Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators
Subtitle: held at Fuji Institute of Education and Training, Japan, May 28-June 2, 1978
By: co-editors and co-chairmen, Hideya Okada, Roger Staehle ; sponsors, Electric Power Research Institute ... [et al.] = [BWR haikan oyobi PWR jōki hasseiki ni okeru fushoku sonshō to yosoku : 1978-nen 5-gatsu 28-nichi--6-gatsu 2-nichi Fuji Kyōiku Kenshūjo ni oite kaisai / henshūsha Okada Hideya, Rōjā W. Sutērī ; kōen Beikoku Denryoku Kenkyūjo ... [et al.]].
Contributors: Okada, Hideya.; Staehle, R. W., 1934-; Electric Power Research Institute.; U.S.-Japan Joint Symposium on Light Water Reactor (1st : 1978 : Fuji Institute of Education and Training, Japan)
Publisher: National Association of Corrosion Engineers
Published: 1982
Place of publication: Houston, Tex
Language: eng
Number of pages: 393
Subjects: Boiling water reactors -- Piping -- Corrosion -- Congresses.; Pressurized water reactors -- Corrosion -- Congresses.
Other titles: BWR haikan oyobi PWR jōki hasseiki ni okeru fushoku sonshō to yosoku.
Notes: Includes bibliographical references.
In English.
Proceeding of 1978 the First U.S.-Japan Joint Symposium on Light Water Reactor. Cf. p. xvii.