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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.
C. P. C. Wong, V. S. Chan, A. M. Garofalo, R. Stambaugh, M. E. Sawan, R. Kurtz, B. Merrill
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 283-288
Fusion Technology Facilities | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14148
Articles are hosted by Taylor and Francis Online.
A fusion nuclear science facility (FNSF) is a necessary complement to ITER, especially in the area of material and component testing needed for DEMO design development. FNSF-AT, which takes advantage of advanced tokamak (AT) physics, should have neutron wall loading of 1-2 MW/m2 , continuous operation for periods of up to 2 weeks, a duty factor goal of 0.3 per year, and an accumulated fluence of 3-6 MW-yr/m2 ([approximately]30-60 dpa) in 10 years to enable the qualification of structural, blanket, and functional materials, components, and corresponding ancillary equipment necessary for the design and licensing of a DEMO. Base blankets with a ferritic steel structure and selected tritium blanket materials will be tested and used for the demonstration of tritium sufficiency. Additional test ports at the outboard midplane will be reserved for test blankets with advanced designs or exotic materials and electricity production for integrated high-fluence testing in a DT fusion spectrum. FNSF-AT will be designed using conservative implementations of all elements of AT physics to produce 150-300 MW of fusion power with modest energy gain (Q < 7) in a modest-sized normal conducting coil device. It will demonstrate and help to select the DEMO plasma-facing, structural, tritium-breeding, and functional materials and ancillary equipment including diagnostics. It will also demonstrate the necessary tritium fuel cycle, design and cooling of the first wall chamber, and divertor components. It will contribute to the knowledge on material qualification, licensing, operational safety, and remote maintenance necessary for DEMO design.