Tag Archives: Stress corrosion cracking
BWRVIP-310: BWR Vessel and Internals Project, Report and Nuclear Regulatory Commission Correspondence DVD, Version 2016
The documents on this DVD provide guidelines for managing the degradation of reactor pressure vessel internal components in boiling water nuclear reactors. It includes hundreds of EPRI technical reports and related correspondence with the U.S. Nuclear Regulatory Commission dating back to 1994.
Steam Generator Management Program: Assessment of Lead Induced Stress Corrosion Cracking Inhibitor Effectiveness
Stress corrosion cracking—a type of degradation in steam generator tubing in nuclear plants—can be linked to the presence of lead. One possible approach to mitigate this degradation involves adding to the plant’s secondary water chemicals that interfere with lead. In this study, researchers tested the effectiveness of several such “inhibitor” chemicals.
BWRVIP-97, Revision 1: BWR Vessel and Internals Project, Guidelines for Performing Weld Repairs to Irradiated BWR Internals
As nuclear reactors age, it becomes more important to consider how irradiation impacts the weldability of stainless steel components. These guidelines help utilities to evaluate welded repairs on irradiated components and avoid cracking.