Published 1986 | Version v1
Book

Test methods for selection of materials of construction for high-level radioactive waste vitrification

  • 1. E.I. du Pone de Nemours and Co., Wilmington, DE (USA)
  • 2. Savannah River Lab., Aiken, SC (USA)

Description

Candidate materials of construction were evaluated for a facility at the Department of Energy's Savannah River Plant to vitrify high-level radioactive waste. Limited operating experience was available under the corrosive conditions of the complex vitrification process. The objective of the testing program was to provide a high degree of assurance that equipment will meet or exceed design lifetimes. To meet this objective in reasonable time and minimum cost, a program was designed consisting of a combination of coupon immersion and electrochemical laboratory tests and pilot-scale tests. Stainless steels and nickel-based alloys were tested. Alloys that were most resistant to general and local attack contained nickel, molybdenum (>9%), and chromium (where Cr + Mo > 30%). Alloy C-276 was selected as the reference material for process equipment. Stellite 6 was selected for abrasive service in the presence of formic acid. Alloy 690 and Allcorr were selected for specific applications

Additional details

Publishing Information

Publisher
American Ceramic Society Inc.
Imprint Place
Westerville, OK (USA)
ISBN
0-916094-82-0
Imprint Title
Nuclear waste management II
Journal Page Range
p. 53-64.

Conference

Title
3. international symposium on ceramics in nuclear waste management.
Dates
28-30 Aug 1986.
Place
Chicago, IL (USA).