Preliminary Concepts of an Automated Additive Manufacturing System for Accident Tolerant Uranium Silicide Fuel Pellets

被引:1
|
作者
McIntyre, Rachael A. [1 ]
van Rooyen, Isabella J. [1 ]
机构
[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA
关键词
D O I
10.1007/978-3-030-36296-6_16
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Traditional methods of manufacturing nuclear fuel are labor intensive and costly, generally including extrusion or sintering processes and the use of substantially pure materials. The US Department of Energy is working to develop accident tolerant nuclear reactor fuels as alternatives to Zircaloy-4-uranium dioxide (UO2) fuel systems. This could increase existing safety margins for nuclear plants while improving nuclear plant performance and decreasing maintenance and operational costs. Idaho National Laboratory has worked with Westinghouse to develop a new process called additive manufacturing as an Alternative Fabrication Technique (AMAFT) centered on the production of one such accident tolerant fuel, uranium silicide (U3Si2). A previous feasibility study performed with surrogate material demonstrates on a manual benchtop experimental setup that U3Si2 fuel pellets can be manufactured by selective laser melting (SLM). This report provides preliminary concepts to aid in process scale-up, including improvements that an automated system can provide for optimized and repeatable material properties. Automation and robotics provide further acceleration of commercialization with the potential to reduce manufacturing time, costs, and decreased material waste while decreasing or even eliminating direct handling of radioactive materials.
引用
收藏
页码:175 / 181
页数:7
相关论文
共 50 条
  • [31] The development of cladding materials for the accident tolerant fuel system from the Materials Genome Initiative
    Liu, Zhen
    Li, Yifan
    Shi, Diwei
    Guo, Yaolin
    Li, Mian
    Zhou, Xiaobing
    Huang, Qing
    Du, Shiyu
    [J]. SCRIPTA MATERIALIA, 2017, 141 : 99 - 106
  • [32] Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3 Si2) with increased uranium loading
    Ortega, Luis H.
    Blamer, Brandon J.
    Evans, Jordan A.
    McDeavitt, Sean M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2016, 471 : 116 - 121
  • [33] iWAAM: An automated system for monitoring and control of wire-arc additive manufacturing
    Coutinho, Fernando
    Lizarralde, Nicolas
    Mendes, Marcel
    Bostrom, Rodrigo
    Silva, Thales
    Couto, Marcus
    Lizarralde, Fernando
    [J]. IFAC PAPERSONLINE, 2023, 56 (02): : 6576 - 6581
  • [34] Towards an automated decision support system for the identification of additive manufacturing part candidates
    Sheng Yang
    Thomas Page
    Ying Zhang
    Yaoyao Fiona Zhao
    [J]. Journal of Intelligent Manufacturing, 2020, 31 : 1917 - 1933
  • [35] Towards an automated decision support system for the identification of additive manufacturing part candidates
    Yang, Sheng
    Page, Thomas
    Zhang, Ying
    Zhao, Yaoyao Fiona
    [J]. JOURNAL OF INTELLIGENT MANUFACTURING, 2020, 31 (08) : 1917 - 1933
  • [36] A review on wire arc additive manufacturing: Monitoring, control and a framework of automated system
    Xia, Chunyang
    Pan, Zengxi
    Polden, Joseph
    Li, Huijun
    Xu, Yanling
    Chen, Shanben
    Zhang, Yuming
    [J]. JOURNAL OF MANUFACTURING SYSTEMS, 2020, 57 : 31 - 45
  • [37] Implementation of chrome oxidation model into best-estimate system code for accident tolerant fuel
    Lee, Dong-Young
    Ro, Tae-Sun
    Chung, Bub-Dong
    Hong, Soon-Joon
    [J]. ANNALS OF NUCLEAR ENERGY, 2023, 192
  • [38] MELCOR MODELING OF COMBINED ACCIDENT TOLERANT FUEL AND REACTOR CORE ISOLATION COOLING SYSTEM OPERATION
    Faucettl, Chris
    Beeny, Bradley
    Kirkland, Karen Vierow
    [J]. PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 2, 2020,
  • [39] TRANSIENT-BEHAVIOR OF LOW ENRICHED URANIUM SILICIDE PLATE-TYPE FUEL FOR RESEARCH REACTORS DURING REACTIVITY INITIATED ACCIDENT CONDITIONS
    YANAGISAWA, K
    FUJISHIRO, T
    HORIKI, O
    SOYAMA, K
    ICHIKAWA, H
    KODAIRA, T
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1993, 30 (08) : 741 - 751
  • [40] Automated reactor physics analysis framework of High Flux Isotope Reactor low-enriched uranium silicide dispersion fuel designs
    Bae, Jin Whan
    Betzler, Benjamin R.
    Chandler, David
    Hartanto, Donny
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2023, 405