Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage

被引：3
|
作者：
Hong, Jong-Dae [1 ]
Yang, Yong-Sik [1 ]
Kook, Donghak [1 ]
机构：
[1] Korea Atom Energy Res Inst, ATF Technol Dev Div, 989-111 Daedeok Daero, Daejeon 34057, South Korea
来源：
NUCLEAR ENGINEERING AND TECHNOLOGY | 2020年 / 52卷 / 03期
关键词：
DHC; PWR spent fuel; dry storage; Sensitivity; BEHAVIOR;
D O I：
10.1016/j.net.2019.07.036
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：
In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (K-IH) was performed. However, there were a few limitations in the analysis of the cladding properties, such as oxide thickness and mechanical properties. In this study, those models were modified to include test data for irradiated materials, and the cladding creep model was introduced to improve the reliability of the DHC assessment. In this study, DHC susceptibility of PWR spent fuel during dry storage depending on the axial elevation was evaluated with the improved assessment methodology. In addition, the sensitivity of affecting parameters such as fuel burnup, hydride thickness, and crack aspect ratio are presented. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码：614 / 620
页数：7
相关论文
共 50 条
  • [1] Delayed hydride cracking assessment of PWR spent fuel during dry storage
    Hong, Jong-Dae
    Kim, Hyo-Chan
    Kim, Ju-Seong
    Yang, Yong-Sik
    Kook, Dong-Hak
    NUCLEAR ENGINEERING AND DESIGN, 2017, 322 : 324 - 330
  • [2] Delayed hydride cracking of spent fuel rods in dry storage
    Kim, Young Suk
    JOURNAL OF NUCLEAR MATERIALS, 2008, 378 (01) : 30 - 34
  • [3] Hydride Reorientation and Delayed Hydride Cracking of Spent Fuel Rods in Dry Storage
    Young S. Kim
    Metallurgical and Materials Transactions A, 2009, 40 : 2867 - 2875
  • [4] Hydride Reorientation and Delayed Hydride Cracking of Spent Fuel Rods in Dry Storage
    Kim, Young S.
    METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2009, 40A (12): : 2867 - 2875
  • [5] Rupture of spent fuel Zircaloy cladding in dry storage due to delayed hydride cracking
    Chao, C. K.
    Yang, K. C.
    Tseng, C. C.
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (01) : 124 - 129
  • [6] Is Spent Nuclear Fuel Immune from Delayed Hydride Cracking during Dry Storage? An IAEA Coordinated Research Project
    Coleman, Christopher E.
    Markelov, Vladimir A.
    Roth, Maria
    Makarevicius, Vidas
    He, Zhang
    Chakravartty, Jayanta Kumar
    Alvarez-Holston, Anna-Maria
    Ali, Liaqat
    Ramanathan, Lalgudi
    Inozemtsev, Victor
    ZIRCONIUM IN THE NUCLEAR INDUSTRY: 18TH INTERNATIONAL SYMPOSIUM, 2018, 1597 : 1224 - 1251
  • [7] THE EFFECTS OF CREEP AND HYDRIDE ON SPENT FUEL INTEGRITY DURING INTERIM DRY STORAGE
    Kim, Hyun-Gil
    Jeong, Yong-Hwan
    Kim, Kyu-Tae
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2010, 42 (03) : 249 - 258
  • [8] Delayed-hydride cracking (DHC) of cladding materials: An analysis for storage and disposal of spent nuclear fuel
    Ahn, Tae M.
    NUCLEAR ENGINEERING AND DESIGN, 2019, 350 : 128 - 136
  • [9] THE RADIATION PROTECTION DESIGN OF PWR SPENT FUEL DRY STORAGE FACILITY
    Huang, Liming
    Yang, Shouhai
    Liu, Jie
    PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 7, 2018,
  • [10] Design study of a modular dry storage facility for typical PWR spent fuel
    Igbal, Masood
    Khan, J.
    Mirza, Sikander M.
    PROGRESS IN NUCLEAR ENERGY, 2006, 48 (06) : 487 - 494
12345