METALLIC FUEL FOR Na-COOLED REACTORS WITH AN EXTENDED BURNUP CYCLE.

被引：0
|
作者：
Bencheikh, A. [1 ]
Karam, R.A. [1 ]
机构：
[1] Georgia Inst of Technology, Nuclear, Engineering & Health Physics, Program, Atlanta, GA, USA, Georgia Inst of Technology, Nuclear Engineering & Health Physics Program, Atlanta, GA, USA
来源：
| 1600年 / 12期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
NUCLEAR FUELS
引用
收藏
相关论文
共 33 条
  • [21] French and United Kingdom experience of high-burnup mixed-oxide fuel in sodium-cooled fast breeder reactors
    Martin, Philippe
    Pelletier, Michel
    Every, Denis
    Buckthorpe, Derek
    NUCLEAR TECHNOLOGY, 2008, 161 (01) : 35 - 44
  • [22] Fuel Cycle Studies on the Uranium Utilization Efficiency and Minor Actinide Burning in Gas Cooled Fast Reactors
    Halasz, M.
    Szieberth, M.
    Feher, S.
    Reiss, T.
    2013 4TH INTERNATIONAL YOUTH CONFERENCE ON ENERGY (IYCE), 2013,
  • [23] Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel
    Zhang, Youpeng
    Wallenius, Janne
    ANNALS OF NUCLEAR ENERGY, 2014, 70 : 180 - 187
  • [24] THE BENEFITS OF CYCLE STRETCH-OUT IN PRESSURIZED WATER-REACTOR EXTENDED-BURNUP FUEL-CYCLES
    MATZIE, RA
    LEUNG, DC
    LIU, Y
    BEEKMANN, RW
    NUCLEAR TECHNOLOGY, 1981, 52 (02) : 189 - 197
  • [25] FEASIBILITY STUDY ON AN UPGRADED FUTURE MONJU CORE CONCEPT WITH EXTENDED OPERATION CYCLE LENGTH OF ONE YEAR AND INCREASED FUEL BURNUP
    Kinjo, Hidehito
    Kageyama, Takeshi
    Kitano, Akihiro
    Usami, Shin
    NUCLEAR TECHNOLOGY, 2009, 167 (02) : 254 - 267
  • [26] Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost
    Lu, Cihang
    Browns, Nicholas R.
    NUCLEAR ENGINEERING AND DESIGN, 2019, 347 : 108 - 121
  • [27] The Study of Capability Natural Uranium as Fuel Cycle Input for Long Life Gas Cooled Fast Reactors with Helium as Coolant
    Ariani, Menik
    Satya, Octavianus Cakra
    Monado, Fiber
    Su'ud, Zaki
    Sekimoto, Hiroshi
    4TH INTERNATIONAL CONFERENCE ON THEORETICAL AND APPLIED PHYSICS (ICTAP) 2014, 2016, 1719
  • [28] Burnup performance of small-sized long-life CANDLE high temperature gas-cooled reactors with U-Th-Pa fuel
    Liem, Peng Hong
    Hoai-Nam Tran
    Sekimoto, Hiroshi
    ANNALS OF NUCLEAR ENERGY, 2016, 91 : 36 - 47
  • [29] DESIGN STUDY OF LEAD-COOLED AND LEAD-BISMUTH-COOLED SMALL LONG-LIFE NUCLEAR-POWER REACTORS USING METALLIC AND NITRIDE FUEL
    SEKIMOTO, H
    SUUD, Z
    NUCLEAR TECHNOLOGY, 1995, 109 (03) : 307 - 313
  • [30] Overview of the SAS4A Metallic Fuel Models and Extended Analysis of a Postulated Severe Accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor
    Tentner, A. M.
    Karahan, A.
    Kang, S. H.
    NUCLEAR TECHNOLOGY, 2020, 206 (02) : 242 - 254
1234