Stress corrosion cracking growth rates of candidate canister materials for spent nuclear fuel storage in chloride-containing atmosphere

被引:20
|
作者
Tani, Jun-Ichi [1 ]
Mayuzumi, Masarni
Arai, Taku
Hara, Nobuyoshi
机构
[1] Cent Res Inst Elect Power Ind, Mat Sci Res Lab, Yokosuka, Kanagawa 2400196, Japan
[2] Tokyo Inst Technol, Grad Sch Sci & Engn, Dept Engn Sci & Mech, Tokyo 1528552, Japan
[3] Tohoku Univ, Grad Sch Engn, Dept Met, Sendai, Miyagi 9808579, Japan
关键词
concrete cask; stainless steel; canister; stress corrosion cracking; sea salt;
D O I
10.2320/matertrans.MRA2006367
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Chloride-induced stress corrosion crack growth rates were measured for candidate canister materials in a simulated marine atmospheric environment. Half-inch compact tension specimens were used to obtain stress corrosion crack growth rates by applying a direct-current potential-drop method to measure crack lengths. The crack growth rates of S31603 and S31260 stainless steels were 3 x 10(-10) m center dot s(-1) and 4 x 10(-13) m center dot S-1 for an applied stress intensity factor of 30 MPa center dot m (0.5), respectively, at a test temperature of 353 K at a relative humidity of 35%. S31254 specimens did not show stress corrosion cracking susceptibility under the same conditions as above, suggesting their superior resistance to chloride-induced stress corrosion cracking. These data were consistent with the results that S31260 and S31254 stainless steels did not fail after up to 37700 h although S31603 failed after 533 h in constant-load tests under the same environmental conditions. Assuming active-path corrosion to be an anodic subprocess of stress corrosion crack growth, anodic polarization Curves of the test materials were obtained in a synthetic seawater solution of pH I at 353 K. The maximum anodic current density of the active dissolution of S31603 stainless steel was ten times as large as that of S31260 stainless steel. This result qualitatively explains the difference in the crack growth behavior between S31603 and S31260 stainless steels.
引用
收藏
页码:1431 / 1437
页数:7
相关论文
共 42 条
  • [1] Chloride induced stress corrosion cracking of candidate canister materials for dry storage of spent fuel
    Mayuzumi, M.
    Tani, J.
    Arai, T.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (05) : 1227 - 1232
  • [2] Initial corrosion behavior of candidate canister materials for the interim storage of spent fuel
    Tani, Jun-Ichi
    Mayuzumi, Masami
    [J]. Zairyo to Kankyo/ Corrosion Engineering, 2005, 54 (12): : 582 - 586
  • [3] Stress corrosion cracking of stainless-steel canister for concrete cask storage of spent fuel
    Tani, Jun-ichi
    Mayuzumi, Masami
    Hara, Nobuyoshi
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2008, 379 (1-3) : 42 - 47
  • [4] Preventing Stress Corrosion Cracking of Spent Nuclear Fuel Dry Storage Canisters
    Hackel, Lloyd
    Rankin, Jon
    Walter, Matt
    Dane, C. Brent
    Neuman, William
    Oneid, Pierre
    Thomas, Garreth
    Bidrawn, Fred
    [J]. FATIGUE DESIGN 2019, INTERNATIONAL CONFERENCE ON FATIGUE DESIGN, 8TH EDITION, 2019, 19 : 346 - 361
  • [5] Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking
    Jensen, Philip J.
    Suffield, Sarah
    Grant, Christopher L.
    Spitz, Casey
    Hanson, Brady
    Ross, Steven
    Durbin, Sam
    Bryan, Charles
    Saltzstein, Sylvia
    [J]. NUCLEAR TECHNOLOGY, 2022, 208 (03) : 586 - 601
  • [6] Fracture Mechanics-Based Study of Stress Corrosion Cracking of SS304 Dry Storage Canister for Spent Nuclear Fuel
    Tjayadi, Leonardi
    Kumar, Nilesh
    Murty, Korukonda L.
    [J]. TMS 2019 148TH ANNUAL MEETING & EXHIBITION SUPPLEMENTAL PROCEEDINGS, 2019, : 1089 - 1097
  • [7] Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Used for Dry Storage of Spent Nuclear Fuel
    Ahn, T.
    Oberson, G.
    DePaula, S.
    [J]. CORROSION, PASSIVITY, AND ENERGY: A SYMPOSIUM IN HONOR OF DIGBY D. MACDONALD, 2013, 50 (31): : 211 - 226
  • [8] Stress Corrosion Cracking of Austenitic Cast Iron in Chloride-Containing Waters
    Francis, Roger
    Byrne, Glenn
    [J]. CORROSION, 2022, 78 (06) : 563 - 569
  • [9] Fracture toughness properties of candidate canister materials for spent fuel storage by concrete cask
    Arai, T
    Mayuzumi, M
    Libin, N
    Hiroshi, T
    [J]. TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 2005, 91 (05): : 57 - 64
  • [10] Initiation and Propagation of Stress Corrosion Cracking of Stainless Steel Canister for Concrete Cask Storage of Spent Nuclear Fuel (Reprinted from Proceedings of the CORROSiON/2008 Research Topical Symposium)
    Tani, J. -I.
    Mayuzurmi, M.
    Hara, N.
    [J]. CORROSION, 2009, 65 (03) : 187 - 194