A Systematic Survey of the Factors Affecting Zircaloy Nodular Corrosion /

A Systematic Survey of the Factors Affecting Zircaloy Nodular Corrosion /

Out-of-reactor corrosion tests in 10.3-MPa steam at temperatures between 490 and 530°C have been carried out on Zircaloy-2 tube specimens of various fabrication histories including archive specimens of the same tube lots as were used in the commercial boiling water reactor (BWR) to get data for comp...

Full description

Bibliographic Details
Main Authors: Abe, K. (Author), Aoki, T. (Author), Fujibayashi, T. (Author), Hattori, T. (Author), Inagaki, M. (Author), Kodama, T. (Author), Murota, K. (Author), Ogata, K. (Author), Okubo, T. (Author), Yoshitsugu, M. (Author)
Corporate Authors: ASTM International, American Society for Testing and Materials
Format: Book
Language:English
Published: West Conshohocken, Pa. : ASTM International, 1989
Subjects:
Boiling water reactor
Fabrication histories
In-reactor nodular corrosion
Nuclear fuel claddings > Congresses
Nuclear fuel claddings
Steam tests
Zircaloy

Internet

This item is not available through BorrowDirect. Please contact your institution’s interlibrary loan office for further assistance.

Similar Items