Irradiation Effects Test Series: Test IE-3. Test results report. [PWR]

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The objectives of the test reported were to: (a) determine the behavior of irradiated fuel rods subjected to a rapid power increase during which the possibility of a pellet-cladding mechanical interaction failure is enhanced and (b) determine the behavior of these fuel rods during film boiling following this rapid power increase. Test IE-3 used four 0.97-m long pressurized water reactor type fuel rods fabricated from previously irradiated fuel. The fuel rods were subjected to a preconditioning period, followed by a power ramp to 69 kW/m at a coolant mass flux of 4920 kg/s-m/sup 2/. After a flow reduction to 2120 ... continued below

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Pages: 154

Creation Information

Farrar, L. C.; Allison, C. M.; Croucher, D. W. & Ploger, S. A. October 1, 1977.

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  • EG & G Idaho
    Publisher Info: EG and G Idaho, Inc., Idaho Falls (USA)
    Place of Publication: Idaho Falls, Idaho

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Description

The objectives of the test reported were to: (a) determine the behavior of irradiated fuel rods subjected to a rapid power increase during which the possibility of a pellet-cladding mechanical interaction failure is enhanced and (b) determine the behavior of these fuel rods during film boiling following this rapid power increase. Test IE-3 used four 0.97-m long pressurized water reactor type fuel rods fabricated from previously irradiated fuel. The fuel rods were subjected to a preconditioning period, followed by a power ramp to 69 kW/m at a coolant mass flux of 4920 kg/s-m/sup 2/. After a flow reduction to 2120 kg/s-m/sup 2/, film boiling occurred on the fuel rods. One rod failed approximately 45 seconds after the reactor was shut down as a result of cladding embrittlement due to extensive cladding oxidation. Data are presented on the behavior of these irradiated fuel rods during steady-state operation, the power ramp, and film boiling operation. The effects of a power ramp and power ramp rates on pellet-cladding interaction are discussed. Test data are compared with FRAP-T3 computer model calculations and data from a previous Irradiation Effects test in which four irradiated fuel rods of a similar design were tested. Test IE-3 results indicate that the irradiated state of the fuel rods did not significantly affect fuel rod behavior during normal, abnormal (power ramp of 20 kW/m per minute), and accident (film boiling) conditions.

Physical Description

Pages: 154

Notes

Dep. NTIS, PC A08/MF A01.

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  • Report No.: TREE-NUREG-1106
  • Grant Number: EY-76-C-07-1570
  • DOI: 10.2172/5251538 | External Link
  • Office of Scientific & Technical Information Report Number: 5251538
  • Archival Resource Key: ark:/67531/metadc1071078

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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Creation Date

  • October 1, 1977

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

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  • June 1, 2018, 4:12 p.m.

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Farrar, L. C.; Allison, C. M.; Croucher, D. W. & Ploger, S. A. Irradiation Effects Test Series: Test IE-3. Test results report. [PWR], report, October 1, 1977; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc1071078/: accessed September 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.