An Analysis of Cladding Failure on Beam Transient of Lead-Bismuth-Cooled Accelerator-Driven System

被引:3
作者
Aizawa, Naoto [1 ]
Iwasaki, Tomohiko [1 ]
机构
[1] Tohoku Univ, Dept Quantum Sci & Energy Engn, Aoba Ku, Sendai, Miyagi 9808579, Japan
关键词
accelerator-driven system; ADS; transient; cladding failure; cumulative creep damage fraction; CDF; DESIGN;
D O I
10.3327/jnst.48.892
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The cladding failure analyses on various beam transients of Lead-Bismuth-cooled Accelerator-Driven System (ADS) were performed with ADSE code and the cladding failure analysis program. First, the cladding failure analysis program was developed. This program is intended for creep ruptures analysis using ADSE code and employs the method of Cumulative creep Damage Fraction (CDF) calculation. Beam diameter expansion, beam flattening, beam hollowing, and beam incident position change were analyzed for the ADS model proposed by JAEA. As a result, beam diameter expansion, beam flattening, and beam hollowing would not lead to cladding failures but beam incident position change was revealed to have a high risk for the cladding failures. Some core designs were proposed for the prevention of failure. The changes of sizes such as plenum length were not effective for CDF reductions. The application of SUS316FR steel cladding instead of Mod.9Cr-1Mo steel showed good performance but the application of SUS316FR steel needs some provisions for erosions and corrosions. The fuel composition change was very effective for CDF control and this measure would be the best modification for the prevention of cladding failures.
引用
收藏
页码:892 / 901
页数:10
相关论文
共 11 条
  • [1] *JAP AT EN AG ADV, 2006, 2006042 JAEA NUCL SC
  • [2] *JAP WELD ENG SOC, 1999, JWESAE9907
  • [3] Kaito T., 2002, TN94002002061 JNC JA
  • [4] MODELING THE BEHAVIOR OF METALLIC FAST-REACTOR FUELS DURING EXTENDED TRANSIENTS
    KRAMER, JM
    LIU, YY
    BILLONE, MC
    TSAI, HC
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1993, 204 : 203 - 211
  • [5] KURATA Y, 2006, 2006024 JAEA
  • [6] Sugawara T, 2009, 2009024 JAEA
  • [7] SUGAWARA T, 2007, P GLOBAL2007 BOIS ID, P998
  • [8] Suzuki M., 2010, P INT TOP M NUCL RES
  • [9] Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code
    Suzuki, T
    Chen, XN
    Rineiski, A
    Maschek, W
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (24) : 2594 - 2611
  • [10] Design study of lead-bismuth cooled ADS dedicated to nuclear waste transmutation
    Takizuka, T
    Tsujimoto, K
    Sasa, T
    Nishihara, K
    Takano, H
    [J]. PROGRESS IN NUCLEAR ENERGY, 2002, 40 (3-4) : 505 - 512