Progress and future plans in the PFR/TREAT safety testing programs
Conference
·
OSTI ID:5507664
This paper briefly describes the progress to date on the joint UKAEA/USDOE program of fast reactor fuel safety testing and the definition of the future tests. The program involves transient tests in the TREAT reactor on fresh and irradiated mixed fuel pins. The tests simulate transient overpower (TOP) accidents, which result from an unintentional addition of reactivity and transient undercooling followed by overpower (TUCOP) accidents, which arise from an unintentional stoppage of the primary sodium circulating pumps, both with failure to scram. Thirteen tests have been performed to date, all on UK pins. Future plans include five tests, all on US pins which have been irradiated in FFTF. Much has been learned about the behavior of fuel driven to conditions well beyond those existing during normal reactor operation.
- Research Organization:
- Argonne National Lab., IL (USA); UKAEA Risley Nuclear Power Development Establishment; UKAEA Atomic Energy Establishment, Winfrith
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5507664
- Report Number(s):
- CONF-860501-15; ON: DE86014494
- Country of Publication:
- United States
- Language:
- English
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FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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LIQUID METAL COOLED REACTORS
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MATERIALS
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