Reactor Pressure Vessel Integrity
Radiation embrittlement is a known degradation mechanism in ferritic steels, and the beltline of reactor pressure vessels is particularly susceptible to radiation damage. The effects of radiation on vessel materials have impacted heatup/cooldown limits for PWRs, and increased hydrostatic test temperatures for BWRs, thereby significantly limiting plant operation. Structural Integrity Associates, Inc. (SI), with strong expertise in managing reactor vessel embrittlement and vessel integrity, can provide nuclear plants with technical support in a number of areas, including pressure-temperature curve development; materials evaluations; third-party reviews of RPV materials surveillance program results and implementation; setpoint evaluations; pressurized thermal shock evaluations; vessel fluence evaluations; and evaluations of projected vessel properties and Pressure-Temperature Limits for license renewal applications. SI has also worked with ASME for the past 15 years to improve PWR and BWR heatup and cooldown limits.For information, please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it