Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators BWR配管およびPWR蒸気発生機における腐食損傷と予測 : held at Fuji Institute of Education and Training, Japan, May 28-June 2, 1978

Author(s)

• 岡田, 秀弥 オカダ, ヒデヤ
• Staehle, R. W.
• Electric Power Research Institute
• U.S.-Japan Joint Symposium on Light Water Reactor

Bibliographic Information

Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators = BWR配管およびPWR蒸気発生機における腐食損傷と予測 : held at Fuji Institute of Education and Training, Japan, May 28-June 2, 1978

co-editors and co-chairmen, Hideya Okada, Roger Staehle ; sponsors, Electric Power Research Institute ... [et al.]

National Association of Corrosion Engineers, c1982

Title Transcription

BWR ハイカン オヨビ PWR ジョウキ ハッセイキ ニオケル フショク ソンショウ ト ヨソク

Note

In English

Proceeding of 1978 the First U.S.-Japan Joint Symposium on Light Water Reactor. Cf. p. xvii

Includes bibliographical references

Details

• NCID: BA35650990
• LCCN: 81085852
• Country Code: us
• Title Language Code: eng
• Text Language Code: eng
• Place of Publication: Houston, Tex.
• Pages/Volumes: xxix, 393, 6 p.
• Size: 29 cm
• Classification:
  • LCC : TK9203.B6
  • DC20 : 621.48/34
• Subject Headings:
  • LCSH : Boiling water reactors -- Piping -- Corrosion -- Congresses
  • LCSH : Pressurized water reactors -- Corrosion -- Congresses