Modeling of hydrogen behavior in spent fuel claddings during dry storage

被引：12
|
作者：
Kolesnik, M. [1 ]
Aliev, T. [1 ]
Likhanskii, V. [1 ]
机构：
[1] Russian Federat Troitsk Inst Innovat & Fus Res, State Res Ctr, Moscow, Russia
来源：
JOURNAL OF NUCLEAR MATERIALS | 2018年 / 508卷
关键词：
dry storage; Zirconium hydrides; Hydride reorientation; HYDRIDE REORIENTATION; ZIRCONIUM HYDRIDE; ZIRCALOY-4; PRECIPITATION; ALLOYS; STRESS; DIFFRACTION; DISSOLUTION; PLATE;
D O I：
10.1016/j.jnucmat.2018.06.012
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
new hydride reorientation model is presented for spent fuel dry storage conditions. The model takes into account the coupled influence of external stresses, alloy texture, temperature cycling and cooling rate. The model has been tested successfully against experiments in a wide range of conditions. The features of the model are the use of kinetic equations and the simulating of such processes as hydride memory effect and possible hydrogen redistribution between hydrides of different orientations. Current version of the model will be used for safety justification of dry storage conditions. (C) 2018 Elsevier B.V. All rights reserved.
引用
收藏
页码：567 / 573
页数：7
相关论文
共 50 条
  • [1] Spent nuclear fuel in dry storage conditions - current trends in fuel performance modeling
    Konarski, Piotr
    Cozzo, Cedric
    Khvostov, Grigori
    Ferroukhi, Hakim
    JOURNAL OF NUCLEAR MATERIALS, 2021, 555
  • [2] Rod internal pressure of spent nuclear fuel and its effects on cladding degradation during dry storage
    Kim, Ju-Seong
    Hong, Jong-Dae
    Yang, Yong-Sik
    Kook, Dong-Hak
    JOURNAL OF NUCLEAR MATERIALS, 2017, 492 : 253 - 259
  • [3] 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
  • [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] Methodology for a realistically conservative characterization of spent fuel in dry storage
    Feria, F.
    Aguado, C.
    Herranz, L. E.
    ANNALS OF NUCLEAR ENERGY, 2020, 140
  • [6] Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
    Jang, Ki-Nam
    Cha, Hyun-Jin
    Kim, Kyu-Tae
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (08) : 1740 - 1747
  • [7] 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
  • [8] REVIEW OF SPENT FUEL INTEGRITY EVALUATION FOR DRY STORAGE
    Kook, Donghak
    Choi, Jongwon
    Kim, Juseong
    Kim, Yongsoo
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2013, 45 (01) : 115 - 124
  • [9] Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage
    Hong, Jong-Dae
    Yang, Yong-Sik
    Kook, Donghak
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (03) : 614 - 620
  • [10] Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage
    Aomi, Masaki
    Baba, Toshikazu
    Miyashita, Toshiyasu
    Kamimura, Katsuichiro
    Yasuda, Takayoshi
    Shinohara, Yasunari
    Takeda, Toru
    ZIRCONIUM IN THE NUCLEAR INDUSTRY: 15TH INTERNATIONAL SYMPOSIUM, 2009, 1505 : 651 - +
12345