Study on thermal performance of accident tolerant fuel with UO2 mixed pellet and zircaloy cladding coating

被引：0
|
作者：
Chen, Ping [1 ]
Liu, Zhenhai [1 ]
Li, Wenjie [1 ]
Xing, Shuo [1 ]
机构：
[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610041, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2015年 / 36卷
关键词：
4;
D O I：
10.13832/j.jnpe.2015.S2.0084
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：84 / 86
相关论文
共 50 条
  • [21] Effects of pellet microstructure on irradiation behavior of UO2 fuel
    Yuda, R
    Harada, H
    Hirai, M
    Hosokawa, T
    Une, K
    Kashibe, S
    Shimizu, S
    Kubo, T
    JOURNAL OF NUCLEAR MATERIALS, 1997, 248 : 262 - 267
  • [22] SiC/Si thin film deposited on zircaloy to improved accident tolerant fuel cladding
    Lee, Kangsoo
    Kim, Dongkyu
    Yoon, Young Soo
    THIN SOLID FILMS, 2018, 660 : 221 - 230
  • [23] MODELING THE IRRADIATION SWELLING OF UO2 AT THE FUEL PELLET RIM
    Gao, Lijun
    Chen, Bingde
    Xiao, Zhong
    Jiang, Shengyao
    Yu, Jiyang
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 1, 2014,
  • [24] IRRADIATION-INDUCED DENSIFICATION OF UO2 PELLET FUEL
    FRESHLEY, MD
    BRITE, DW
    DANIEL, JL
    HART, PE
    JOURNAL OF NUCLEAR MATERIALS, 1976, 62 (2-3) : 138 - 166
  • [25] Effects of pellet microstructure on irradiation behavior of UO2 fuel
    Nippon Nuclear Fuel Development Co, Ltd, Ibaraki-ken, Japan
    J Nucl Mater, (262-267):
  • [26] Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation
    Simon R. Phillpot
    Anter El-Azab
    Aleksandr Chernatynskiy
    James S. Tulenko
    JOM, 2011, 63 : 73 - 79
  • [27] Thermal Conductivity of UO2 Fuel: Predicting Fuel Performance from Simulation
    Phillpot, Simon R.
    El-Azab, Anter
    Chernatynskiy, Aleksandr
    Tulenko, James S.
    JOM, 2011, 63 (08) : 77 - 83
  • [28] SIMULATION ON PELLET-CLADDING MECHANICAL INTERACTION (PCMI) OF ACCIDENT TOLERANT FUEL (ATF) WITH COATED CLADDING
    Deng, Yangbin
    Qiu, Bowen
    Wu, Yingwei
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 3, 2017,
  • [29] Double diffusive dissolution model of UO2 pellet in molten Zr cladding
    Itoh, Ayumi
    Yamashita, Susumu
    Tasaki, Yudai
    Kakiuchi, Kazuo
    Kobayashi, Yoshinao
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2023, 60 (04) : 450 - 459
  • [30] PERFORMANCE OF MIXED-OXIDE FUEL AT HIGH BURNUP AND COMPARISON WITH UO2 FUEL
    HAAS, D
    LIPPENS, M
    THOMSON, JM
    AMERICAN CERAMIC SOCIETY BULLETIN, 1981, 60 (03): : 418 - 418
12345