Zr–Sn–Nb–Fe–Si–O alloy for fuel cladding candidate: Processing, microstructure, corrosion resistance and tensile behavior

2015 ◽  
Vol 100 ◽  
pp. 332-340 ◽  
Author(s):  
Liangyu Chen ◽  
Jiuxiao Li ◽  
Yao Zhang ◽  
Lai-Chang Zhang ◽  
Weijie Lu ◽  
...  
Keyword(s):  
Corrosion Resistance ◽  
Tensile Behavior ◽  
Fuel Cladding

scholarly journals Investigation of Corrosion Resistance of Alloys with Potential Application in Supercritical Water-cooled Nuclear Reactors

2019 ◽  
Vol 63 (2) ◽  
pp. 328-332 ◽  
Author(s):  
Ákos Horváth ◽  
Attila R. Imre ◽  
György Jákli
Keyword(s):  
Corrosion Resistance ◽  
Supercritical Water ◽  
Power Plants ◽  
Fuel Cladding ◽  
Pressurized Water ◽  
Water Reactors ◽  
Reactor Types ◽  
Materials Used ◽  
Supercritical Water Cooled Reactor ◽  
Nuclear Applications

The Supercritical Water Cooled Reactor (SCWR) is one of the Generation IV reactor types, which has improved safety and economics, compared to the present fleet of pressurized water reactors. For nuclear applications, most of the traditional materials used for power plants are not applicable, therefore new types of materials have to be developed. For this purpose corrosion tests were designed and performed in a supercritical pressure autoclave in order to get data for the design of an in-pile high temperature and high-pressure corrosion loop. Here, we are presenting some results, related to corrosion resistance of some potential structural and fuel cladding materials.

scholarly journals Microstructure and Tensile Behavior of Powder Metallurgy FeCrAl Accident Tolerant Fuel Cladding

2022 ◽  
pp. 153524
Author(s):  
Shenyan Huang ◽  
Evan Dolley ◽  
Ke An ◽  
Dunji Yu ◽  
Cole Crawford ◽  
...  
Keyword(s):  
Powder Metallurgy ◽  
Tensile Behavior ◽  
Fuel Cladding

scholarly journals Effect of chemical composition on corrosion resistance of zircaloy fuel cladding tube for BWR.

1990 ◽  
Vol 32 (7) ◽  
pp. 728-740
Author(s):  
Masahisa INAGAKI ◽  
Kimihiko AKAHORI ◽  
Jirou KUNIYA ◽  
Isao MASAOKA ◽  
Masateru SUWA ◽  
...  
Keyword(s):  
Corrosion Resistance ◽  
Chemical Composition ◽  
Fuel Cladding

scholarly journals Assessment of Corrosion Resistance of Candidate Alloys for Accident Tolerant Fuel Cladding under Reactor Conditions

2017 ◽  
Vol 23 (S1) ◽  
pp. 2226-2227
Author(s):  
Slavica Grdanovska ◽  
Peng Wang ◽  
Gary Was ◽  
David Battels
Keyword(s):  
Corrosion Resistance ◽  
Fuel Cladding

Effect of Annealing Conditions on the Microstructure and Corrosion Characteristics of Zr-xNb Alloys

2006 ◽  
Vol 118 ◽  
pp. 77-82 ◽  
Author(s):  
Hyun Gil Kim ◽  
Yong Hwan Jeong
Keyword(s):  
Corrosion Resistance ◽  
Systematic Investigation ◽  
Annealing Condition ◽  
Fuel Cladding ◽  
Corrosion Rates ◽  
Annealing Conditions ◽  
The Matrix ◽  
Nb Content ◽  
Soluble State ◽  
Zr Alloys

