Structural analysis of reactor fuel elements

Weeks, R.W.

doi:10.1016/0029-5493(78)90017-1

Cited by 8 publications

(3 citation statements)

References 42 publications

(32 reference statements)

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“…Large numbers of computer codes that simulate fuel behavior are available. Generally, those codes can be divided into three major categories which include simple correlation fuel performance codes, fuel model codes, and mechanistic fuel performance codes [67,72]. The latest category is of interest here, since the former categories provide simplistic representation of the fuel behavior that are limited to certain applications and cannot be used to extrapolate the fuel behavior.…”

Section: Vic Current Tools and Approachmentioning

confidence: 99%

Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

Palmiotti¹,

Cahalan²,

Pfeiffer³

et al. 2006

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This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits. Results reported in the AFCI series of technical memoranda frequently are preliminary in nature and subject to revision. Consequently, they should not be quoted or referenced without the author's permission

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Section: Vic Current Tools and Approachmentioning

confidence: 99%

Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

Palmiotti¹,

Cahalan²,

Pfeiffer³

et al. 2006

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“…R. W. Weeks (1978) presented an excellent overview of the capabilities and limitations of fuel performance codes in his Principal Division Lecture D/O at SMiRT-4 in San Francisco. Finally, K. Lassmann (1980) is cited for his excellent discussion and categorization of fuel element codes presented in paper D3/1 at SMiRT-5 in West Berlin.…”

Section: Introductionmentioning

confidence: 99%

Advancements in the behavioral modeling of fuel elements and related structures

Billone¹,

Montgomery²,

Rashid³

et al. 1992

Nuclear Engineering and Design

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An important aspect of the design and analysis of nuclear reactors is the ability to predict the behavior of fuel elements in the adverse environment of a reactor system. By understanding the thermomechanical behavior of the different materials which constitute a nuclear fuel element, analysis and predictions can be made regarding the integrity and reliability of fuel element designs. The SMiRT conference series, through the division on fuel elements and the post-conference seminar's on fuel element modeling, provided technical forums for the international participation in the exchange of knowledge concerning the thermomechanical modeling of fuel elements. This paper discusses the technical advances in the behavioral modeling of fuel elements presented at the SMiRT conference series since its inception in 1971. Progress in the areas of material properties and constitutive relationships, modeling methodologies, and integral modeling approaches was reviewed and is summarized in light of their impact on the thermomechanical modeling of nuclear fuel elements.

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“…A magnetita, o óxido de ferro-III, é a camada intermediária, um óxido magnético com estrutura cúbica, e ponto de fusão de 1592 °C. No caso do aço, as oxidações do ferro com o oxigênio são exotérmicas; ferro em contato com oxigênio produz óxido de ferro-I, FeO, e libera energia[12,47].As características dos óxidos originados no aço são complexas contendo além dos óxidos de ferro, os seguintes óxidos: CrO3, Cr2O3 e NiO e spinel. O procedimento de cálculo considera três parâmetros cinéticos: (i) a potência linear da oxidação; (ii) a espessura da camada formada;(iii) a taxa de oxidação.As correlações são referentes aos calores específicos dos óxidos[3,10].…”

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Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico

Gomes¹

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Structural analysis of reactor fuel elements

Cited by 8 publications

References 42 publications

Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

Advancements in the behavioral modeling of fuel elements and related structures

Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico

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