Thesis (Ph. D.)--Ohio state University, 1921. / Autobiography. Reprint of an article by C.W. Foulk and Samuel Morris in the Journal of the American chemical society, v.44, no. 2, February 1922.

Thesis (Ph. D.)--University of Wisconsin--Madison, 1980. / Typescript. Vita. eContent provider-neutral record in process. Description based on print version record. Includes bibliographical references (leaves 187-193).

[No abstract submitted] / Science, Faculty of / Physics and Astronomy, Department of / Graduate

Thesis (Ph. D.)--McMaster University (Canada), 1990. / Source: Dissertation Abstracts International, Volume: 62-13, Section: A, page: 0000.

Thesis (M. App. Sc.)--University of Sydney, 2001. / Title from title screen (viewed Aug. 11, 2009) Includes tables. Submitted in fulfilment of the requirements for the degree of Master of Applied Science to the Faculty of Health Sciences. Includes bibliographical references. Also available in print form.

[No abstract available] / Science, Faculty of / Chemistry, Department of / Graduate

Based upon the results reported by Balykin, V. S.r Letokhov, V. S., Mishen, V. I., and Semchishen, V. A., Chem. Phys., 17, 111 (1976), an attempt was made to shift the ortho-iodine to para-iodine ratio by (1) selectively predissociating the ortho-iodine molecules with the 5145 A argon ion laser line and (2) by reacting the selectively excited ortho molecules with the scavengers, 2-hexene, acetylene, nitric oxide, nitrosyl chloride, and ethyl iodide. In both cases the ortho to para ratio was monitored via the fluorescence induced by a scanning dye laser beam. Neither tactic prooved effective, in contradiction with the aforementionned authors. In the case of systems containing low pressures ' of iodine' vapour alone, time dependent differential quenching of the vibrational [mathematical formula omitted] transitions was observed attributed to outgasing of the test cells over the course of the experiment and may be the cause of the apparant shift claimed by Letokhov et al. In mixtures of iodine and scavenger, the null result was probably due to the formation of radical chains during the photo-induced reactions capable of rapidly relaxing any shift that had occurred. / Science, Faculty of / Physics and Astronomy, Department of / Graduate

This research suggests ways of reducing contamination of iodine-126 in iodine-125 and lays out a simpler iodine-125 production technique to increase the yield. By using aluminum irradiation vessels the yield of iodine-125 produced by neutron irradiation of Xe-124 can be doubled compared to using stainless steel vessels. Because of increased yields irradiation times are shorter, the chance of I-126 contamination is reduced. Solidified iodine within the aluminum vessels can be extracted using 0.1 N sodium hydroxide solution, however the solution also reacts with the vessel walls. These impurities in the extracted solution are then removed by distillation that concentrates and purifies the extracted solution. High recovery, ranging from 88 to 96 percent, was typical for the experiments described. Gamma spectroscopic results suggest that the distillate is free from any impurities such as aluminum or sodium ions. Distillation can reduce the extracted solution to at least one third or less of its original volume. The work described here provides the basis for I-125 production at the Texas A&M Nuclear Science Center.

This research suggests ways of reducing contamination of iodine-126 in iodine-125 and lays out a simpler iodine-125 production technique to increase the yield. By using aluminum irradiation vessels the yield of iodine-125 produced by neutron irradiation of Xe-124 can be doubled compared to using stainless steel vessels. Because of increased yields irradiation times are shorter, the chance of I-126 contamination is reduced. Solidified iodine within the aluminum vessels can be extracted using 0.1 N sodium hydroxide solution, however the solution also reacts with the vessel walls. These impurities in the extracted solution are then removed by distillation that concentrates and purifies the extracted solution. High recovery, ranging from 88 to 96 percent, was typical for the experiments described. Gamma spectroscopic results suggest that the distillate is free from any impurities such as aluminum or sodium ions. Distillation can reduce the extracted solution to at least one third or less of its original volume. The work described here provides the basis for I-125 production at the Texas A&M Nuclear Science Center.

No description available.