Fuel Pin and Assembly Design

This chapter deals with the mechanical designs of fuel pins and assemblies. These core components must be designed to withstand the high temperature, high flux environment of a fast spectrum reactor for a long irradiation exposure time. In this chapter we will describe many of the factors that influence this design, and we will examine in some detail the stress analysis of the fuel pin. We begin in Section 8.2 with the basic geometric and heat transfer relationships for the fuel pin, and then discuss some topics related to fuel and fission gas that must be considered in analysis of steady-state fuel-pin performance. The discussion of fuel-pin design is continued in Section 8.3, in which failure criteria and stress analysis are presented. Discussion is then shifted in Section 8.4 to grouping the pins into a fuel assembly. This will include discussion of mechanical design problems such as fuel-pin spacing and duct swelling.

[1]  R. W. Weeks,et al.  LIFE-II: A COMPUTER ANALYSIS OF FAST-REACTOR FUEL-ELEMENT BEHAVIOR AS A FUNCTION OF REACTOR OPERATING HISTORY. , 1972 .

[2]  W. H. Sutherland,et al.  AXICRP — Finite element computer code for creep analysis of plane stress, plane strain and axisymmetric bodies , 1970 .

[3]  R. A. Markley,et al.  Thermal analysis of liquid--metal fast breeder reactors , 1978 .

[4]  A. Mendelson Plasticity: Theory and Application , 1968 .

[5]  S. A. Chastain,et al.  Modeling of the fuel cladding postirradiation gap in mixed-oxide fuel pins , 1973 .

[6]  J. Straalsund,et al.  A new approach to stress-rupture data correlation , 1977 .

[7]  Peter L. Balise,et al.  Elements of Materials Science , 1959 .

[8]  D. Mohr,et al.  BOW-V: A CDC-3600 PROGRAM TO CALCULATE THE EQUILIBRIUM CONFIGURATIONS OF A THERMALLY BOWED REACTOR CORE. EBR-II Project. , 1970 .

[9]  Joseph Edward Shigley,et al.  Mechanical engineering design , 1972 .

[10]  Donald R. Olander,et al.  Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .

[11]  J. Bates,et al.  Dependence of irradiation creep on temperature and atom displacements in 20% cold worked type 316 stainless steel , 1977 .

[12]  F. L. Brown,et al.  Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux , 1969 .

[13]  E. R. Gilbert,et al.  Creep Deformation of 20 Percent Cold Worked Type 316 Stainless Steel , 1977 .

[14]  Donald R. Olander,et al.  Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .