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The present study of the tritium transmission electron microscopic autoradiography (TEMARG) procedure was carried out on radiationdamaged Fe-Cr-Ni alloy. The Fe-Cr-Ni alloys used in internal reactor components and irradiated in light water reactors (LWR) is influenced by hydrogen generated by the radiolysis of the LWR coolant water and (n,p) reaction in Fe-Cr-Ni alloy. There is a probability that a portion of the hydrogen in the coolant water would be diffused into the Fe-Cr-Ni alloy, thus forming an interstitial solid solution, and that hydrogen would change to H2 or CH4 in voids at grain boundaries1). These hydrogen atoms are presumed to be one of the causes of irradiation assisted stress corrosion cracking (IASCC) and hydrogen embrittlement of internal reactor components2),3). These phenomena have a very important bearing on IASCC of Fe-Cr-Ni alloy. However, the cause and mechanism of IASCC is not clearly understood4). To investigate the cause of IASCC, tritium has been used to study the compatibility between hydrogen in reactor coolant water and that in radiation damaged Fe-CrNi alloy. The TEM-ARG procedure using tritium has been developed to investigate tritium and hydrogen interactions with radiation induced defects and grain boundaries. During the past fifteen years many studies have been carried out using tritium ARG to investigate hydrogen behavior in non-radiation-damaged metals5)-11) In 1963, the

Application of Tritium Tracer for Investigation of Hydrogen Behavior in a Radiation Damaged Fe-Cr-Ni Alloy.