Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version) | Zendy

Marion P. Krug | Zendy; R.P. Shogan | Zendy; Arnold H. Fero | Zendy; Matthew Snyder | Zendy

Open Access

Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)

Author(s) -

Marion P. Krug,

R.P. Shogan,

Arnold H. Fero,

Matthew Snyder

Publication year - 2004

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/836105

Subject(s) - pressurized water reactor , nuclear engineering , coolant , materials science , reactor pressure vessel , characterization (materials science) , neutron flux , structural material , environmental science , metallurgy , neutron , mechanical engineering , nuclear physics , engineering , physics , nanotechnology

Pressurized water reactor (PWR) cores, operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR

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