Most of the advanced Zr-based alloys contain Nb for improving the corrosion resistance. However, the Nb effect on the corrosion behavior of Zr alloys has not been established. For developing fuel cladding materials, it is essential to investigate the effect of the Nb-content and annealing conditions after beta quenching on the microstructure and the corrosion of Zr-xNb alloys. In this study, a systematic investigation to obtain the optimized annealing condition and Nb content were performed for Zr-xNb alloys (x = 0.1~2.0 wt.%). The corrosion resistance of 0.1 and 0.2 wt.% Nb alloys where Nb existed in an equilibrium soluble state in the matrix was excellent in the quenched and annealed conditions. For the high Nb-containing alloys, the corrosion rates were very sensitive to the annealing condition, and it took about 50 hours at 570 to reach the corrosion rates comparable to those of the low Nb wt.% alloys. The corrosion resistance was closely related to the stabilization of the tetragonal ZrO2 and the columnar oxide structure when the Nb concentration in the matrix was reduced to the equilibrium soluble limit.

The Main Changes and Consequences by Burnup Extensions in PWRs: Some Recommendations for Negative Plant Performance Issue Limitations

2008 ◽  
Author(s):  
Ivan D. Dobrevski ◽  
Neli N. Zaharieva
Keyword(s):  
Corrosion Resistance ◽  
Boric Acid ◽  
Nuclear Fuel ◽  
Nucleate Boiling ◽  
Plant Performance ◽  
Water Radiolysis ◽  
Fuel Cladding ◽  
Pressurized Water ◽  
Nuclear Fuel Cladding ◽  
The Creation

The higher duty cores are always attended with the onset of sub-cooled nucleate boiling (SNB) on the fuel cladding surfaces and the initial excess reactivity of core. The impacts of these factors on the chemical environments of the nuclear fuel cladding- and reactor coolant system- surfaces are discussed: The SNB at the cladding surfaces strongly influences the behavior of gases dissolved in cladding water layer phase, causing their stripping out which will favor the creation of oxidizing conditions. It is considered that the creation of oxidizing conditions in the nuclear fuel cladding environment is not a direct boiling consequence but it is a result of the synergic impact of the boiling- and water radiolysis- processes on the Pressurized Water Reactor fuel cladding surface areas. This requires new criteria for corrosion resistance properties of fuel cladding materials. These materials must have high corrosion resistance to oxidizing conditions. If only boric acid as neutron absorber is implemented, the critical boron concentration in coolant increases significantly when implementing an extended fuel cycle. This effect can be limited through application of 10B enriched boric acid or by application of such solid burnable absorbers as Gd2O3 integrated in UO2 fuel. Some recommendations to address negative plant performance issues are given in addition to the results of these investigations.

Improvement in the hydrothermal corrosion resistance of Ti-based nitride coatings by adding Cr for accident tolerant fuel cladding applications

2021 ◽  
Vol 549 ◽  
pp. 152903
Author(s):  
Arang Do ◽  
Daejong Kim ◽  
Heon-Jin Choi ◽  
Sung-Woo Kim ◽  
Sang-Yeob Lim ◽  
...  
Keyword(s):  
Corrosion Resistance ◽  
Fuel Cladding ◽  
Nitride Coatings

Microstructures of Ti-1.5 w/o Ni Alloys with Mo and A1 Additions

1975 ◽  
Vol 33 ◽  
pp. 54-55
Author(s):  
Anna C. Fraker
Keyword(s):  
Corrosion Resistance ◽  
Beneficial Effect ◽  
Crevice Corrosion ◽  
Local Corrosion ◽  
Precipitate Size ◽  
Ni Alloys

Small amounts of nickel are added to titanium to improve the crevice corrosion resistance but this results in an alloy which has sheet fabrication difficulties and is subject to the formation of large Ti2Ni precipitates. These large precipitates can serve as local corrosion sites; but in a smaller more widely dispersed form, they can have a beneficial effect on crevice corrosion resistance. The purpose of the present work is to show that the addition of a small amount of Mo to the Ti-1.5Ni alloy reduces the Ti2Ni precipitate size and produces a more elongated grained microstructure. It has recently been reported that small additions of Mo to Ti-0.8 to lw/o Ni alloys produce good crevice corrosion resistance and improved fabrication properties.

Sign in / Sign up

Export Citation Format

Share Document