BOW-V: A CDC-3600 PROGRAM TO CALCULATE THE EQUILIBRIUM CONFIGURATIONS OF A THERMALLY BOWED REACTOR CORE. EBR-II Project.

Kucera, D.A.; Mohr, Dirk

doi:10.2172/4157753

Cited by 8 publications

(6 citation statements)

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“…None of the calculated curves reproduces the localized moat formation that occurred. The 50 and 60 lb pad-load curves do show total displacements as large as measured, but according to recent BOW-V calculations the pad loads should be less than 25 lb, rather than more [53]. No additional calculations of this type are planned until either (a) AXICRP has been modified to account for local swelling effects that have been observed [49] Cand that might influence moat formation), or (b) additional evidence accumulates that indicates the creep correlation employed generates low values.…”

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confidence: 72%

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Implications of Metal Swelling in Fast Reactor Design.

Huebotter¹,

Bump²

1971

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confidence: 72%

“…Because no public code exists that accounts for both creep and interactions of assemblies, the BOW-V [53], and CRASIB [54,55] codes are being combined.…”

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confidence: 99%

Implications of Metal Swelling in Fast Reactor Design.

Huebotter¹,

Bump²

1971

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“…Each core configuration has to be individually assessed. Complex code systems such as CRASIB [32], AXICRP [33], and BOW-V [34] have been developed to analyze such systems. Figure 8.24 contains a calculational sample for CRASIB, which qualitatively illustrates the bowing pattern emerging from various clamped and unclamped configurations (where clamping occurs at three axial levels: core support structure, top of the core, and top of duct).…”

Section: Duct Bowingmentioning

confidence: 99%

Fuel Pin and Assembly Design

Waltar

Todd²

2011

Fast Spectrum Reactors

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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. Limited attention is then directed to the design of other assemblies, including blanket, control and shielding assemblies. The final section of the chapter will provide a description of methods to restrain the assemblies and to control duct bowing. Fuel Pin Design ConsiderationsFuel pin design is a complex process that involves an integration of a wide range of phenomena. The design procedure must integrate the thermal analysis of the pin with an assessment of the characteristics of the fuel and cladding as a function of temperature and irradiation history and with the stress analysis of the fuel-cladding system. Many of the phenomena that affect fuel pin performance are illustrated schematically in Fig. 8.1. Each of these will be treated in Chapters 8 and 9, with additional discussions in Chapter 11. It should be readily apparent that there is no single way to order the examination of so many interacting phenomena. Each sequence selected to cover these tightly coupled processes will inherently suffer from the need for input from processes not yet discussed. In actual design practice, all of the governing processes are integrated in large time-dependent pin analysis codes such as LIFE [1].Our presentation will begin with the geometrical arrangement of the various sections of a fuel pin, including the function of each section. We will then extend the discussion of pin geometry to the selection of pin diameter. This will involve the concept of linear power. Fuel restructuring is then introduced, followed by fission gas release and the associated length of the gas plenum to establish A. Waltar (B) Pacific Northwest

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“…( 9 ). In terms of the three components Mo, M, 13 and Mzrr 1 s, on the other hand, any bending moment can be expressed in three ways, since one degree of freedom is added to the expression through the three components.…”

Section: (9)mentioning

confidence: 99%

Analytical Method of Fuel Pin Deformations in LMFBR Assembly

Miki

1977

J. Nucl. Sci. Technol.

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A new analytical method is presented for analyzing, in three dimensions, the mechanical response of fuel pins with wire spacers, to their thermal and neutronic environment in a fuel assembly of a LMFBR. It analyzes the mechanical interactions between fuel pins in the assembly in each of three directions, which form an angle of 7t/3 radians with one another, based on the mathematical relationship between the displacements at the contact points and the associated contact forces with respect to all fuel pins forming a line in one of the three directions.Based on this method, a new computational code, the Subchannel Deformation Analysis Code for Wire-Wrap Assemblies (SHADOW) has been developed, and is applied to a fuel assembly of a prototype fast breeder reactor in order to analyze the deformation of 169 fuel pins due to thermal bowing.Conclusions drawn from the study confirm that the SHADOW code can be an effective tool for analyzing or evaluating thermal and structural designs of a LMFBR fuel assembly.

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BOW-V: A CDC-3600 PROGRAM TO CALCULATE THE EQUILIBRIUM CONFIGURATIONS OF A THERMALLY BOWED REACTOR CORE. EBR-II Project.

Cited by 8 publications

References 0 publications

Implications of Metal Swelling in Fast Reactor Design.

Implications of Metal Swelling in Fast Reactor Design.

Fuel Pin and Assembly Design

Analytical Method of Fuel Pin Deformations in LMFBR Assembly

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