Title of article :
Department of energys annealing prototype demonstration projects
Author/Authors :
Warren، J.W. نويسنده , , Harrison، D.L. نويسنده , , Agarwal، D.C. نويسنده , , Rochau، G.E. نويسنده , , Nakos، J.T. نويسنده , , Kelly، J.E. نويسنده ,
Issue Information :
دوهفته نامه با شماره پیاپی سال 1999
Abstract :
One of the; challenges utilities face in addressing technical issues associated with the aging of nuclear power plants is the long-term effect of plant operation on reactor pressure vessels. These vessels are exposed to neutrons during the operation of a reactor. For certain plants, this exposure can cause embrittlemenl of some of the vessel welds, which can shorten the useful life of the vessel. This reactor pressure vessel embriltlement issue has the potential to affect the continued operation of a number of US pressurized water reactor plants. However, the properties that are degraded by long-term irradiation can he recovered through a thermal annealing treatment of the vessel steel. Although a dozen Kussian-designcd and several US military vessels have been successfully annealed, US utilities concluded that an annealing demonstration using a US reactor pressure vessel was a prerequisite belore annealing a licensed US nuclear power plant. In May 1995, the Department of Energy and Sandia National Laboratories initiated a program to evaluate the feasibility of annealing US licensed plants using two different heating technologies. One team completed its annealing prototype demonstration in July 1996, using an indirect gas-fired furnace at the uncompleted Public Service of Indianaʹs Marble Hill nuclear power plant in southern Indiana. The second teamʹs annealing prototype demonstration using a direct heat electrical furnace at the uncompleted Consumers Power Companyʹs nuclear power plant at Midland, Michigan, was scheduled to be completed in early 1997, but has now been delayed indefinitely. This paper describes the Deparlmcnt of Energyʹs annealing prototype demonstration program and the results to date for each project. (0 1999 Elsevier Science S.A. All rights reserved.
Keywords :
Transient data collection , Fatigue monitoring , Pressurized water reactors
Journal title :
Nuclear Engineering and Design
Journal title :
Nuclear Engineering and Design