... in 288 °C BWR water was developed from seven sources comprised of 274 crack growth rate data. The data were evaluated based on experimental technique and water chemistry relevance (for example, air saturated water of ~1 μS/cm was considered the least relevant), then analyzed...

... in simulated boiling water reactor (BWR) high temperature water chemistries. Results show that alloys with a uniform equiaxed microstructure and Cr concentrations of 25 wt% and higher showed a larger than 10X reduction in SCC growth rates in the water chemistries tested compared to those with Cr concentrations...

.... Optimization of electrocatalysis by a continuous electrocatalytic process is described, for example where Pt is injected at levels of 0.002 to 0.05 ppb. Stress corrosion cracking BWR catalysis mitigation structural materials INTRODUCTION Stress corrosion cracking (SCC) of structural materials has occurred...

... of an unused stabilizer support bracket. Alloy X-750 has exhibited SCC in field components, and this study was designed to examine its microstructure and SCC response in some detail to determine the suitability of Alloy X-750 for long term reliable service in BWRs. stress corrosion cracking BWR high...

... for reduction of corrosion potentials and mitigation of SCC in Boiling Water Reactors (BWR) is included. Assuming equilibrium conditions at operating temperature 288°C in a relevant component crevice the time step wise calculated development of the critical crevice solution is quantitatively shown to initiate...

...Abstract Many boiling water nuclear reactors (BWRs) throughout the world have applied the NobleChem^TM (or noble metal chemical addition: NMCA) process just before end-of-cycle shutdown or during a mid-cycle shutdown to mitigate the stress corrosion cracking (SCC) of structural materials...

... showed that, in high temperature, high purity water, TiO₂ coating is a candidate oxide as an anti fouling layer under BWR water chemistry condition. BWR oxide fouling crud zeta potential high temperature water 304 SS jet pump INTRODUCTION During the operation of boiling water reactors...

..., such as Zr, Y, and their oxides, to structural materials. Abstract The fundamental understanding and practical application for mitigating degradation of structural materials in boiling water reactor (BWR) is described. Controlling the electrochemical property of surface alters the electrochemical corrosion...

...stress corrosion cracking cold rolling crack growth test BWR INTRODUCTION Stress corrosion cracking (SCC) has been observed on weld joints of the shroud and the pipes of primary loop recirculation system fabricated by Type 316L or 316NG stainless steel in Boiling Water Reactor (BWR). The main...

...BWR stainless steel high temperature water ECP stress corrosion cracking oxygen peroxide INTRODUCTION The degradation of structural materials in nuclear power plants has been well addressed in previous papers ^{1 - 2} . It is well understood that when the ECP of stainless steel (SS...

...The ECP is the mixed potential associated with equilibrium of redox reactions occurring on a metal surfce and the metal dissociation. In BWR reactor water, cathodic currents associated with the reduction of oxygen and hydrogen peroxide are balanced by anodic currents involving hydrogen oxidation...

... * [email protected] Abstract The adequacy and conservative character of the Boiling Water Reactor (BWR) Vessel and Internals Project (BWRVIP-60) stress corrosion cracking (SCC) disposition lines during and after water chemistry transients were evaluated and assessed in the context...

.... Thus, they can easily cover catalytically active sites and, thereby, alter the recombination kinetics of O₂ and H₂. High temperature water BWR 304 SS YSZ noble metal oxygen hydrogen INTRODUCTION The coolant in boiling water reactor (BWR) recirculation lines is high purity...

... NMCA increases the effectiveness of hydrogen injection and allows reduction of radiation exposure to the plant personnel. DAEC has now completed two cycles of successful operation with NMCA and has performed a reapplication. Following the successful demonstration of NMCA at DAEC many other BWRs have...

... in this simulated PWR water was measured to be 2.7 ppm at 350° and 1.8 ppm at 290°C. The BWR experiments were mostly carried out in a static autoclave which was permanently sparged with a Ar/O₂ gas mixture, resulting in an oxygen content of 400 ppb. The initial conductivity was 0.3 μS/cm. A small number...

...THEORETICAL APPROACH (2) H 2 O 2 + 2 H + + 2 e - = 2 H 2 O while the oxidation reactions of primary interest are (3) H 2 = 2 H + + 2 e - (4) M = M + n + ne - Redox Reactions In the BWR primary coolant, O₂, H₂...

...In the spring of 1994, the BWR Owners Group (BWROG) formed a new organization, the BWR Vessel and Internals Project (BWRVIP), to address the issue of IGSCC of BWR internal components. All domestic licensees and several foreign BWRs are members of the BWRVIP. The BWRVIP has five main committees...

...The purpose of the present study is to evaluate the effect of noble metal chemical addition on the ECP behavior and FAC of carbon steel in simulated BWR conditions at 288°C. EXPERIMENTAL PROCEDURE Specimen Preparation Test specimens of carbon steel (2.5 cm x 1.0 cm x 0.15 cm) were wet ground...

... temperature water BWR stainless steel INTRODUCTION The purpose of this study is to apply EIS for determining the in-situ resistive property of oxide films formed on 304 SS in 288°C water containing various amounts of O₂, H₂O₂, and H₂. This provides in-situ...

... amount of hydrogen is present in the water. electrochemical polarization oxygen hydrogen 304 Ss noble metal high temperature water ECP BWR INTRODUCTION The coolant in boiling water reactors (BWRs) recirculation lines is high purity, neutral pH water containing radiolytically generated...