000			01812nab a2200205 4500
005			20260520002824.0
008			260224s2009 xxu
100	1		_aScheel, J.E. _943001
100	1		_aHornbach, D.J. _943002
100	1		_aPrevey, P.S. _943003
245	0	0	_aNuclear power plant develops method to assess susceptibility of components to cracking _bInformation on corrosion control and prevention
260			_csep. 2009
270			_a17/06/2010 ; 17/06/2010
300			_a9 p. ; 16-24
520			_aTranscripción del resumen del autor. Stress corrosion cracking (SCC) can weaken piping and other components in a nuclear power plant. It's difficult to predict SCC can take 20 years or more to develop and costly to repair. To avoid unexpected SCC, managers at the Fort Calhoun Station nuclear power plant, located on the west bank of the Missouri River ~ 19 miles (31 km) north of Omaha, Nebraska and owned and operated by Omaha Public Power District (OPPD), developed a method to accurately assess the susceptibility of stainless steel (SS) and other alloys to SCC through eddy current inspection. This method, used successfully at the facility for the past 10 years to inspect reactor vessel head nozzles, reactor vessel nozzles, and control element drive mechanism (CEDM) seal housings, has helped the plant to avoid unnecessary replacement of expensive process components, with a savings of nearly $7 million, and significantly reduced plant personnel's radiation exposure. In May 2009, Fort Calhoun Station was honored for developing this method with the nuclear energy industry's B. Ralph Sylvia Best of the Best Award presented by the Nuclear Energy Institute (Washington, DC).
581			_a9
773	0		_tMaterials Performance _g48
942			_cARTICULO
999			_c171203 _d171203