... the σ_crev and the occurrence of localized corrosion was also revealed in the attendant studies. ^{12 - 13} boiling water reactor carbon stainless steel crevice corrosion crevice water chemistry high-purity water high-temperature water low-stress corrosion cracking F e-Cr-Ni...

... for so many important structural applications in nuclear power plants. To address this question, the historical development of both pressurized water reactor designs and boiling water reactor designs is reviewed. The review covers factors such as the material types selected for test and use...

..., University of Alberta, Edmonton, AB, Canada T6G 2V4. ^**Canadian Nuclear Laboratories, Chalk River, Ontario, Canada K0J 1J0. 27 2 2015 11 5 2015 11 5 2015 © 2015 NACE International 2015 boiling water reactor cathode cathodic polarization contact corrosion...

...Pascal V. Grundler; Amuthan Ramar; Lyubomira Veleva; Stefan Ritter Stress corrosion cracking of stainless steel components in boiling water reactors can threaten their structural integrity and lead to costly maintenance operations. A low electrochemical corrosion potential can reduce...

...Hans J. Leber; Stefan Ritter; Hans-Peter Seifert Two unique facilities for isothermal low-cycle fatigue (LCF) and in-phase (IP) or out-of-phase (OP) thermo-mechanical fatigue (TMF) testing of tubular specimens under boiling water reactor (BWR) and pressurized water reactor (PWR) coolant conditions...

...Y.Y. Chen; H.C. Shih; L.H. Wang; J.C. Oung The fatigue crack growth behavior of sensitized Type 304 (UNS S30400) stainless steel (SS) with an electrochemical potentiokinetic reactivation (EPR) value of 30 C/cm² was investigated under boiling water reactor (BWR) conditions at 288°C. Tests...

... dependence of the ECP in 288°C water containing various oxygen concentrations can be calculated at any instant from the well-known Nernst equation. September 2005 February 2006 NACE International 2006 alcohol Alloy 690 boiling water reactor electrochemical corrosion potential high...

... analyses, as well as for dispositioning existing or postulated defects. In this paper, the results of corrosion fatigue (CF) and stress corrosion cracking (SCC) experiments with two different reactor pressure vessel (RPV) steels at 288°C (~561 K) under simulated boiling water reactor (BWR) conditions...

... NACE International 2005 boiling water reactor electrochemical corrosion potential high-temperature water insulated coatings noble metal plasma spray yttria-stabilized zirconia Intergranular stress corrosion cracking (IGSCC) of sensitized stainless steel (SS) components in boiling...

...X.-Q. Wu; Y. Katada The low-cycle fatigue (LCF) behavior of as-received and thermally aged A533B pressure vessel steels has been investigated in a simulated boiling water reactor (BWR) environment. The inclusions, microstructure, and cyclic cracking behavior were examined carefully. Pronounced...

...N. Saito; S. Tanaka; H. Sakamoto To evaluate the effect of corrosion potential on the stress corrosion cracking (SCC) initiation lifetime of nickel-base alloys, periodically unloaded uniaxial constant load (PU-UCL) tests were conducted, simulating boiling water reactor (BWR) water chemistry...

...Y.-J. Kim Effects of a variety of water chemistry conditions on the theoretical understanding and development of an electrochemical corrosion potential (ECP) prediction model to calculate the ECP of structural materials in boiling water reactors (BWR) are described. In particular, the effects...

... in regions of highly disturbed cooling water flow during the operation of a boiling water reactor (BWR) under hydrogen water chemistry (HWC) conditions. Carbon steels (CS) are extensively used in some parts of nuclear power plants, and erosion-corrosion of CS in water and wet steam is known to be a major...

... effect of Cu and Zn on the total loadings of Pt and Rh. boiling water reactor high-temperature water noble metal polarization recombination kinetics stainless steel The coolant in boiling water reactor (BWR) recirculation lines is high-purity, neutral pH water containing radiolytically...

... to the power generation industry. In particular, intergranular stress corrosion cracking (IGSCC) of sensitized stainless steel (SS) components in boiling water reactors (BWR) under normal water chemistry (NWC) conditions containing high levels of O₂ and hydrogen peroxide (H₂O₂...

.... November 1998 August 1999 1 2010 NACE International 1999 boiling water reactor chromium hydrogen water chemistry iron nickel normal water chemistry Pourbaix diagram spinel oxides Corrosion resistance of materials in different environments is related closely to the phases...

...C.C. Lin; Y.J. Kim; L.W. Niedrach; K.S. Ramp The electrochemical corrosion potential (ECP) of stainless steel (SS) was measured under simulated boiling-water reactor (BWR) coolant circuit conditions using a rotating cylinder electrode (RCE). Based upon those measurements, an empirical model...

... to failure corrected to strain rate of 10^–6/s. December 1994 April 1995 1 2010 NACE International 1995 boiling water reactor chloride lithium hydroxide potential slow strain rate tests stress corrosion cracking sulfate temperature type 304 stainless steel...

.... A thicker oxide formed under the NWC environment than under the HWC condition. September 1994 February 1995 1 2010 NACE International 1995 boiling water reactor hydrogen water chemistry normal water chemistry oxide film stainless steel temperature type 304 stainless steel...

... supporting the idea that low-temperature annealing (LTA) can mitigate IASCC. The sheath portion of a control rod that had operated in a U.S. boiling water reactor (BWR) for four fuel cycles between July 1967 and May 1977 was used as the starting material. This material was commercial-purity (CP) type...