Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings

被引:79
|
作者
Wagih, Malik [1 ]
Spencer, Benjamin [2 ]
Hales, Jason [2 ]
Shirvan, Koroush [1 ]
机构
[1] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave, Cambridge, MA 02139 USA
[2] Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA
关键词
Accident tolerant fuel; Chromium; Silicon carbide; Cladding; Nuclear fuel; BISON; HIGH-TEMPERATURE OXIDATION; SIC-SIC COMPOSITES; NUCLEAR-FUEL; MECHANICAL-PROPERTIES; NEUTRON-IRRADIATION; FUKUSHIMA; FIBER;
D O I
10.1016/j.anucene.2018.06.001
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
The U.S. Department of Energy's Accident Tolerant Fuel program is focused on extending the time for fuel failure during postulated severe accidents compared to the standard UO2-Zr alloy fuel system. This paper investigates the feasibility of two different chromium-coated cladding concepts, one of which is zirconium-alloy based and the other is composite-SiC based. Both claddings had 50 mu m coatings, deducted from the base layer thicknesses. The claddings were studied, using the multi-physics fuel performance tool BISON, under steady-state PWR operating conditions as well as under two transients: a power ramp and a loss-of-coolant accident (LOCA). The chromium-coated claddings showed comparable thermo-mechanical performance to the reference Zircaloy-4 cladding. As chromium is reported to provide an order of magnitude improvement in oxidation resistance, it is expected to be a better alternative in accident scenarios. Simulation results for both concepts show that further experimental investigation as well as modeling of beyond design-basis accidents is warranted. (C) 2018 Elsevier Ltd. All rights reserved.
引用
收藏
页码:304 / 318
页数:15
相关论文
共 50 条
  • [21] Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings
    Song, Ligang
    Huang, Bo
    Li, Jianghua
    Ma, Xianfeng
    Liu, Min
    Jiang, Jishen
    Hu, Yanying
    ANNALS OF NUCLEAR ENERGY, 2021, 156
  • [22] IRRADIATION PERFORMANCE OF PYROLYTIC-CARBON-COATED FUEL PARTICLES AND SILICON-CARBIDE-COATED FUEL PARTICLES
    REAGAN, PE
    LONG, EL
    MORGAN, JG
    COOBS, JH
    NUCLEAR APPLICATIONS AND TECHNOLOGY, 1970, 8 (05): : 417 - &
  • [23] Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors
    Younan, Simon
    Novog, David
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2018, 2018
  • [24] Nickel-chromium (Ni-Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings
    Sidelev, Dmitrii V.
    Kashkarov, Egor B.
    Syrtanov, Maxim S.
    Krivobokov, Valery P.
    SURFACE & COATINGS TECHNOLOGY, 2019, 369 : 69 - 78
  • [25] Effect of chromium coated zircaloy cladding of accident tolerant fuel on the best estimate LOCA methodology
    Bae, Jae -Ho
    Hong, Soon-Joon
    Ro, Tae -Sun
    PROGRESS IN NUCLEAR ENERGY, 2022, 151
  • [26] Thermomechanical Assessment of Fuel Rod Cladding Made of Zirconium Alloy and Silicon Carbide Material During Reactivity-Initiated Accident
    Halabuk, David
    Navrat, Tomas
    NUCLEAR SCIENCE AND ENGINEERING, 2018, 189 (01) : 69 - 81
  • [27] Preparation and high temperature oxidation resistance of thick Cr coated on Zr-4 alloy by cathodic arc deposition for accident tolerant fuel claddings
    Hu, Xiao-Gang
    Dong, Chuang
    Chen, Bao-Qing
    Yang, Hong-Yan
    Zhang, Rui-Qian
    Gu, Wei
    Chen, Da-Min
    Surface Technology, 2019, 48 (02): : 207 - 219
  • [28] Elastoplastic Deformation and Fracture Behavior of Cr-Coated Zr-4 Alloys for Accident Tolerant Fuel Claddings
    Ma, Xianfeng
    Zhang, Wenjie
    Chen, Zejia
    Yang, Dong
    Jiang, Jishen
    Song, Ligang
    Tu, Jiajun
    Zhai, Hailin
    FRONTIERS IN ENERGY RESEARCH, 2021, 9
  • [29] Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview
    Pham, Hai V.
    Kurata, Masaki
    Steinbrueck, Martin
    THERMO, 2021, 1 (02): : 151 - 167
  • [30] Neutronic Performance Analysis of Inner-Side Chromium Coatings for Accident Tolerant Fuel
    Khlifa, Rofida Hamad
    Nikitenkov, Nicolay N.
    NUCLEAR TECHNOLOGY, 2023, 209 (09) : 1268 - 1281