Post irradiation examination of fast reactor fuel pins irradiated in a sodium environment up to about 55 MWd/kg UO$sub 2$
Technical Report
·
OSTI ID:4935786
Two fast reactor fuel pins have been irradiated in a sodium environment in the HFR Poolside Facility at Petten to a burnup of 41.5 and 53.5 MWd/kg UO/sub 2/, respectively. The fuel pins consisted of 50% enriched UO/sub 2/ pellets of 5.1-mm diameter, canned in an X-8 Cr Ni MoV Nb 16.13 (Werkstoffnr, 4955) stainless steel tube with an outer diameter of 6.0 mm and a wall thickness of 0.35 mm. Both irradiations had to be terminated prematurely; the first one (R62- A03) because of a breakdown of the midplane thermocouples and the second one (R62- A04) because of fuel pin failure. The target burnups were 50 and 80 MWd/kg UO/ sub 2/, respectively. The maximum measured sodium temperature was 650 deg C, which means that the maximum average canning has been 750 deg C. The average heat ratings in the fuel pins were about 600 W/cm. About 70% of the fission gases formed in fuel pin A03 have been released. The canning on the failure spot in A04 showed an axial crack with a length of about 25 mm and a maximum width of about 2 mm. Part of the fuel at the location of the failure was washed out and was found at the bottom of the capsule between the shroud tube and sodium containment. Dimensional control after irradiation revealed that the maximum change in diameter of fuel pin A03 was 1.2%. For A04 this was about 3.3%. Considerable interaction between fuel and canning was observed in both fuel pins. (71 figures, 11 tables) (auth)
- Research Organization:
- Stichting Reactor Centrum Nederland, Petten
- Sponsoring Organization:
- Sponsor not identified
- NSA Number:
- NSA-29-011878
- OSTI ID:
- 4935786
- Report Number(s):
- RCN--197
- Country of Publication:
- Netherlands
- Language:
- English
Similar Records
UO$sub 2$--PuO$sub 2$ fuel-rod-bundle irradiation Mol-7A. Evaluation of the investigation results on the irradiated fuel rods
Oxide-cermet fuel rods: production, properties, and irradiation behavior
Status of steady-state irradiation testing of mixed-carbide fuel designs. [LMFBR]
Technical Report
·
Fri Jun 01 00:00:00 EDT 1973
·
OSTI ID:4932655
Oxide-cermet fuel rods: production, properties, and irradiation behavior
Technical Report
·
Wed Aug 01 00:00:00 EDT 1973
·
OSTI ID:4932657
Status of steady-state irradiation testing of mixed-carbide fuel designs. [LMFBR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6211512