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Title: Corrosion of spent Advanced Test Reactor fuel

The results of a study of the condition of spent nuclear fuel elements from the Advanced Test Reactor (ATR) currently being stored underwater at the Idaho National Engineering Laboratory (INEL) are presented. This study was motivated by a need to estimate the corrosion behavior of dried, spent ATR fuel elements during dry storage for periods up to 50 years. The study indicated that the condition of spent ATR fuel elements currently stored underwater at the INEL is not very well known. Based on the limited data and observed corrosion behavior in the reactor and in underwater storage, it was concluded that many of the fuel elements currently stored under water in the facility called ICPP-603 FSF are in a degraded condition, and it is probable that many have breached cladding. The anticipated dehydration behavior of corroded spent ATR fuel elements was also studied, and a list of issues to be addressed by fuel element characterization before and after forced drying of the fuel elements and during dry storage is presented.
Authors:
;
Publication Date:
OSTI Identifier:
10192330
Report Number(s):
EGG-M--94222; CONF-941207--9
ON: DE95002010; TRN: 94:022723
DOE Contract Number:
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: Spent nuclear fuel meeting: challenges and initiatives,Salt Lake City, UT (United States),14-16 Dec 1994; Other Information: PBD: [1994]
Research Org:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Org:
USDOE, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; SPENT FUEL ELEMENTS; CORROSION; ATR REACTOR; UNDERWATER; TEMPERATURE DEPENDENCE; SPENT FUEL STORAGE; ALUMINIUM BASE ALLOYS 220300; 220600; FUEL ELEMENTS; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS