SIMILARITY OF 2-FLUID FLOW HEATED BY A FUEL-ROD

被引:1
|
作者
BENEDEK, S
机构
[1] Inst for Electrical Power Research, Budapest
关键词
SCALING LAWS; 2-FLUID FLOW; NUMERICAL EXAMPLES;
D O I
10.13182/NT94-A34923
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
General scaling laws for transient two-fluid flow heated by a rod are presented. The similarity of these processes can be ensured only by applying the same volume and time scale with identical model parameters. In practice, the requirement of similar interfacial friction terms cannot be fulfilled because of volume (diameter) reducing scale. Numerical examples show remarkable deviations between the state variables (the values of slip) of the prototype and those of the scaled model, especially with unsteady flow rates. The deviation becomes significant when the slip of phase velocities exceeds the range of 1.6 to 1.8. Volume and time scaling can be carried out only if the phase velocities are similar (slip equal to approximately 1 in the quasi-homogeneous flow model). Maintenance of the similarity of heat transfer processes of a heated fuel rod may necessitate time scaling. Furthermore, numerical examples are presented for a scale model of a prototype pressurized water reactor, employing the time-scaled homogeneous flow model.
引用
收藏
页码:201 / 215
页数:15
相关论文
共 50 条
  • [41] Accident Tolerant Fuel with Chromium-Coated Fuel-Rod Cladding
    L. A. Karpyuk
    V. I. Kuznetsov
    A. A. Maslov
    V. V. Novikov
    V. K. Orlov
    D. V. Rykunov
    A. O. Titov
    Atomic Energy, 2021, 130 : 149 - 155
  • [42] DEVELOPMANT AND TESTING OF A FUEL-ROD CHOPPER FOR A REPROCESSING PLANT
    DLUZNIEWSKI, E
    WALTHER, HJ
    KERNTECHNIK ISOTOPENTECHNIK UND CHEMIE, 1967, 9 (06): : 246 - +
  • [43] MECHANICAL ANALYSIS OF THE FUEL-ROD WITH THE KWU CODE SENATOR
    HERING, W
    RES MECHANICA, 1986, 18 (03): : 191 - 200
  • [44] DEVELOPMENT OF PCI-RESISTANT FUEL-ROD DESIGNS
    VESTERLUND, G
    VAERNILD, O
    BRANZELL, HG
    JUNKRANS, S
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 34 (JUN): : 208 - 209
  • [45] OXIDATION OF FUEL-ROD UNDER DRY STORAGE CONDITION
    NAKAMURA, J
    OTOMO, T
    KIKUCHI, T
    KAWASAKI, S
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1995, 32 (04) : 321 - 332
  • [46] An experimental study of reflooding in a VVER fuel-rod assembly
    Balashov, S.M.
    Kon'kov, A.S.
    Zemlyanukhin, V.V.
    Teploenergetika, 1999, 46 (06): : 26 - 32
  • [47] AN EXPERIMENTAL DETERMINATION OF DANCOFF EFFECT IN FUEL-ROD ARRAYS
    GLASS, CD
    STUBBINS, WF
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (02): : 520 - +
  • [48] MULTIPURPOSE BENCH FOR IN-CELL FUEL-ROD EXAMINATION
    CHEVALIER, M
    BROCHIER, M
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 471 - 472
  • [49] ONLINE FUEL-ROD PERFORMANCE-MEASUREMENTS AND FUEL INSPECTION APPLICATIONS
    VITANZA, C
    KERNTECHNIK, 1991, 56 (02) : 124 - 130
  • [50] LWR FUEL-ROD BEHAVIOR DURING SEVERE ACCIDENTS
    HAGEN, S
    HOFMANN, P
    NUCLEAR ENGINEERING AND DESIGN, 1987, 103 (01) : 85 - 106