[논문]HIGH TEMPERATURE OXIDATION OF NB-CONTAINING ZR ALLOY CLADDING IN LOCA CONDITIONS

Chuto, Toshinori; Nagase, Fumihisa; Fuketa, Toyoshi

doi:10.5516/net.2009.41.2.163

[국내논문] HIGH TEMPERATURE OXIDATION OF NB-CONTAINING ZR ALLOY CLADDING IN LOCA CONDITIONS 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.41 no.2, 2009년, pp.163 - 170

Chuto, Toshinori (Fuel Safety Research Group, Nuclear Safety Research Center) , Nagase, Fumihisa (Fuel Safety Research Group, Nuclear Safety Research Center) , Fuketa, Toyoshi (Fuel Safety Research Group, Nuclear Safety Research Center)

Abstract ▼ AI-Helper

In order to evaluate high-temperature oxidation behavior of the advanced alloy cladding under LOCA conditions, isothermal oxidation tests in steam were performed with cladding specimens prepared from high burnup PWR fuel rods that were irradiated up to 79 MWd/kg. Cladding materials were $M5^{(R)}$ and $ZIRLO^{TM}$, which are Nb-containing alloys. Ring-shaped specimens were isothermally oxidized in flowing steam at temperatures from 1173 to 1473 K for the duration between 120 and 4000s. Oxidation rates were evaluated from measured oxide layer thickness and weight gain. A protective effect of the preformed corrosion layer is seen for the shorter time range at the lower temperatures. The influence of pre-hydriding is not significant for the examined range. Alloy composition change generally has small influence on oxidation in the examined temperature range, though $M5^{(R)}$ shows an obviously smaller oxidation constant at 1273 K. Consequently, the oxidation rates of the high burnup $M5^{(R)}$ and $ZIRLO^{TM}$ cladding are comparable or lower than that of unirradiated Zircaloy-4 cladding.

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제안 방법

Temperature was measured with an R-type thermocouple at the specimen holder. Specimen temperature was estimated from the holder temperature and the temperature difference between the holder and the specimen, which was measured in the preliminary tests. Conditions of the oxidation tests are summarized in Table 2.
In order to investigate the influence of high burnup on the high-temperature oxidation of advanced alloy cladding, oxidation tests were performed at temperatures from 1173 to 1473 K for times between 120 and 4000s in steam flow. The specimens were sampled from high burnup PWR fuel rods (<79 MWd/kg) with M5 and ZIRLO cladding.

대상 데이터

The specimens were prepared from three PWR fuel rods that had been irradiated to 66, 67 or 79 MWd/kg (local burnup) at European power plants. The cladding materials were M5 (Zr-1.
The specimens were prepared from three PWR fuel rods that had been irradiated to 66, 67 or 79 MWd/kg (local burnup) at European power plants. The cladding materials were M5 (Zr-1.0% Nb) and ZIRLO (Zr-1.0% Sn-0.1% Fe-1.0%Nb). Corrosion layer thickness and hydrogen concentration were determined by microstructure observation and hydrogen analysis with the hot extraction method for specimens taken from the same fuel rods.
flow. The specimens were sampled from high burnup PWR fuel rods (<79 MWd/kg) with M5 and ZIRLO cladding. Oxidation rates were evaluated from measured oxide layer thickness and weight gain.

참고문헌 (9)

M. Ozawa, T. Takahashi, T. Homma, and K. Goto, "Behavior of irradiated Zircaloy-4 fuel cladding under simulated LOCA conditions," Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354, West Conshohocken, Pennsylvania, USA, p. 279 (2000).
J. -C. Brachet, V. Maillot, L. Portier, D. Gilbon, A. Lesbros, N. Weackel, and J. -P. Mardon, "Hydrogen content, preoxidation, and cooling scenario effects on post-quench microstructure and mechanical properties of Zircaloy-4 and M5 alloys in LOCA conditions," Zirconium in the Nuclear Industry: 15th International Symposium, Sun River, Oregon, USA, February 24-28, 2007.

상세보기
F. Nagase, T. Otomo, H. Uetsuka, "Experiments on high burnup fuel behavior under LOCA conditions at JAERI," 2000 International Topical Meeting on Light Water Reactor Fuel Performance, Park City, Utah, USA , April 10-13, 2000.
L. Portier, T. Bredel, J. -C. Brachet, V. Maillot, J. -P. Mardon, and A. Lesbros, "Influence of long service exposures on the thermal-mechanical behavior of Zy-4 and M5TM alloys in LOCA conditions," Zirconium in the Nuclear Industry: 14th International Symposium, Stockholm, Sweden, January 13-15, 2004.
F. Nagase, T. Otomo and H. Uetsuka, "Oxidation Kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1573 K," J. Nucl. Sci. Technol., 40, 4, p.213 (2003).

상세보기
Y. Yan, T. Burtseva and M. Billone, "LOCA-Related Research at ANL," Proc. of Fuel Safety Research Meeting 2004, Tokyo, Japan, March 1-2, 2004.
F. Nagase, "High burnup fuel behavior under LOCA conditions," Proc. Fuel Safety Research Meeting 2005, Tokyo, Japan, March 2-3, 2005.
F. Nagase, T. Chuto, T. Fuketa, "Fracture resistance of high burnup PWR fuel cladding under simulated LOCA conditions," 2008 Water Reactor Fuel Performance Meeting, Seoul, Korea, Oct. 19-23, 2008.
L. Baker and L. C. Just, Studies of Metal-Water Reaction at High Temperatures III. Experimental and Theoretical Studies of the Zirconium-Water Reaction, ANL-6548, Argonne National Laboratory (1962).

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DOI : 10.5516/NET.2009.41.2.163 [무료]
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