PFR fuel cladding transient test results and analysis

Cannon, N.S.; Hunter, C.W.; Kear, K.L.; Wood, M.H.

doi:10.1016/0022-3115(86)90164-9

Cited by 8 publications

(3 citation statements)

References 3 publications

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“…Due both to low fissile fraction and low neutron flux, 15 the volumetric heat generation rate in the blanket fuel is much lower than in the core fuel. Hence, blanket pins can be larger in diameter than core pins while maintaining linear powers, χ , no greater than linear powers in the core.…”

Section: Blanket Assembliesmentioning

confidence: 98%

“…The reader should be cautioned that occurrence of the FAE phenomenon appears to occur in some cladding types, such as 316 stainless steel, and not others [14,15]; hence, the details of this analysis will depend upon the material type. The appearance or lack of appearance of the FAE phenomenon demonstrates the critical need for detailed testing of any proposed cladding material.…”

Section: Correlations For Time-to-failurementioning

confidence: 99%

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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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Section: Blanket Assembliesmentioning

confidence: 98%

Section: Correlations For Time-to-failurementioning

confidence: 99%

Fuel Pin and Assembly Design

Waltar

Todd²

2011

Fast Spectrum Reactors

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“…Nevertheless, the presence of the fuel has been shown to influence the response of the cladding. In stainless steel cladding, void swelling has been shown to increase and fracture strength to decrease in fueled pins relative to unfueled pins (Cannon et al 1986;Uwaba et al 2002). Some of the differences can be explained by the more complex stress and temperature histories experienced by fueled pins, and in addition, to the effect of solid fission products that react with the interior surface of the cladding.…”

Section: Scientific Challengesmentioning

confidence: 99%

Basic Research Needs for Advanced Nuclear Systems. Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems, July 31-August 3, 2006

Roberto¹,

Rubia²,

Gibala³

et al. 2006

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The cover depicts two cesium ions (orange) bound inside a molecule that belongs to the calixarene-crown ethers family. These calixarenes are capable of selectively separating more than 99.9975% of the cesium ions from million-fold-higher concentrations of other ions. By studying how such molecules function as extractants, scientists have developed a process * employing a derivative of the cover molecule that is the basis of the Salt Waste Processing Facility being built at the Savannah River Site to remove trace amounts of cesium and other radionuclides from waste left over from reprocessing spent fuel.The graphic is based on an experimentally determined structure † and shows nitrogen atoms in blue, oxygen atoms in red, and carbon ions in gray. The hydrogen atoms bound to each carbon are not shown.

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