Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux

O'Boyle, D.R.; Brown, F.L.; Sanecki, J.E.

doi:10.1016/0022-3115(69)90124-x

Cited by 82 publications

(18 citation statements)

References 10 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The maximum solubility of SrO in UO 2 was experimentally 95 found to be much higher in UO 2 than in UO 2-x , which mirrors our calculated trend. This can be explained on the fact that the solution of strontium becomes increasingly favorable as one approaches hyperstoichiometric conditions owing to the strong Coulombic interactions.…”

Section: +supporting

confidence: 90%

See 1 more Smart Citation

The Development of Models to Optimize Selection of Nuclear Fuels through Atomic-Level Simulation

Sinnott¹,

Seifert²,

Tulenko³

2009

View full text Add to dashboard Cite

Section: +supporting

confidence: 90%

“…Considering individual oxides, Cs 2 O is predicted to be stable at all stoichiometries, though in UO 2+x , it is on the borderline of stability. With regard to UO 2+x , it is also observed experimentally 95 that the solubility of Cs increases as we go from hypostoichiometric to hyperstoichiometric fuels. Our calculations support this argument.…”

Section: +mentioning

confidence: 76%

The Development of Models to Optimize Selection of Nuclear Fuels through Atomic-Level Simulation

Sinnott¹,

Seifert²,

Tulenko³

2009

View full text Add to dashboard Cite

“…No melting [6] center of the pellet leaves a more fully dense fuel material behind and this can result in a large hole in the center of the pellet. Most of this restructuring occurs in a matter of hours at full power.…”

Section: Fig 85mentioning

confidence: 98%

“…It has smaller diameter pins (5.8 mm) than a typical power SFR. 6 Pores are tiny void spaces purposely fabricated into the fuel to allow space for fuel swelling and expansion during steady-state and thermal upset conditions. Porosity is the fraction of the fuel volume that is void.…”

Section: Fuel Restructuringmentioning

confidence: 99%

Fuel Pin and Assembly Design

Waltar

Todd²

2011

Fast Spectrum Reactors

View full text Add to dashboard Cite

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

show abstract

“…Cesium and molybdenum can be soluble or insoluble depending on conditions, most notably the oxygen activity. [1][2][3] Consequently, voids, gas bubbles, second phases, and new compounds are formed continuously during the service life of the pellet, and during post-service storage. To add further complexity, pellet-clad interactions can lead to additional chemical changes in the fuel.…”

Section: Introductionmentioning

confidence: 99%

Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation

Phillpot

El–Azab²,

Chernatynskiy

et al. 2011

JOM

View full text Add to dashboard Cite

How would you……describe the overall significance of this paper? Atomistic level simulations have not traditionally contributed to nuclear fuel performance simulations. However, recent advances in methodologies and computer power are now enabling atomic level simulations to provide mechanistic insights and parameters that can help in the development of performance codes.…describe this work to a materials science and engineering professional with no experience in your technical specialty? Predicting the thermal and mechanical properties of nuclear fuel is a difficult task due to the many length and time scales involved. In this paper we discuss how the results obtained at the atomistic scale contribute to the continuum models of the standard nuclear fuel performance codes.…describe this work to a layperson? Nuclear reactor performance depends crucially on the ability of the nuclear fuel to transport energy generated by the nuclear reaction to the electricity generating station. This ability is influenced greatly by the structure of the fuel at the very fine scale: down to the position of the individual atoms. In this paper we discuss how computer simulations are able to penetrate to this scale and help to predict energy transport characteristics of the nuclear fuel.Recent progress in understanding the thermal-transport properties of UO 2 for fission reactors is reviewed from the perspective of computer simulations. A path to incorporating more accurate materials models into fuel performance codes is outlined. In particular, it is argued that a judiciously integrated program of atomic-level simulations and mesoscale simulations offers the possibility of both better predicting the thermal-transport properties of UO 2 in light-water reactors and enabling the assessment of the thermal performances of novel fuel systems for which extensive experimental databases are not available.

show abstract

Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux

Cited by 82 publications

References 10 publications

The Development of Models to Optimize Selection of Nuclear Fuels through Atomic-Level Simulation

The Development of Models to Optimize Selection of Nuclear Fuels through Atomic-Level Simulation

Fuel Pin and Assembly Design

Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation

Contact Info

Product

Resources

About