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Westinghouse has developed an engineering analysis method (which has been accepted by the U.S. NRC) to define the loads on baffle bolts during various normal, upset, and faulted conditions. This method...
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05-08-2007
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106
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File Size 31.7kB
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Primary water stress corrosion cracking (PWSCC) of Alloy 600 materials and Alloy 182/82 welds has become a top industry concern for PWR plants. PWSCC has produced significant availability losses and has...
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05-08-2007
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260
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File Size 211.4kB
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Instances of flux thimble tube wear and leakage observed in operating reactors have been attributed to flow-induced vibrations in the lower internals support column area. As a result, the NRC has issued...
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05-08-2007
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143
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File Size 92.9kB
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In the early 1980s, Alloy X-750 guide tube support pins originally installed in the guide tubes in upper internals began exhibiting cracks. In some cases, the pin shank and the nut securing the pin broke...
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05-08-2007
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206
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File Size 404.2kB
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Flow leakage through the axial gap between the vertical baffle plates has caused fuel rod damage in some early generations of Westinghouse plants that have a downflow configuration. These vertical baffle...
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05-08-2007
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152
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File Size 29.4kB
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Instrument nozzle penetrations are common to pressurizer and hot/cold leg reactor coolant system (RCS) piping. Inconel 600 partial penetration welded nozzles typical to these areas are susceptible to stress...
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05-08-2007
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174
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File Size 115.4kB
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Pressurized water reactor (PWR) plants have experienced primary water stress corrosion cracking (PWSCC) since the 1980s. PWSCC occurs in Alloy 82/182 welds as well as Alloy 600 components. Left untreated...
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05-08-2007
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286
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File Size 507kB
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Conventional cavity seal rings must be installed and removed during each outage.They are difficult to handle and allow significant leakage past the seals. Westinghouse has designed the Permanent Cavity...
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05-08-2007
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113
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File Size 79kB
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In response to industry events involving Alloy 600 material in reactor vessel closure head (RVCH) penetrations, a number of pressurized water reactor (PWR) utilities have, or intend to, replace the RVCH...
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05-08-2007
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254
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File Size 40.7kB
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The primary driver for pressurizer replacement is a plant's desire to reduce or eliminate downtime due to pressurizer heater sleeve leaks or other Alloy 600 leaks that have plagued the industry for some...
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05-08-2007
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341
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File Size 38.2kB
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