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Title: Research reactor decommissioning experience - concrete removal and disposal -

Conference ·
OSTI ID:21141227
;  [1]
  1. Chem-Nuclear Systems, Incorporated, 220 Stoneridge Drive, Columbia, SC 29210 (United States)

Removal and disposal of neutron activated concrete from biological shields is the most significant operational task associated with research reactor decommissioning. During the period of 1985 thru 1989 Chem-Nuclear Systems, Inc. was the prime contractor for complete dismantlement and decommissioning of the Northrop TRIGA Mark F, the Virginia Tech Argonaut, and the Michigan State University TRIGA Mark I Reactor Facilities. This paper discusses operational requirements, methods employed, and results of the concrete removal, packaging, transport and disposal operations for these (3) research reactor decommissioning projects. Methods employed for each are compared. Disposal of concrete above and below regulatory release limits for unrestricted use are discussed. This study concludes that activated reactor biological shield concrete can be safely removed and buried under current regulations.

Research Organization:
General Atomics, San Diego, CA (United States)
OSTI ID:
21141227
Report Number(s):
INIS-US-09N0043; TOC-23; TRN: US09N0073020864
Resource Relation:
Conference: 12. U.S. TRIGA users conference, Austin, TX (United States), 11-14 Mar 1990; Other Information: Country of input: International Atomic Energy Agency (IAEA); 3 figs, 2 tabs; Related Information: In: 12. U.S. TRIGA users conference. Papers and abstracts, 328 pages.
Country of Publication:
United States
Language:
English