Characterising the impact of castellations on the efficiency of induction heating during testing in the HIVE facility

Flinders, K.; Bamber, R.; Lewtas, Heather; Hancock, D. L.; Homfray, D.; Kamalu, John; Barrett, T.

doi:10.1016/j.fusengdes.2019.03.097

Cited by 2 publications

(3 citation statements)

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“…In this section, we will discuss results showing volumetric defects present in the DEMO divertor mock-up caused by the HHF test performed on the HIVE facility [17] at UKAEA. The specimen was studied non-destructively with a spatial resolution (voxel size) of 139 μm and a geometrical unsharpness of 119 μm.…”

Section: Resultsmentioning

confidence: 99%

“…From the neutron tomography tests [4], no major issues have been identified within the sample. Subsequently, the specimen was subjected to HHF loads with a single cycle at ∼8 MWm −2 on the HIVE facility [17] at United Kingdom Atomic Energy Authority (UKAEA). During this test, a loss of cooling flow was experienced which led to bulk boiling in the pipe-work and a subsequent expansion of the specimen in its central area.…”

Section: Demo Divertor Mock-up Sample and Previous Testingmentioning

confidence: 99%

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Are tungsten-based nuclear fusion components truly invisible to x-ray inspection?

Minniti

Lewtas

2022

Nucl. Fusion

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The ability to detect undesired volumetric defects in reactor components could affect the safety and reliability of a fusion power plant and change the expected lifetime and performance of the reactor. This is even more true for critical reactor parts like plasma-facing components which have to withstand challenging in-vessel conditions due to a combination of plasma bombardment, radiation, and nuclear heating. The structural integrity of these components prior to their installation in a nuclear fusion reactor needs to be assessed non-destructively. Until now, industrial X-ray radiography and tomography have not been used to non-destructively inspect fusion components due to their lack of penetration power into dense material such as tungsten which is often used to manufacture plasma-facing components. However, aiming to revert this consolidated belief, we have demonstrated for the first time the feasibility of assessing volumetric defects non-destructively on DEMO divertor mock-up by means of MeV energy range X-ray tomography. The authors believe that the application of this technology could be easily extended for inspecting large fusion components and positively impact procedures to be followed in the qualification of fusion components for current and future nuclear reactors.

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Section: Resultsmentioning

confidence: 99%

Section: Demo Divertor Mock-up Sample and Previous Testingmentioning

confidence: 99%

Are tungsten-based nuclear fusion components truly invisible to x-ray inspection?

Minniti

Lewtas

2022

Nucl. Fusion

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“…14 Therefore, it is very important to control the temperature distribution of the heated workpiece during the induction heating process. However, some challenges associated with the coil structure design 15,16 and selection of parameters, 17,18 including the heating time, current density, and current frequency, should be overcome during induction heating. Meanwhile, this process is complicated and relies on the trial-and-error method.…”

Section: Introductionmentioning

confidence: 99%

Experimental and numerical study of the effect of coil structure on induction nitriding temperature field

Song

Guan

et al. 2020

Advances in Mechanical Engineering

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The axial and radial temperature distributions of an induction heating workpiece considerably impact the subsequent nitriding process. To obtain a satisfactory temperature distribution, an equal pitch coil, a variable pitch coil, and a variable radius coil were designed. Furthermore, an induction heating model that exhibits electromagnetic and temperature field coupling was established; thus, the effects of the current density and frequency on the heating efficiency and temperature distribution of the workpiece were analyzed and compared. In addition, an induction heating experiment was conducted to verify the model. According to the numerical results, the variable radius coil can reduce the axial temperature difference in comparison with equal pitch coil and variable pitch coil. Hence, the workpiece heated using the variable radius coil can achieve a better temperature distribution when compared with those heated by the equal pitch coil and variable pitch coil, with appropriate current density and current frequency values.

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Characterising the impact of castellations on the efficiency of induction heating during testing in the HIVE facility

Cited by 2 publications

References 1 publication

Are tungsten-based nuclear fusion components truly invisible to x-ray inspection?

Are tungsten-based nuclear fusion components truly invisible to x-ray inspection?

Experimental and numerical study of the effect of coil structure on induction nitriding temperature field

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