z-logo
open-access-imgOpen Access
Assessment of pressurized water reactor control rod drive mechanism nozzle cracking
Author(s) -
V.N. Shah,
A.G. Ware,
A M Porter
Publication year - 1994
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/10196760
Subject(s) - nozzle , pressurized water reactor , cracking , coolant , materials science , stress corrosion cracking , control rod , corrosion , reactor pressure vessel , metallurgy , head (geology) , structural engineering , pressurizer , composite material , nuclear engineering , engineering , geology , mechanical engineering , geomorphology

The content you want is available to Zendy users.

Already have an account? Click here to sign in.
Having issues? You can contact us here
Accelerating Research

Address

John Eccles House
Robert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom