Chemical interactions between pre-oxidized Zircaloy-4 and 304 stainless steel-B4C melt at 1300°C

被引:14
作者
Zheng, Lichun [1 ]
Hosoi, Kazuya [1 ]
Ueda, Shigeru [1 ]
Gao, Xu [1 ]
Kitamura, Shin-ya [1 ]
Kobayashi, Yoshinao [2 ]
Sudo, Ayako [3 ]
机构
[1] Tohoku Univ, Inst Multidisciplinary Res Adv Mat, Aoba Ku, Katahira 2-1-1, Sendai, Miyagi 9808577, Japan
[2] Tokyo Inst Technol, Inst Innovat Res, Lab Adv Nucl Energy, Meguro Ku, Ookayama 2-12-1, Tokyo 1528550, Japan
[3] Japan Atom Energy Agcy, Shirakata 2-4, Tokai, Ibaraki 3191195, Japan
基金
日本科学技术振兴机构;
关键词
304 stainless steel; B4C; Zircaloy-4; ZrO2 oxide scale; Chemical interactions; Mechanism; Kinetics; REACTION BEHAVIOR; FE-ZR; B4C; OXIDATION; STEAM; TEMPERATURES; DEGRADATION; ACCIDENT; KINETICS;
D O I
10.1016/j.jnucmat.2018.05.057
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
During severe nuclear accidents, control rods rapidly liquefy at temperatures above 1250 degrees C due to eutectic reaction, forming a 304 stainless steel (304SS)-B4C melt. The melt will relocate and attack surrounding fuel rod claddings made of Zircaloy-4 (Zry-4). To understand to what extent ZrO2 oxide scale formed on Zry-4 will protect Zry-4 claddings against 304SS-B4C melt attack, we studied the chemical interactions between pre-oxidized Zry-4 and 304SS-B4C melt at 1300 degrees C. Bare Zry-4 was completely dissolved in 304SS-B4C melt within 60 min. The presence of ZrO2 oxide scale on Zry-4 significantly delayed the interactions, especially when ZrO2 oxide scale was dense. Typically, the reaction zone consists of ZrB2,Zr-6(Fe, Ni, Cr) 23 and Fe-Ni-Cr metallic phase at room temperature. Due to the presence of alpha-Zr and beta-Zr in Zry-4 metal matrix, ZrO2 oxide scale becomes thermodynamically unstable. Dissolution of dense ZrO2 oxide scale can be described in three stages with different dissolution rates. Dissolution of ZrO2 oxide scale provides Zr source for the growth of reaction zone. Generally, the thickness of reaction zone linearly increases with time. Compared with the reaction couples of pre-oxidized Zry-4 and solid 316 stainless steel, both ZrO2 dissolution rate and reaction zone growth rate are much slower in the reaction couples of pre-oxidized Zry-4 and 304SS-B4C melt. The corresponding reasons were discussed. (C) 2018 Elsevier B.V. All rights reserved.
引用
收藏
页码:361 / 370
页数:10
相关论文
共 32 条
  • [21] Reaction behavior between B4C, 304 grade of stainless steel and Zircaloy at 1473 K
    Sasaki, Ryosuke
    Ueda, Shigeru
    Kim, Sun-Joong
    Gao, Xu
    Kitamura, Shin-ya
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2016, 477 : 205 - 214
  • [22] Reaction between B4C and austenitic stainless steel in oxidizing atmosphere at temperatures below 1673 K
    Sasaki, Ryosuke
    Ueda, Shigeru
    Kim, Sun-Joong
    Gao, Xu
    Kitamura, Shin-ya
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 466 : 334 - 342
  • [23] Experimental determination of intermetallic phases, phase equilibria, and invariant reaction temperatures in the Fe-Zr system
    Stein, F
    Sauthoff, G
    Palm, M
    [J]. JOURNAL OF PHASE EQUILIBRIA, 2002, 23 (06): : 480 - 494
  • [24] Synopsis and outcome of the QUENCH experimental program
    Steinbrueck, M.
    Grosse, M.
    Sepold, L.
    Stuckert, J.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (07) : 1714 - 1727
  • [25] Degradation and oxidation of B4C control rod segments at high temperatures
    Steinbrueck, M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2010, 400 (02) : 138 - 150
  • [26] High-Temperature Oxidation of Zircaloy-4 in Oxygen-Nitrogen Mixtures
    Steinbrueck, Martin
    Schaffer, Steffi
    [J]. OXIDATION OF METALS, 2016, 85 (3-4): : 245 - 262
  • [27] Influence of boron carbide on core degradation during severe accidents in LWRs
    Steinbrueck, Martin
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 64 : 43 - 49
  • [28] Stuckert J., 2008, 7373 FZKA
  • [29] Thermodynamic evaluation of Sn-Zr phase diagram
    Subasic, N
    [J]. CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY, 1998, 22 (02): : 157 - 165
  • [30] Analysis of Core Melt Accident in Fukushima Daiichi-Unit 1 Nuclear Reactor
    Tanabe, Fumiya
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2011, 48 (08) : 1135 - 1139