LWR Off-Gas Treatment: A reference facility has been described in a draft report. A survey of technical literature for immobilization of /sup 14/CO/sub 2/ was completed. Waste Management: Laboratory evaporations were continued using simulated HLLW solutions representing three fuel cycle processes. Total solids content at various degrees of evaporation are presented together with boiling point rises and slurry densities. Substitution of less costly materials for Rh, Pd, and Tc did not affect the physical properties of the slurries or the quantity of solids formed. The effect of adding nuclear poisons (gadolinium, boron, or cadmium) on physical properties of HLLW and on solids formation is reported. Solids formed in all HLLW solutions contained major amounts of Zr and Mo. The design of the small-scale thermosyphon evaporator and the reboiler tube test specimen are presented. Evaporated HLLW slurries stored for two months at 35/sup 0/C have not produced significantly more solids. Laboratory corrosion data showed excessive corrosion occurred in HLLW containing high iron concentrations and 7 M HNO/sub 3/, apparently due to Cr formed by stainless steel corrosion. Iodine-129 Adsorbent and Storage Development: Silver-exchanged zeolite (AgX) and mordenite (AgZ) were loaded with and stripped of elemental iodine for evaluation for recycle behavior.more » After five cycles, the AgZ showed no decrease in loading (approximately 440 mg/g); the AgX loading dropped about 50 percent from its initial value of 320 mg/g. (DLC)« less

The presence of water or nitrogen dioxide in an untreated off-gas stream will detrimentally affect the performance of a silver-exchanged zeolite adsorbent. The waste management program is being performed (1) to determine the behavior of LWR liquid wastes during evaporation and storage with regard to solids production, fouling tendencies, and off-gas behavior, and (2) to evaluate materials of construction for process evaporators and waste tanks. Simulated high-level liquid waste (HLLW) solutions were prepared by combining stock solutions to closely approximate the components in actual process waste solutions. Vapor-liquid equilibrium compositions of nitric acid were measured to determine the effect of components in HLLW on the volatilization of HNO/sub 3/. Laboratory evaporations were conducted to determine the physical and chemical properties of HLLW solutions during evaporation. Data are reported for boiling point rise, density, and undissolved solids at varying degrees of concentration. A pilot unit thermosyphon evaporator was designed on the basis of conditions proposed for the HLLW waste evaporator at Barnwell Nuclear Fuel Plant (BNFP) for LWR fuels. The long-term physical characteristics of solids formed in the HLLW solutions are being investigated during storage without agitation at 35/sup 0/. Laboratory corrosion tests are being initiated to determine the effects ofmore » waste compositions of materials of construction in evaporators and storage tanks. Materials which have been selected for testing in the reboiler section of the pilot plant evaporator are types 304L, 309S, and 310S stainless steels, titanium, Nitronic-50, Carpenter 329, Sandvik 2 RE 10, and Sandvik 2 RE 69 ELC.« less

satisfactory for all solutions could not be selected. The optimum treatment for a salvage solution which was grossly contaminated with zirconium, soluble and colloidal silica, and dibutyl phosphate was to boil a 1N acid deficient solution with 600 milligrams of gelatin per liter, filter, and use a Hexone extraction system. A silicic colloid in fuel processing solutions was characterized as a surface active material by this study. (auth)

More economical methods of manufacturing aluminum-uranium fuel elements used extensively in high thermal-neutron flux reactors might be employed if the quantity of silicon allowed in the fuels could be substantially increased. Since silicon has created problems in reprocessing this type of fuel, various core and cladding alloys were examined for the effect of the silicon content upon dissolution, extraction, and solids production during dissolution. Dissolution rates in nitric acid were related to the metallurgical compositions of the alloys which, in turn, were related to their silicon content, but the effect was not sufficient to interfere with the reprocessing of the fuels. Emulsion stabilization, a problem during liquid-liquid extraction of uranium, is caused by the silicon that dissolves from the alloy as the intermetallic phase U(Al,Si)3. Silicon present in the alloy at a silicon:uranium atom ratio <1 is in the intermetallic fuel particle, while silicon in excess of approximately one atom per atom of uranium does not enter into the intermetallic phase and is present in the alloys as segregations of elemental silicon. This elemental silicon does not dissolve and remains in the dissolver solution as undesirable solids.

The penetration of iodine (released as I ) into protective coatings, which are used for the interior of reactor buildings, is described by a simple model derived from Fick's basic diffusion concepts.Diffusion coefficients for four commercial coatings are given for the temperature range 20-1^+0 C.

ADVERTISEMENT RETURN TO ISSUEPREVArticleNEXTBarium Fluozirconate Precipitation. Improved Process for Uranium-Zirconium Alloy FuelsB. E. Paige, B. J. Newby, and K. L. RohdeCite this: Ind. Eng. Chem. Process Des. Dev. 1963, 2, 2, 112–116Publication Date (Print):April 1, 1963Publication History Published online1 May 2002Published inissue 1 April 1963https://pubs.acs.org/doi/10.1021/i260006a005https://doi.org/10.1021/i260006a005research-articleACS PublicationsRequest reuse permissionsArticle Views46Altmetric-Citations-LEARN ABOUT THESE METRICSArticle Views are the COUNTER-compliant sum of full text article downloads since November 2008 (both PDF and HTML) across all institutions and individuals. These metrics are regularly updated to reflect usage leading up to the last few days.Citations are the number of other articles citing this article, calculated by Crossref and updated daily. Find more information about Crossref citation counts.The Altmetric Attention Score is a quantitative measure of the attention that a research article has received online. Clicking on the donut icon will load a page at altmetric.com with additional details about the score and the social media presence for the given article. Find more information on the Altmetric Attention Score and how the score is calculated. Share Add toView InAdd Full Text with ReferenceAdd Description ExportRISCitationCitation and abstractCitation and referencesMore Options Share onFacebookTwitterWechatLinked InRedditEmail Other access options Get e-Alerts

Electrolytic dissolution in a nitric acid electrolyte is promising as a universal headend in the recovery of uranium from a wide variety of nuclear fuels. A number of fuel materials of different shapes are dissolved continuously without difficulty. Preliminary studies indicate the applicability of electrolytic dissolution in the decladding of UO2 and the cutting of stainless steel fuel cans.

A remotely operated device was developed for determining the coalescence times of solvent extraction plant process streams suspected of containing surfactants. Using the device, the coalescence times of pilot plant extraction column feed streams were correlated with observations of column behavior. Measurements made on plant streams derived from fully-irradiated fuels were used in the Idaho Chemical Processing Plant to predict the behavior of such streams and to prevent attempted processing with incompatible chemical systems.