Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water

Hirotaka Kawamura; Masahiro Furuya

Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water

Hirotaka Kawamura^*, Masahiro Furuya

^*Corresponding author for this work

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

2 Citations (Scopus)

Abstract

Japanese PWR utilities desire to employ long-term fuel cycle and high bum-up operations. Corrosion product (crud) deposition on fuel cladding surface would become significant issue in Japanese PWRs, because the large amounts of crud deposition has led to an increase of the dose rate in the primary coolant system and become a root cause of axial offset anomalies (AOA) for other utilities. In order to clarify the contribution factors of the deposition, the effects of steaming rate, pHi-, and boron contents in the test solution on the crud deposition were investigated under sub-cooled boiling and non-irradiated condition. From the test results, it was revealed that the spinel oxide layer was formed on the fuel cladding surface in a simulated Japanese PWR fuel cycle chemistry at 325°C. The oxide layer was easily formed on the heated surface of the fuel cladding, and the oxide thickness was increased with increase of steaming rate and decrease of pH_T.

Original language	English
Title of host publication	Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Pages	369-384
Number of pages	16
Publication status	Published - 2007 Dec 1
Externally published	Yes
Event	13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 - Whistler, BC, Canada Duration: 2007 Apr 19 → 2007 Apr 23

Publication series

Name	Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Volume	1

Conference

Conference	13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Country/Territory	Canada
City	Whistler, BC
Period	07/4/19 → 07/4/23

Keywords

Boric acid concentration
Corrosion product
Crud
PWR primary coolant
Zircaloy-4

ASJC Scopus subject areas

Nuclear Energy and Engineering
Safety, Risk, Reliability and Quality
Materials Science(all)

Cite this

Kawamura, H., & Furuya, M. (2007). Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water. In Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 (pp. 369-384). (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007; Vol. 1).

Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water. / Kawamura, Hirotaka; Furuya, Masahiro.
Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. 2007. p. 369-384 (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007; Vol. 1).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Kawamura, H & Furuya, M 2007, Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water. in Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007, vol. 1, pp. 369-384, 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007, Whistler, BC, Canada, 07/4/19.

Kawamura H, Furuya M. Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water. In Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. 2007. p. 369-384. (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007).

Kawamura, Hirotaka ; Furuya, Masahiro. / Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water. Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. 2007. pp. 369-384 (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007).

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abstract = "Japanese PWR utilities desire to employ long-term fuel cycle and high bum-up operations. Corrosion product (crud) deposition on fuel cladding surface would become significant issue in Japanese PWRs, because the large amounts of crud deposition has led to an increase of the dose rate in the primary coolant system and become a root cause of axial offset anomalies (AOA) for other utilities. In order to clarify the contribution factors of the deposition, the effects of steaming rate, pHi-, and boron contents in the test solution on the crud deposition were investigated under sub-cooled boiling and non-irradiated condition. From the test results, it was revealed that the spinel oxide layer was formed on the fuel cladding surface in a simulated Japanese PWR fuel cycle chemistry at 325°C. The oxide layer was easily formed on the heated surface of the fuel cladding, and the oxide thickness was increased with increase of steaming rate and decrease of pHT.",

keywords = "Boric acid concentration, Corrosion product, Crud, PWR primary coolant, Zircaloy-4",

author = "Hirotaka Kawamura and Masahiro Furuya",

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AU - Kawamura, Hirotaka

AU - Furuya, Masahiro

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N2 - Japanese PWR utilities desire to employ long-term fuel cycle and high bum-up operations. Corrosion product (crud) deposition on fuel cladding surface would become significant issue in Japanese PWRs, because the large amounts of crud deposition has led to an increase of the dose rate in the primary coolant system and become a root cause of axial offset anomalies (AOA) for other utilities. In order to clarify the contribution factors of the deposition, the effects of steaming rate, pHi-, and boron contents in the test solution on the crud deposition were investigated under sub-cooled boiling and non-irradiated condition. From the test results, it was revealed that the spinel oxide layer was formed on the fuel cladding surface in a simulated Japanese PWR fuel cycle chemistry at 325°C. The oxide layer was easily formed on the heated surface of the fuel cladding, and the oxide thickness was increased with increase of steaming rate and decrease of pHT.

AB - Japanese PWR utilities desire to employ long-term fuel cycle and high bum-up operations. Corrosion product (crud) deposition on fuel cladding surface would become significant issue in Japanese PWRs, because the large amounts of crud deposition has led to an increase of the dose rate in the primary coolant system and become a root cause of axial offset anomalies (AOA) for other utilities. In order to clarify the contribution factors of the deposition, the effects of steaming rate, pHi-, and boron contents in the test solution on the crud deposition were investigated under sub-cooled boiling and non-irradiated condition. From the test results, it was revealed that the spinel oxide layer was formed on the fuel cladding surface in a simulated Japanese PWR fuel cycle chemistry at 325°C. The oxide layer was easily formed on the heated surface of the fuel cladding, and the oxide thickness was increased with increase of steaming rate and decrease of pHT.

KW - Boric acid concentration

KW - Corrosion product

KW - Crud

KW - PWR primary coolant

KW - Zircaloy-4

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Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water

Abstract

Publication series

Conference

Keywords

ASJC Scopus subject areas

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