Independent safety evaluation of the enriched uranium oxide test UO-1
The UO-1 test is designed to provide information on the performance of D9 clad, enriched uranium oxide fuel in FFTF. The Series IV FFTF driver fuel will utilize enriched uranium oxide fuel with D9 cladding. Irradiation data are needed for computer code calibration to support the FSAR analysis effort for the series IV fuel. The UO-1 assembly consists of a 217-pin bundle with the same pin and duct dimensions as a standard driver fuel assembly. The test consists of seven UO{sub 2} pins, 30 mixed oxide test pins, and 180 driver type pins. The test will be irradiated for approximately 250 EFPD. An Independent Safety Evaluation (ISE) of the test has been conducted. Information has been taken from the Test Design Documents, but independent calculations have been made of the safety-related parameters. The scope includes all items specified in the Users` Guide for Irradiation of Experiments in the FTR. Areas investigated include Technical Specification Compliance, Steady State Operation, Transient Operation, Failure Consequences, Stress and Seismic, HCDA, and Test Handling and Criticality Considerations.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States)
- Sponsoring Organization:
- USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 449247
- Report Number(s):
- WHC-SP-0549; ON: DE97003953
- Resource Relation:
- Other Information: PBD: Nov 1989
- Country of Publication:
- United States
- Language:
- English
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