An integrated chemical effects test (ICET) was designed and executed to investigate the corrosion of materials in a hypothetical post-loss of coolant accident (LOCA) environment for pressurized water reactors (PWRs) and the resulting effects on the measured head loss in three vertical columns through multiconstituents debris beds. The head loss columns were isolated approximately after 72 h, as the measured head loss in all three columns approached or surpassed the maximum limit of the differential pressure (DP) cells. Additional bench scale tests were carried out to investigate the cause of high head loss in the three columns. Combination of epoxy agglomeration and adhesion to fiber resulted in subsequent blockage of the flow through the debris bed with no chemical precipitation was concluded as the most reasonable cause of high head loss observed in the test. The test continued thereafter up to 30 days as an integrated chemical effects test using the corrosion tank only. The results presented in this article demonstrate trends for zinc, aluminum, and calcium release that are consistent with separate bench scale testing and previous integrated tests conducted under trisodium phosphate (TSP)-buffered post-LOCA environmental conditions. In general, the total and filtered samples showed almost identical concentration of all metals (Al, Ca, Si, and Mg) except zinc which clearly indicate that no precipitation occurred. The release rate and maximum concentrations of the released materials were slightly different than the separate effect testing as a result of different experimental conditions (temperature, surface area-to-water volume ratio) and/or the presence of other metals and chemicals in the integrated test.
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April 2017
Research-Article
Experimental Study of Aqueous Chemical Trisodium Phosphate-Buffered Environment Under Post-LOCA Conditions With Head Loss Measurements
Amir Ali,
Amir Ali
Research Assistant Professor
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: amirali@unm.edu
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: amirali@unm.edu
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Daniel LaBrier,
Daniel LaBrier
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: dlabrier@unm.edu
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: dlabrier@unm.edu
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Kerry J. Howe,
Kerry J. Howe
Professor
Department of Civil Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: howe@unm.edu
Department of Civil Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: howe@unm.edu
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Edward D. Blandford
Edward D. Blandford
Assistant Professor
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: edb@unm.edu
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: edb@unm.edu
Search for other works by this author on:
Amir Ali
Research Assistant Professor
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: amirali@unm.edu
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: amirali@unm.edu
Daniel LaBrier
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: dlabrier@unm.edu
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: dlabrier@unm.edu
Kerry J. Howe
Professor
Department of Civil Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: howe@unm.edu
Department of Civil Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: howe@unm.edu
Edward D. Blandford
Assistant Professor
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: edb@unm.edu
Department of Nuclear Engineering,
University of New Mexico,
1 University of New Mexico,
Albuquerque, NM 87131-0001
e-mail: edb@unm.edu
1Corresponding author.
Manuscript received April 13, 2016; final manuscript received August 3, 2016; published online March 1, 2017. Assoc. Editor: Michio Murase.
ASME J of Nuclear Rad Sci. Apr 2017, 3(2): 021002 (12 pages)
Published Online: March 1, 2017
Article history
Received:
April 13, 2016
Revised:
August 3, 2016
Citation
Ali, A., LaBrier, D., Howe, K. J., and Blandford, E. D. (March 1, 2017). "Experimental Study of Aqueous Chemical Trisodium Phosphate-Buffered Environment Under Post-LOCA Conditions With Head Loss Measurements." ASME. ASME J of Nuclear Rad Sci. April 2017; 3(2): 021002. https://doi.org/10.1115/1.4034572
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