Development of Finite Element Analysis Code SPOTBOW for Prediction of Local Velocity and Temperature Fields around Distorted Fuel Pin in LMFBR Assemblies

この論文にアクセスする

この論文をさがす

著者

抄録

A two-dimensional steady-state distributed parameter code SPOTBOW has been developed for predicting the fine structure of cladding temperature in an liquid metal fast breeder reactor (LMFBR) fuel assembly where the deformation of fuel pins is induced by irradiation swelling, creep and thermal distortion under high burn-up operating condition. When the deformed fuel pin approaches adjacent pins and wrapper tube and comes in contact with those, the peak temperature, known as the hot spot temperature, can appear somewhere on the outer surface of the cladding. The temperature rise across the film is an important consideration in the cladding temperature analysis. Fully developed turbulent momentum and heat transfer equations based on the empirical turbulent model are solved by using the Galerkin finite element method which is suitable for the problem of the complicated boundary shape, such as the wire-wrapped fuel pin bundle. A new iteration procedure has been developed for solving the above equations by using the rise in coolant temperature, which is obtained with subchannel analysis codes, as a boundary condition. Calculated results are presented for local temperature distribution in normal and bowing pin bundle geometry, as compared with experiments.

収録刊行物

  • Journal of nuclear science and technology

    Journal of nuclear science and technology 33(5), p.429-438, 1996-05-25

    Atomic Energy Society of Japan

参考文献:  18件中 1-18件 を表示

  • <no title>

    MOLLER R.

    Nucl. Eng. Des. 62, 69, 1980

    被引用文献1件

  • <no title>

    NIJSING R.

    Prog. Heat Transfer 7, 115, 1971

    被引用文献1件

  • <no title>

    HOFMANN F.

    Nucl. Eng. Des. 14, 43, 1970

    被引用文献1件

  • <no title>

    DWYER O. E.

    Nucl. Eng. Des. 23, 273, 1972

    被引用文献1件

  • <no title>

    CHUANG M. C.

    Nucl. Eng. Des. 35, 21, 1975

    被引用文献1件

  • <no title>

    SHIMIZU T.

    J. Nucl. Sci. Technol. 15, 628, 1978

    被引用文献1件

  • <no title>

    AOKI S.

    Bull. Tokyo Inst. Technol. 54, 1953

    被引用文献1件

  • <no title>

    REHME K.

    Nucl. Eng. Des. 62, 137, 1980

    被引用文献1件

  • <no title>

    FINLAYSON B. A.

    The Method of Weighted Residuals and Variational Principles 226, 1972

    被引用文献2件

  • <no title>

    HOOD P.

    Int. J. Numer. Methods Eng. 10, 379, 1976

    被引用文献1件

  • <no title>

    SHIMIZU T.

    Nucl. Eng. Des. 120, 369, 1990

    被引用文献1件

  • <no title>

    ZEGGLE W.

    5th IAHR Specialists Meeting on Liquid Metals Thermal-Hydraulics, Grenoble, 1986

    被引用文献1件

  • <no title>

    EIFLER W.

    Nucl. Eng. Des. 5, 22, 1967

    被引用文献1件

  • <no title>

    TRUPP A. C.

    Nucl. Eng. Des. 32, 47, 1975

    被引用文献1件

  • <no title>

    RAMM H.

    Trans. ASME. J. Heat Transfer, 1975

    被引用文献1件

  • <no title>

    NIJSING R.

    Proc. Int. Meeting on Reactor Heat Transfer, Karlsruhe, Germany, 1973

    被引用文献1件

  • <no title>

    EIFLER W.

    EUR-4950e, 1973

    被引用文献1件

  • <no title>

    SCHLICHTING H.

    Boundary Layer Theory 504, 1960

    被引用文献2件

各種コード

  • NII論文ID(NAID)
    10002074840
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • データ提供元
    CJP書誌  J-STAGE 
ページトップへ