Experimental measurements to evaluate the effects of fuel microstructure on fission gas release in thoria

被引:2
作者
Barry, A. [1 ]
机构
[1] Canadian Nucl Labs, Chalk River, ON, Canada
关键词
Thorium dioxide; Thoria; Fission gas release; Irradiation; Fuel performance; Microstructure;
D O I
10.1016/j.anucene.2020.107933
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
Canadian Nuclear Laboratories (CNL) has many decades of thoria research and development experience, including fabrication, irradiation testing, and post-irradiation examination. CNL has previously shown fission gas release (FGR) to be dependent on fuel microstructure in thoria fuels. Lower density fuel with large granules surrounded by porous regions results in higher FGR. Higher and more uniform density fuel results in superior FGR results in thoria fuels with a similar irradiation history. In this paper, this effect of fuel microstructure on FGR is shown empirically using the most recent post-irradiation examination (PIE) results of CNL's DME-176 and DME-221 thoria experiments. Previously reported PIE results of CNL's BDL-422 and DME-221 thoria experiments are also compared. Crown Copyright (C) 2020 Published by Elsevier Ltd. All rights reserved.
引用
收藏
页数:8
相关论文
共 38 条
  • [21] Identification of Radial Position of Fission Gas Release in High-Burnup Fuel Pellets under RIA Conditions
    Sasajima, Hideo
    Sugiyama, Tomoyuki
    Chuto, Toshinori
    Nagase, Fumihisa
    Nakamura, Takehiko
    Fuketa, Toyoshi
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2010, 47 (02) : 202 - 210
  • [22] Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions
    Gonzalez-Robles, E.
    Metz, V.
    Wegen, D. H.
    Herm, M.
    Papaioannou, D.
    Bohnert, E.
    Gretter, R.
    Mueller, N.
    Nasyrow, R.
    de Weerd, W.
    Wiss, T.
    Kienzler, B.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2016, 479 : 67 - 75
  • [23] FEMAXI-V Benchmarking Study on Peak Temperature and Fission Gas Release Prediction of PWR Rod Fuel
    Suwardi
    Dewayatna, W.
    Briyatmoko, B.
    [J]. 3RD INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING 2011 (ICANSE 2011), 2012, 1448 : 126 - 134
  • [24] Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO 2 fuel
    Muntaha, Md Ali
    Chatterjee, Sourav
    Blondel, Sophie
    Aagesen, Larry
    Andersson, David
    Wirth, Brian D.
    Tonks, Michael R.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2024, 594
  • [25] Fission gas release behavior of high burnup UO2 fuel under reactivity initiated accident conditions
    Sasajima, H
    Nakamura, J
    Fuketa, T
    Uetsuka, H
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1999, 36 (11) : 1101 - 1104
  • [26] EVALUATION OF FISSION-GAS RELEASE IN HIGH-BURNUP LIGHT WATER-REACTOR FUEL-RODS
    BARNER, JO
    CUNNINGHAM, ME
    FRESHLEY, MD
    LANNING, DD
    [J]. NUCLEAR TECHNOLOGY, 1993, 102 (02) : 210 - 231
  • [27] Simulation of radioactive fission gas release from defective PWR fuel rod using the MFPR/R mechanistic code
    Tarasov, V. I.
    Ozrin, V. D.
    Veshchunov, M. S.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2023, 583
  • [28] Fission gas release in the micro-cell fuel pellet under normal operating conditions: A simplified approach based on UO2 pellet experience
    Koo, Yang-Hyun
    Shin, Chang-Hwan
    Jeon, Sang-Chae
    Kim, Dong-Seok
    Kim, Keon-Sik
    Kim, Dong-Joo
    Song, Kun-Woo
    Kook, Dong-Hak
    Kim, Hyun-Gil
    Jung, Yang-Il
    Yang, Jae-Ho
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2019, 527
  • [29] Fission gas release in BWR fuel with a burnup of 56 GWd/t during simulated reactivity initiated accident (RIA) condition
    Amaya, Masaki
    Sugiyama, Tomoyuki
    Nagase, Fumihisa
    Fuketa, Toyoshi
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (05) : 423 - 431
  • [30] Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis
    Pastore, Giovanni
    Luzzi, Lelio
    Di Marcello, Valentino
    Van Uffelen, Paul
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2013, 256 : 75 - 86