Acid dissolution behavior of ferritic FeCrAl tubes candidates for nuclear fuel cladding.
نویسندگان
چکیده
The international materials community is engaged in finding safer alternatives to zirconium alloys for the cladding of fuel light water reactors. One solution replace using ferritic iron-chromium-aluminum (FeCrAl) alloys, which offer extraordinary resistance high-temperature reaction with air or steam due formation a protective alumina layer on external surface. It important characterize behavior FeCrAl not only during accident conditions but entire cycle, may include reprocessing used after it removed from power involve dissolution rods mineral acids. Little nothing known common acids, therefore objective this research was study typical tubing having two compositions (APMT and C26M) three acids (H2SO4, HNO3, HCl) as function temperature both standard ASTM immersion tests well electrochemical tests. compared capability other traditional nuclear such austenitic stainless steels (304SS 316SS) nickel (Alloy 600 Hastelloy C-276). Results show that C26M APMT have higher studied will be beneficial procedures.
منابع مشابه
Recycle of Zirconium from Used Nuclear Fuel Cladding:
Feasibility tests were initiated to determine if the zirconium in commercial used nuclear fuel (UNF) cladding can be recovered in sufficient purity to permit re-use, and if the recovery process can be operated economically. Initial tests are being performed with unirradiated, non-radioactive samples of various types of Zircaloy materials that are used in UNF cladding to develop the recovery pro...
متن کاملThermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings
The thermophysical performance and solid mechanics behavior of UO2-36.4vol % BeO fuel pellets cladded with Zircaloy, SiC, and FeCrAl, and Zircaloy cladding materials coated with SiC and FeCrAl, are investigated based on simulation results obtained by the CAMPUS code. In addition, the effect of coating thickness (0.5, 1 and 1.5 mm) on fuel performance and mechanical interaction is discussed. The...
متن کاملPhenomena Affecting Used Nuclear Fuel Cladding Temperatures during Vacuum Drying Operations
A two-dimensional computational model of a loaded used nuclear fuel canister filled with helium gas was constructed to predict the cladding temperature during vacuum drying conditions. It includes distinct regions for the fuel pellets, cladding and helium within each basket opening. Symmetry boundary conditions are employed so that only one-eighth of the package cross-section is included, and t...
متن کاملRadiation induced dissolution of UO2 based nuclear fuel – A critical review of predictive modelling approaches
Radiation induced dissolution of uranium dioxide (UO2) nuclear fuel and the consequent release of radionuclides to intruding groundwater are key-processes in the safety analysis of future deep geological repositories for spent nuclear fuel. For several decades, these processes have been studied experimentally using both spent fuel and various types of simulated spent fuels. The latter have been...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: Corrosion
سال: 2021
ISSN: ['0010-9312', '1938-159X']
DOI: https://doi.org/10.5006/3965