NEUTRON EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS

Technical Report · Tue Oct 22 04:00:00 EDT 1963

OSTI ID:4116865

Steele, L E; Hawthorne, J R

This report presents the status of observations on the embrittlement of steels which are commonly used for the primary pressure containment vessels of nuclear power plants. The demonstrated criterion of nil ductility transition (NDT) temperature provides the basis for meaningful analysis of neutron-induced embrittlement in reactor steels. Results to date indicate that the degree of embrittlement depends upon the material, the neutron exposure, and the temperature during irradiation. These same variables also affect the degree of notch ductility recovery effected by postirradiation heat treatment. In addition, the time and temperature of heat treatment are shown to play an important role in establishing the recovery pattern. The validity of these experimental observations is being tested through correlations with data from reactor surveillance programs and from specimens of the SL-1 reactor pressure vessel. Preliminary data from dosimetry in the SM-1A reactor permit the extension of experimental data to predict the increase in NDT of the reactor pressure vessel. (auth)

• Research Organization: Naval Research Lab., Washington, D.C.
• NSA Number: NSA-18-007307
• OSTI ID: 4116865
• Report Number(s): NRL-5984; AD-423526
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BRITTLENESS
DOSEMETERS
DUCTILITY
HEAT TREATMENTS
IRRADIATION
METALS, CERAMICS, AND OTHER MATERIALS
NEUTRONS
NOTCHES
POWER PLANTS
PRESSURE VESSELS
RADIATION DOSES
REACTORS
RECOVERY
STEELS
TEMPERATURE