z-logo
open-access-imgOpen Access
Boiling-Water Reactor internals aging degradation study. Phase 1
Author(s) -
K.H. Luk
Publication year - 1993
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/10182155
Subject(s) - nuclear engineering , boiling water reactor , coolant , stress corrosion cracking , materials science , reactor pressure vessel , environmental science , boiler feedwater , neutron flux , natural circulation , nuclear reactor , boiling , shutdown , pressurized water reactor , neutron , corrosion , metallurgy , waste management , nuclear physics , mechanical engineering , engineering , boiler (water heating) , chemistry , physics , organic chemistry

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