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Assessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components /

Bibliographic Details
Corporate Authors: U.S. Nuclear Regulatory Commission. Division of Fuel, Engineering, and Radiological Research, Pacific Northwest National Laboratory (U.S.)
Other Authors: Diaz, Aaron A.
Format: Government Document eBook
Language:English
Published: Washington, DC : Division of Fuel, Engineering, and Radiological Research, Division of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2007.
Subjects:
Nuclear power plants > Piping > Cracking.
Online Access:https://purl.fdlp.gov/GPO/LPS106400

Internet

https://purl.fdlp.gov/GPO/LPS106400

Available Online

Holdings details from Available Online
Call Number: Y 3.N 88:25/6929
 
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Y 3.N 88:25/6929 Available