ASYMMETRIC FUEL-CLADDING GAP CONDUCTANCE AND FUEL PIN THERMAL PERFORMANCE

被引：0
|
作者：
MCNARY, O [1 ]
BAUER, TH [1 ]
机构：
[1] ARGONNE NATL LAB, ARGONNE, IL 60439 USA
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1979年 / 33卷 / NOV期
关键词：
D O I：
暂无
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：
引用
收藏
页码：275 / 276
页数：2
相关论文
共 50 条
  • [31] Simulation of Asymmetric Fuel Thermal Behavior Using 3D Gap Conductance Model
    Kang, Chang Hak
    Lee, Sung Uk
    Yang, Dong Yol
    Kim, Hyo Chan
    Yang, Yong Sik
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A, 2015, 39 (03) : 249 - 257
  • [32] Distributions of volatile fission products in or near the fuel-cladding gap of the FBR MOX fuel pins irradiated to high burn-up
    Maeda, K
    Tanaka, K
    Asaga, T
    Furuya, H
    JOURNAL OF NUCLEAR MATERIALS, 2005, 344 (1-3) : 274 - 280
  • [33] THE EFFECT OF CIRCUMFERENTIAL TEMPERATURE-VARIATION ON FUEL-CLADDING FAILURE
    FERNER, J
    ROSINGER, HE
    JOURNAL OF NUCLEAR MATERIALS, 1985, 132 (02) : 167 - 172
  • [34] Quenching of candidate materials for accident tolerant fuel-cladding in LWRs
    Kang, Jun-Young
    Kim, Tong Kyun
    Lee, Gi Cheol
    Kim, Moo Hwan
    Park, Hyun Sun
    ANNALS OF NUCLEAR ENERGY, 2018, 112 : 794 - 807
  • [35] FUEL-CLADDING CHEMICAL INTERACTION DUE TO IODINE INDUCED BY IRRADIATION
    KONASHI, K
    KANEKO, H
    YAMAWAKI, M
    KANNO, M
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 45 : 275 - 276
  • [36] EXPERIMENTAL INVESTIGATION OF THE GAP CONDUCTANCE BETWEEN FUEL AND CLADDING OF LIGHT-WATER REACTOR-FUEL RODS
    NEUER, G
    MINH, TN
    ATOMKERNENERGIE-KERNTECHNIK, 1985, 47 (04): : 229 - 231
  • [37] Microstructural Analysis of Zirconia at the Fuel-Cladding Interface in Medium and High Burnup Irradiated Fuel Rods
    C. Schneider
    L. Fayette
    I. Zacharie-Aubrun
    T. Blay
    J. Sercombe
    J. Favergeon
    S. Chevalier
    Oxidation of Metals, 2021, 96 : 295 - 306
  • [38] Microstructural Analysis of Zirconia at the Fuel-Cladding Interface in Medium and High Burnup Irradiated Fuel Rods
    Schneider, C.
    Fayette, L.
    Zacharie-Aubrun, I
    Blay, T.
    Sercombe, J.
    Favergeon, J.
    Chevalier, S.
    OXIDATION OF METALS, 2021, 96 (3-4): : 295 - 306
  • [39] Further observations on OCOM MOX fuel: Microstructure in the vicinity of the pellet rim and fuel-cladding interaction
    Walker, CT
    Goll, W
    Matsumura, T
    JOURNAL OF NUCLEAR MATERIALS, 1997, 245 (2-3) : 169 - 178
  • [40] Micro-Raman analysis of the fuel-cladding interface in a high burnup PWR fuel rod
    Ciszak, Clement
    Mermoux, Michel
    Miro, Sandrine
    Gutierrez, Gaelle
    Lepretre, Frederic
    Popa, Ioana
    Hanifi, Karine
    Zacharie-Aubrun, Isabelle
    Fayette, Laurent
    Chevalier, Sebastien
    JOURNAL OF NUCLEAR MATERIALS, 2017, 495 : 392 - 404
12345