On the validity of the dilute gas assumption for gap conductance calculations in nuclear fuel performance codes

被引:7
|
作者
Toptan, Aysenur [1 ]
Kropaczek, David J. [1 ,2 ]
Avramova, Maria N. [1 ]
机构
[1] NC State Univ, Dept Nucl Engn, Raleigh, NC 27695 USA
[2] Oak Ridge Natl Lab, Reactor & Nucl Syst, Oak Ridge, TN 37381 USA
关键词
Fill gas thermal conductivity; Gap conductance; Fuel performance; Doppler; Mixture thermal conductivity; Rod internal pressure; Dilute; Dense; RESEARCH-AND-DEVELOPMENT; THERMAL-CONDUCTIVITY; BINARY-MIXTURES; MULTIPARAMETER CORRELATION; ROOM-TEMPERATURE; ORGANIC VAPORS; NOBLE-GASES; VISCOSITY; TRANSPORT; ARGON;
D O I
10.1016/j.nucengdes.2019.04.042
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
Fill gas thermal conductivity's dependence on pressure is neglected in today's nuclear fuel performance codes. Current codes assume that gas behaves as a dilute gas, but the pressure effect is more pronounced at temperatures lower than ten times the critical temperature of each pure gas. The validity of this assumption for nuclear fuel performance is examined herein. Theories related to dilute and dense gas properties are presented, along with their validation against literature data at up to 30 MPa for selected inert gases. Underlying assumptions are clearly described for each model, and their possible impacts on gap conductance calculations are discussed. The dilute gas assumption is valid for helium because it behaves as a dilute gas. However, the assumption is not valid in most gap conductance calculations when the gap is mostly occupied with either lower conductivity gaseous fission products or an initial fill gas other than helium.
引用
收藏
页码:1 / 8
页数:8
相关论文
共 25 条
  • [1] A MODEL FOR GAP CONDUCTANCE IN NUCLEAR-FUEL RODS
    LOYALKA, SK
    NUCLEAR TECHNOLOGY, 1982, 57 (02) : 220 - 227
  • [2] TRANSIENT GAP CONDUCTANCE IN NUCLEAR-FUEL RODS
    DHARMADURAI, G
    NUCLEAR TECHNOLOGY, 1995, 112 (02) : 295 - 298
  • [3] A review of nuclear fuel performance codes
    Aybar, HS
    Ortego, P
    PROGRESS IN NUCLEAR ENERGY, 2005, 46 (02) : 127 - 141
  • [4] ASYMMETRIC FUEL-CLADDING GAP CONDUCTANCE AND FUEL PIN THERMAL PERFORMANCE
    MCNARY, O
    BAUER, TH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 275 - 276
  • [5] THE EFFECT OF ASYMMETRIC FUEL-CLAD GAP CONDUCTANCE ON FUEL PIN THERMAL PERFORMANCE
    MCNARY, O
    BAUER, TH
    NUCLEAR ENGINEERING AND DESIGN, 1981, 63 (01) : 39 - 46
  • [6] A review of the development of nuclear fuel performance analysis and codes for PWRs
    Ding, Ming
    Zhou, Xuhua
    Zhang, Haojie
    Bian, Haozhi
    Yan, Qiang
    ANNALS OF NUCLEAR ENERGY, 2021, 163
  • [7] Relaxation effects in nuclear fuel coupled calculations using serpent-OpenFOAM codes
    Korinek, Tomas
    Zavorka, Jiri
    Lovecky, Martin
    Skoda, Radek
    PROGRESS IN NUCLEAR ENERGY, 2024, 173
  • [8] Numerical verification of equilibrium thermodynamic computations in nuclear fuel performance codes
    Piro, M. H. A.
    Besmann, T. M.
    Simunovic, S.
    Lewis, B. J.
    Thompson, W. T.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 414 (03) : 399 - 407
  • [9] A coupling methodology for mesoscale-informed nuclear fuel performance codes
    Tonks, Michael
    Gaston, Derek
    Perrnann, Cody
    Millett, Paul
    Hansen, Glen
    Wolf, Dieter
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) : 2877 - 2883
  • [10] EFFECTS OF FILL-GAS COMPOSITION AND ECCENTRIC GAP GEOMETRY ON GAP CONDUCTANCE OF UO2 FUEL RODS
    WILLIFORD, RE
    HANN, CR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 324 - 325