case of water flooding.
27. Conclusion
Corium consist of metal oxides like Zirconium dioxide(ZrO2), Indium(I)
oxide,Indium(I) hydroxide,Uranium dioxide(UO2). Corium’s four important
properties for nuclear reactor are melting point,thermal conductivity,density
and specific heat.Accident occurred due to unavalibility of corium cooling are
three mile island accident,Chernobyl accident and fukushima daichi accident.
Three cooling methods used for corium cooling are top flooding,bottom
flooding and indirect cooling. From all three methods, bottom flooding is best
technique for cooling(it takes several minutes). Melt oxidation is process
influencing condition of molten corium pool formed in reactor vessel at
bottom. Sodium borosilicate glass is used in experiment of top flooding. It
shows that water ingression occurred only upto 10 mm depth, and it do not
cool it fully.For CaO-B2O3 oxide material, top and bottom flooding is done and
it shows bottom flooding is better technique.Cooling time increase with
increase in volume. CaO-B2O3 takes 61 s and glass takes 122 s
respectively.Average quenching time for three nozzle diameter(8 mm , 12 mm
and 18 mm) are 166 s, 77 s and 81 seconds.Average cooling time increase with
decrease in pressure.