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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.
S. J. Raffety, J. T. Mihalczo
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 433-443
Technical Paper | doi.org/10.13182/NSE72-A22511
Articles are hosted by Taylor and Francis Online.
A series of clean critical experiments has been performed with homogeneous mixtures of finely divided U(2)F4 or U(3)F4 dispersed in dispersed in paraffin with H/235U atomic ratios varying from 133 to 972. The assemblies were constructed in rectangular geometry, and minimum critical masses and volumes in cylindrical and spherical geometries were obtained from buckling conversions. The minimum critical spherical volumes of a U(2)F4-paraffin mixture when unreflected and when reflected with an effectively infinite solid hydrogenous material are 199 and 138 liters, respectively, and the minimum critical 235U masses are 7.5 and 5.4 kg, respectively. The experiments with the U(3)F4-paraffin mixtures were not extensive enough to determine experimentally the values at optimum moderation but transport theory calculations indicate that the unreflected and reflected minimum critical volumes are about 93 and 57 liters, respectively, and that the minimum critical masses are about 4.1 and 2.7 kg of 235U, respectively. Measurements of the 238U-to-235U fission ratio indicated that in some assemblies as much as 6.5% of the fissions occurred in 238U. Prompt-neutron decay constants, α = βeff/1 were measured in reflected and unreflected delayed-critical assemblies of several fuel mixtures by the pulsed-neutron technique; the infinite-medium neutron multiplication factor, k∞, for the various fuel mixtures was inferred from height perturbation measurements.Transport theory calculations of k∞ and feff have been made using various cross-section sets.