Dry Rod Consolidation Technology Project results
Conference
·
OSTI ID:6348564
The Dry Rod Consolidation Technology (DRCT) Project conducted at the Idaho National Engineering Laboratory (INEL), in 1987 demonstrated the technical feasibility of a dry horizontal fuel rod consolidation process. Fuel rods from Westinghouse 15 /times/ 15 pressurized water reactor (PWR) spent fuel assemblies were consolidated into canisters to achieve a 2:1 volume reduction ratio. The consolidation equipment was operated at an existing hot cell complex at the INEL. The equipment was specifically designed to interface with the existing facility fuel handling and operational capabilities and was instrumented to provide data collection for process technology research. During the operational phase, data were collected from observation of the consolidation process, fuel assembly handling, and fuel rod behavior and characteristics. Equipment performance was recorded and data measurements were compiled on crud and contamination generated and spread. Fuel assembly skeletons (non-fuel bearing components (NFBC)) were gamma scanned and analyzed for isotopic content and profile. The above data collection was enhanced by extensive photograph and video documentation. The loaded consolidation fuel canisters were utilized for a test of the Transnuclear, Inc. TN-24P dry storage cask with consolidated fuel. The NFBC material was stored for a future volume reduction demonstration project. 14 figs., 4 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6348564
- Report Number(s):
- EGG-M-29587; CONF-880354-12; ON: DE89011140
- Country of Publication:
- United States
- Language:
- English
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Thu Mar 31 23:00:00 EST 1988
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Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5963724
Related Subjects
052001* -- Nuclear Fuels-- Waste Processing
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
DATA ANALYSIS
DRY STORAGE
EVALUATION
HIGH-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
MINIMIZATION
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
SPENT FUEL STORAGE
STORAGE
VOLUME
WASTE MANAGEMENT
WASTE STORAGE
WASTES
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
DATA ANALYSIS
DRY STORAGE
EVALUATION
HIGH-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
MINIMIZATION
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
SPENT FUEL STORAGE
STORAGE
VOLUME
WASTE MANAGEMENT
WASTE STORAGE
WASTES