Procedure for Conducting Breakaway Oxidation Tests with Zirconium-based Cladding Alloys
ثبت نشده
چکیده
4. Sample Preparation and Characterization 7 4.1 Hydrogen-content determination for as-fabricated samples 7 4.2 Minimum sample lengths for oneand two-sided oxidation tests 7 4.3 End-cap mass and welding procedure for one-sided oxidation test samples 7 4.4 Length, outer diameter, and wall thickness measurements 7 4.5 Pre-test cleaning with chemical detergent or organic solvent and rinsing 8 4.6 Pre-test sample weight measurement (after drying) 8
منابع مشابه
Crystal Structure of the ZrO Phase at Zirconium/Zirconium Oxide Interfaces**
Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and structural components. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency, is water corrosion. This oxidation process has recently been linked to the presence of a sub-oxide phase with well-defined composition but unkno...
متن کاملMicrostructure and Mechanical Strength of Surface Ods Treated Zircaloy-4 Sheet Using Laser Beam Scanning
Zirconium alloys have been used as a fuel cladding material for a long time because they have good corrosion resistance and irradiation stability in a reactor environment. However, it was recognized that the severe oxidation and creep ballooning behaviors of zirconium alloy cladding tubes at an accident condition of a nuclear reactor have to be considered to improve nuclear plant safety after t...
متن کاملUse of Secondary Ions Mass Spectrometry (SIMS) for Cladding Materials Post- Irradiation Examination (PIE)
Zirconium-based alloys are widely used in the field of nuclear industry as cladding for nuclear fuel in power plants. In a pressurized water reactor (PWR), boric acid is added in the coolant for reactivity control. Lithium hydroxide is added to render the coolant slightly alkaline, which helps to inhibit corrosion product deposition on the fuel cladding and reduces the corrosion rate of structu...
متن کاملRecycle 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 کاملModeling of Zircaloy cladding primary creep during load drop and reversal
Modeling fuel behavior requires an accurate description of the cladding stress response for both operational and safety considerations. The transient creep response of Zirconium alloys is commonly modeled using a strain hardening rule which is known to hold in cases with monotonously increasing stresses. However, the strain hardening rule is experimentally known to fail in scenarios such as loa...
متن کامل