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Going Nuclear: Notes from the officially unofficial book tour
I work in the analytical labs at one of Europe’s oldest and largest nuclear sites: Sellafield, in northwestern England. I spend my days at the fume hood front, pipette in one hand and radiation probe in the other (and dosimeter pinned to my chest, of course). Outside the lab, I have a second job: I moonlight as a writer and public speaker. My new popular science book—Going Nuclear: How the Atom Will Save the World—came out last summer, and it feels like my life has been running at full power ever since.
R. D. Boyd, A. M. May, P. Cofie, R. Martin
Fusion Science and Technology | Volume 70 | Number 3 | November 2016 | Pages 448-460
Technical Paper | doi.org/10.13182/FST16-102
Articles are hosted by Taylor and Francis Online.
In order to accommodate high thermal loading of single-side-heated (SSH) components, robust thermal management and high-heat-flux-removal approaches are essential to prevent thermal instability, thermal runaway, or a thermal spiral toward component failure. This paper presents multidimensional steady-state heat transfer measurements for a high-strength-copper SSH monoblock (heat sink) coolant flow channel with a helical wire insert (HI) and thermally developing internal laminar and turbulent water (coolant) flow. In the present case, the term “monoblock” refers to a solid parallelepiped with a central coolant flow channel along the axial centerline. In addition to producing local two-dimensional (axial and circumferential) flow boiling curves, multidimensional monoblock wall temperature distribution comparisons were made between flow channels with and without a HI. Further, flow boiling curves were measured up to ~4.0 MW/m2 at the inside flow channel wall. For the same inside flow channel temperature, the HI enhanced (1) the incident heat flux by >70% when compared with the flow channel without the insert and (2) the inside flow channel wall heat flux by up to a factor of 5 near the monoblock heated side and at all axial locations. These results can be used for validation of computational fluid dynamics codes.