Thermomechanical Assessment of Fuel Rod Cladding Made of Zirconium Alloy and Silicon Carbide Material During Reactivity-Initiated Accident

Halabuk, Dávid; Návrat, Tomáš

doi:10.1080/00295639.2017.1373518

Cited by 7 publications

(6 citation statements)

References 12 publications

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“…This concept showed low failure possibility in comparison to other concepts [17]. Previously done thermomechanical analysis on the multilayer SiC concept [18] showed more suitable results in fresh state during Reactivity Initiated Accident (RIA) than zircaloy cladding. An upgradation of this concept includes a triplex SiC cladding model [19], and an addition of an Environmental Barrier Coating (EBC) on the outer SiC CMC layer [20] SiC has been well researched as a possible cladding concept based on its material properties.…”

Section: Introductionmentioning

confidence: 81%

“…All material properties were considered isotropic. The thermal conductivities and the densities of the fuel and the SiC layers has been taken from [18]. The heat capacities of the fuel, mSiC and SiC/SiC has been taken from [28][29][30] respectively [28,31] has been referred for gap thermal properties.…”

Section: Materials Propertiesmentioning

confidence: 99%

“…The heat capacities of the fuel, mSiC and SiC/SiC has been taken from [28][29][30] respectively [28,31] has been referred for gap thermal properties. Zircaloy properties have been referred to from [18]. And, Volumetric specific heat capacity (Jm −3 K)=39336.975 K Where, T = temperature (K) q = the Einstein temperature (K)…”

Section: Materials Propertiesmentioning

confidence: 99%

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Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly

Handa¹,

Ray²,

Munshi³

et al. 2022

Eng. Res. Express

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A thermal-hydraulic analysis of a nuclear fuel rod subassembly of a Pressurized Water Reactor (PWR) has been performed during a Loss of Flow Accident (LOFA). Two different cladding materials are studied in this exercise namely, (a) conventional Zircaloy (Zr) and (b) a Silicon Carbide (SiC) cladding concept approach using monolithic SiC and SiC composite two-layer structure. The simulation is carried out by using USNRC licensed and AERB approved RELAP5/MOD3.4 code. A short-time problem is analyzed, neglecting the burnup change and irradiation effects. A transition into film boiling is observed in the upper part of the rod during LOFA, causing the convective heat transfer coefficient to decrease. The peak cladding temperatures and the Critical Heat Flux Ratio (CHFR) values of the two cladding materials are compared. From a safety perspective, the use of SiC is considered as it will be able to maintain performance during the operational transients.

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Section: Introductionmentioning

confidence: 81%

Section: Materials Propertiesmentioning

confidence: 99%

Section: Materials Propertiesmentioning

confidence: 99%

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Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly

Handa¹,

Ray²,

Munshi³

et al. 2022

Eng. Res. Express

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“…One uranium pellet (a cylinder of 10 mm × 8 mm, made of slightly enriched uranium dioxide) has as much energy available as three barrels of oil of 42 gallons each, or as one ton of coal, or as 17,000 cubic feet of natural gas. Such uranium pellets are inserted into a tube made of a zirconium alloy (the fuel rod cladding [71]) with a spring on top, and several such resulting fuel rods are arranged in parallel in a grid forming one fuel assembly ( Figure 1). Dozens of fuel assemblies (either new, or spent to different degrees) are present inside a nuclear reactor core at a given time [72].…”

Section: Preliminary Notions In Nuclear Engineering Concerning Fuel mentioning

confidence: 99%

An Overview of AI Methods for in-Core Fuel Management: Tools for the Automatic Design of Nuclear Reactor Core Configurations for Fuel Reload, (Re)arranging New and Partly Spent Fuel

Nissan

2019

Designs

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An important aspect of managing a nuclear reactor is how to design refuellings, and from the 1980s to the present different artificial intelligence (AI) techniques have been applied to this problem. A section of the reactor core resembles a symmetrical grid; long fuel assemblies are inserted there, some of them new, some of them partly spent. Rods of “burnable poisons” dangle above, ready to be inserted into the core, in order to stop the reactor. Traditionally, manual design was made by shuffling positions in the grid heuristically, but AI enabled to automatically generate families of candidate configurations, under safety constraints, as well as in order to optimize combustion, with longer cycles of operation between shutdown periods, thus delaying the end-of-cycle point (except in France, where shutdown is on an annual basis, and Canada, where individual fuel assemblies are replaced, with no need for shutdown for rearranging the entire batch). Rule-based expert systems, the first being FUELCON,1 were succeeded by projects combining neural and rule-based processing (a symbolic-to-neural compilation of rules we did not implement), and later on, genetic algorithms in FUELGEN.2 In the literature, one also comes across the application of fuzzy techniques, tabu search, cellular automata and simulated annealing, as well as particle swarms. Safety regulations require simulating the results using a parameter prediction tool; this is done using either nodal algorithms, or neural processing.

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“…These have been studied by scanning electron microscopy to reveal the changes in microstructure [6]. This can be advantageously used for examination of transition layers or weldments not only for quasi-static loadings but also for creep [7].…”

Section: Introductionmentioning

confidence: 99%

The role of punch eccentricity in small punch testing

Šebek

Dymáček

Kubík

et al. 2018

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The small punch testing technique under quasi-static loading was examined in the view of punch eccentricity role. It might arise especially when the ball is used as the penetrating tool, instead of hemisphericalended punch. The austenitic stainless steel AISI 316L was chosen to execute several various "large scale" tests in order to calibrate the multi-linear stress-strain relationship along with the ductile fracture criterion KHPS. All the calibration procedure was performed without using the small punch testing. Then, the model was applied to small punch tests to observe the prediction ability when compared to real small punch experiments. Consequently, a numerical study was conducted to see the role of eccentricity in the case of 2 and 2.5 mm ball diameters used as the penetrating tool. The magnitude of eccentricity up to 0.3 mm was numerically tested. The results showed negligible role of eccentricity for 2 mm ball diameter and minor role for 2.5 mm diameter and studied material.

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Thermomechanical Assessment of Fuel Rod Cladding Made of Zirconium Alloy and Silicon Carbide Material During Reactivity-Initiated Accident

Cited by 7 publications

References 12 publications

Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly

Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly

An Overview of AI Methods for in-Core Fuel Management: Tools for the Automatic Design of Nuclear Reactor Core Configurations for Fuel Reload, (Re)arranging New and Partly Spent Fuel

The role of punch eccentricity in small punch testing

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