Experimental studies of U-Pu-Zr fast reactor fuel pins in the experimental breeder reactor-ll

Pahl, R.; Porter, David; Lahm, C.E.; Hofman, G.L.

doi:10.1007/bf02647233

Cited by 104 publications

(37 citation statements)

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“…As fuel elements were irradiated for longer times, the inventory of fission products continued to grow and over time the fission products were found to migrate towards the fuel/cladding interface [4]. Eventually, the fuel contacted the cladding and localized interaction occurred, which resulted in diffusion of lanthanide fission products (and minor amounts of other fission products) along with U and Pu from the fuel into the cladding [5]. In addition, the Fe and Ni interdiffused from the cladding into the fuel.…”

Section: Introductionmentioning

confidence: 99%

Fuel-cladding interaction layers in irradiated U-ZR and U-PU-ZR fuel elements.

Keiser¹

2006

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Section: Introductionmentioning

confidence: 99%

Fuel-cladding interaction layers in irradiated U-ZR and U-PU-ZR fuel elements.

Keiser¹

2006

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“…It should be mentioned that pure metallic fuel with the density of 19.1 g/cm 3 is used in this paper, which is in favor of breeding and the asymptotic keff level, but would not be so realistic for a high burn-up. Usually the zirconium alloyed metallic fuel with the density of 15.8 g/cm 3 , see e.g., [27], were used. …”

Section: Data Preparationmentioning

confidence: 99%

Asymptotic Solutions of Serial Radial Fuel Shuffling

Chen

Kiefhaber

2015

Energies

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Abstract:In this paper, the mechanism of traveling wave reactors (TWRs) is investigated from the mathematical physics point of view, in which a stationary fission wave is formed by radial fuel drifting. A two dimensional cylindrically symmetric core is considered and the fuel is assumed to drift radially according to a continuous fuel shuffling scheme. A one-group diffusion equation with burn-up dependent macroscopic coefficients is set up. The burn-up dependent macroscopic coefficients were assumed to be known as functions of neutron fluence. By introducing the effective multiplication factor keff, a nonlinear eigenvalue problem is formulated. The 1-D stationary cylindrical coordinate problem can be solved successively by analytical and numerical integrations for associated eigenvalues keff. Two representative 1-D examples are shown for inward and outward fuel drifting motions, respectively. The inward fuel drifting has a higher keff than the outward one. The 2-D eigenvalue problem has to be solved by a more complicated method, namely a pseudo time stepping iteration scheme. Its 2-D asymptotic solutions are obtained together with certain eigenvalues keff for several fuel inward drifting speeds. Distributions of the neutron flux, the neutron fluence, the infinity multiplication factor kinf and the normalized power are presented for two different drifting speeds.

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“…Temperatures higher than 725 0 C can cause actinide diffusion into the cladding and lead to low-melting-point regions resulting in clad thinning and potential failure [17]. These conditions have therefore been deemed unacceptable.…”

Section: Success Criteriamentioning

confidence: 99%

Reliability analysis of a passive cooling system using a response surface with an application to the flexible conversion ratio reactor

Fong

Apostolakis

Langewisch

et al. 2009

Nuclear Engineering and Design

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A comprehensive risk-informed methodology for passive safety system design and performance assessment is presented and demonstrated on the Flexible Conversion Ratio Reactor (FCRR). First, the methodology provides a framework for risk-informed design decisions and as an example two design options for a decay heat removal system are assessed and quantitatively compared. Next, the reliability of the system is assessed by quantifying the uncertainties related to system performance and propagating these uncertainties through a response surface using Monte Carlo simulation. Finally, a sensitivity study is performed to measure the relative effects of each parameter and to identify ways to maintain, improve, and monitor system performance. A common characteristic of passive safety systems is that their driving force tends to be weak and therefore adverse or off-normal conditions may substantially degrade system performance [2]. Under certain conditions, system performance may be degraded to a level that results in unacceptable consequences. These consequences are typically identified by the system designer and are referred to as failure criteria. Failure criteria can be defined at the system level (e.g., flow rate, fluid temperature) or at a higher level (e.g., peak cladding temperature, containment pressure). Therefore, the conditional failure probability of a passive system can be defined as the probability that, given an initiating event, a set of thermal-hydraulic conditions will exist that cause the system to exceed one or more failure criteria. System conditions leading to failure are the result of adverse combinations of system parameter values such as pressure, temperature, and void fraction. Prediction of the exact values of these parameters is made difficult by several sources of uncertainty and typically, we can only assume a range of expected values and a corresponding probability distribution. We will refer to this type of uncertainty as parametric uncertainty. Second, there are uncertainties associated with the models used to predict system behavior. These can involve equations or empirical correlations used to model various phenomena or may stem from the numerical methods employed by computer codes. We will refer to this type of uncertainty as model uncertainty. Both parametric and model uncertainties are classified as epistemic since they are related to a lack of knowledge as opposed to aleatory uncertainty, which is related to randomness [3]. An estimate of system reliability can be obtained by quantifying parametric and model uncertainty and observing their effect on system performance. Further insights can be gained by evaluating the sensitivity of system performance to each parameter, and we will demonstrate several ways in which this can be done.The reliability of passive safety systems has been the subject of a great deal of research this decade both in the United States and internationally. System failure is assumed to occur when a physical quantity such as temperature exceeds a value th...

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Experimental studies of U-Pu-Zr fast reactor fuel pins in the experimental breeder reactor-ll

Cited by 104 publications

References 1 publication

Fuel-cladding interaction layers in irradiated U-ZR and U-PU-ZR fuel elements.

Fuel-cladding interaction layers in irradiated U-ZR and U-PU-ZR fuel elements.

Asymptotic Solutions of Serial Radial Fuel Shuffling

Reliability analysis of a passive cooling system using a response surface with an application to the flexible conversion ratio reactor

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