STP1354

    Evaluation of Zircaloy-2 Cladding Corrosion Characteristics by Simulated BWR Corrosion Loop Test

    Published: Jan 2000


      Format Pages Price  
    PDF (476K) 21 $25   ADD TO CART
    Complete Source PDF (24M) 21 $393   ADD TO CART


    Abstract

    The effects of irradiation conditions such as neutron flux, β and γ rays, and of heat flux on the corrosion behavior of Zircaloy-2 cladding tubes were studied by using an inreactor corrosion loop simulating BWR conditions. Platinum and hafnium rings were placed in the rigs as β and γ emitters, respectively, to evaluate local radiation effects on cladding corrosion. The tube materials included an early BWR 8 x 8RJ type and a new, more corrosionresistant BWR 9X9-type cladding. Both tubes contained UO2 and Al2O3 pellets and were irradiated under the same conditions in two rigs in the same loop for about 180 days. Nodular corrosion appeared on the 8X8RJ-type tube, while the 9X9-type tube presented only uniform oxide layer. Metallographic and SEM observations revealed that the β and γ emitters enhanced the uniform oxide formation for the 9X9-type tube, while they increased the nodule density for the 8X8RJ type. Computer analyses on neutron flux and β- and γ-ray intensities were conducted for the 8X8RJ-type and 9X9-type test rods. Those results were utilized to comprehensively discuss and to understand the in-pile corrosion behavior.

    Keywords:

    Zircaloy-2, cladding tube, corrosion, heat flux, radiation, γ ray, β ray, boiling water reactor


    Author Information:

    Shimada, S
    Chief researcher, senior researcher, and researcher, Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken,

    Asahi, K
    Chief researcher, senior researcher, and researcher, Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken,

    Nonaka, Y
    Chief researcher, senior researcher, and researcher, Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken,

    Sasaki, M
    Senior engineer, Hitachi, Ltd., Hatachi Works, Ibaraki-ken,

    Kogai, T
    Senior specialist, Toshiba Corp., Isogo Nuclear Engineering Center, Yokohama-shi,

    Hayashi, H
    Manager, chief engineer, and assistant chief engineer, Nuclear Power Engineering Corp., Tokyo,

    Kitamura, M
    Manager, chief engineer, and assistant chief engineer, Nuclear Power Engineering Corp., Tokyo,

    Sakamoto, M
    Manager, chief engineer, and assistant chief engineer, Nuclear Power Engineering Corp., Tokyo,

    Yamawaki, M
    Professor, University of Tokyo, Tokyo,


    Paper ID: STP14325S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP14325S


    CrossRef ASTM International is a member of CrossRef.