I want to know about the fuel rod which is cladding of zirconium alloy can be covered by other material. if so, will its reaction distrubs the reactor or not.
The nuclear fuel cladding coating systems must have a number of essential properties: adherence to the substrate, thermal stability to high temperature with maximum oxidation resistance, resistance to scratching/gauging and resistance to radiation damage.
The selection of the coating materials is based on the neutron cross-section, thermal conductivity, thermal expansion, melting point, phase transformation behavior, and high-temperature oxidation rate.
One of the cladding concepts under development is zirconium alloys coatings: cromium thin layer or MAX phase coatings having good thermal and electrical conductivity, as well as good corrosion resistance and the good mechanical properties maintained at high temperature.
See refferences:
http://www-pub.iaea.org/MTCD/Publications/PDF/TE1797web.pdf
https://www.kns.org/kns_files/kns/file/13F-04A-2A-%b1%e8%c7%f6%b1%e6.pdf
http://www.mne.psu.edu/motta/Publications/129_Alat_SCT_2015.pdf
http://www.mne.psu.edu/motta/Publications/135_Alat_JNM_2016.pdf
Florian Glodeanu @ Thanks for the everything.
I would like to know that any material used on fuel cladding as per your suggestion and literature will or will not disturb the volatile radioactive elements of reactor such as Iodine cesium, Tellurides, Krypton, Xenon etc. inside the fuel rod.
Zr+ 2H2O --- Zro2 +2H2
this reaction takes place when fuel rod cracks generated. If the material for coating so used which cannot form the hydrogen and having all such properties as you suggested will be work the system to avoid the accident or not.
Hoping for your valuable suggestions.
In the previous comment, I referred to the coatings of the outer surface of the fuel elements tears to increase the oxidation resistance.
The coating of the inner surface of the fuel elements cladding is used known in CANDU fuel technology as CANLUB. The purpose of the CANLUB layer is to mitigate stress-corrosion cracking of the sheath following a power ramp. Post-irradiation examination (PIE) has shown that fuel incorporating CANLUB coatings has less oxidation on the inside sheath surface than uncoated fuel. It appears that the CANLUB layer prevents the Zircaloy sheath from being oxidized. One possibility is that the fission-liberated oxygen in CANLUB-coated fuel remains in the U02 and diffuses along the thermal gradient.
See references:
https://www.nrc.gov/docs/ML0334/ML033450496.pdf
http://www.nuclearresearch.ca/uploads/files/Kommy%20CNS%20Fuel%202013.pdf
http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/11/536/11536159.pdf
@ Florian Glodeanu: Thank you sir.
The coating using Microreactor assisted Nanomaterial deposition (MAND) Techniques (introduced by Brail K. Paul & Choi et al.) which is advanced method of CBD/CVD. This coating control various parameters such as densities, pore sizes, hydrophillic & superhydrophillic surfaces, control on reaction in chemitries, etc. If this coating does on fuel rod with high thermal conductivity, low - oxidation and high resistance material will improve the augmentation of heat transfer on fuel rod which can save the crack in fuel rod during cooling.
Suggest me. If I where wrong on above comment.
For nanomaterials research in nuclear energy see references:
https://www.nature.com/articles/srep3347
https://www.researchgate.net/publication/273927083_Nanomaterials_and_nanotechnologies_in_nuclear_energy_chemistry
https://www.energy.gov/sites/prod/files/2015/08/f25/NEET-Reactor%20Materials%20Newsletter%20-%20Issue%201.pdf
Article Nanomaterials and nanotechnologies in nuclear energy chemistry
@ Florian Glodeanu:
Sir,
https://www.nature.com/articles/srep3347
something is missing in this web address. I had tried lot by changing the last digit but didn't find the exact paper and if i continue with the same link page not found message will appear. Will you send this link once again or just give the title of the paper.
Awaiting for kind cooperation.
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