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Selection of a form for fixation of iodine-129

Description: This report summarizes work on the selection of an /sup 129/I disposal form. Iodine compounds have been screened on the basis of solubilities, thermal stabilities, cost and availability, toxicity of the cation, and the thermodynamic resistance to oxidation and hydrolysis, and leaching of that compound in portland type III cement. Also considered were iodine capture technology, disposal criteria or guidelines, and the disposal site/strategy. The recommended iodine fixation forms, based on their … more
Date: December 1, 1981
Creator: Burger, L. L.; Scheele, R. D. & Wiemers, K. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Technical requirements for the control of 129I in a nuclear fuels reprocessing plant

Description: A proposed regulation would limit the release of /sup 129/I to the environment to 0.005 Ci/GWe-yr of nuclear power produced. This corresponds to an overall /sup 129/I retention factor of about 250 for the LWR fuel cycle. Technolgies available and under development for removing iodine from off-gas and waste water streams in an LWR nuclear fuel reprocessing plant and for converting iodine to stable forms and retaining it for interim and long-term storage, transportation and isolation are discusse… more
Date: November 1, 1979
Creator: Burger, L.L. & Burns, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compatibility of technologies with regulations in the waste management of H-3, I-129, C-14, and Kr-85. Part I. Initial information base

Description: This report summarizes the information base that was collected and reviewed in preparation for carrying out an analysis of the compatibility with regulations of waste management technologies for disposal of H-3, I-129, C-14, and Kr-85. Based on the review of this literature, summaries are presented here of waste-form characteristics, packaging, transportation, and disposal methods. Also discussed are regulations that might apply to all operations involved in disposal of the four nuclides, inclu… more
Date: August 1, 1983
Creator: Trevorrow, L.E.; Vandegrift, G.F.; Kolba, V.M. & Steindler, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Iodox process tests in a transuranium element production campaign

Description: The Iodox process, an advanced method for removing gaseous radioiodine from airstreams, was tested at high activity levels during transuranium element production operations. Special equipment was used to remove radioiodine from 3-5M HNO/sub 3/ dissolver solutions by volatilization and to absorb the iodine from the dissolver off-gas into hyperazeotropic HNO/sub 3/. More than 96% of the /sup 131/I in the dissolver solutions was removed by heeating to 100/sup 0/C and air-sparging. Treatments such … more
Date: June 1, 1979
Creator: Collins, E. D. & Benker, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Use of extractive distillation to produce concentrated nitric acid

Description: Concentrated nitric acid (> 95 wt %) is needed for the treatment of off-gases from a fuels-reprocessing plant. The production of concentrated nitric acid by means of extractive distillation in the two-pot apparatus was studied to determine the steady-state behavior of the system. Four parameters, EDP volume (V/sub EDP/) and temperature (T/sub EDP/), acid feed rate, and solvent recycle, were independently varied. The major response factors were percent recovery (CPRR) and product purity (CCP). S… more
Date: April 1, 1981
Creator: Campbell, P.C.; Griffin, T.P. & Irwin, C.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transuranium processing plant semiannual report of production, status, and plans for period ending December 31, 1977

Description: Transuranium elements were obtained from 13 irradiated HFIR targets. One batch of high-purity /sup 248/Cm (approximately 75 mg) was separated from /sup 252/Cf. Eighteen shipments were made from TRU during the period. Seven HFIR targets, each containing 8 to 9 g of curium, were fabricated. A new scrubber system was installed in the dissolver off-gas (DOG) stream to remove the bulk of the /sup 131/I and to reduce the amount sorbed in the Hopcalite--charcoal system. During TRU target Campaign 53, … more
Date: August 1, 1978
Creator: King, L. J.; Bigelow, J. E. & Collins, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Iodine and NO sub x behavior in the dissolver off-gas and IODOX (Iodine Oxidation) systems in the Oak Ridge National Laboratory Integrated Equipment Test facility

Description: This paper describes the most recent in a series of experiments evaluating the behavior of iodine and NO{sub x} in the Integrated Equipment Test (IET) Dissolver Off-Gas (DOG) System. This work was performed as part of a joint collaborative program between the US Department of Energy and the Power and Nuclear Fuel Development Corporation of Japan. The DOG system consists of two shell-and-tube heat exchangers in which water and nitric acid are removed from the dissolver off-gas by condensation, f… more
Date: January 1, 1990
Creator: Birdwell, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Literature survey: methods for the removal of iodine species from off-gases and liquid waste streams of nuclear power and nuclear fuel reprocessing plants, with emphasis on solid sorbents

Description: Emphasis was focused on the operating parameters that most strongly affected the optimization of the processes used to treat actual process or feed streams which simulated actual compositions occurring at nuclear facilities. These parameters included gas superficial velocity, temperature, types of organic and inorganic contaminants, relative humidity, iodine feed-gas concentration, iodine species, column design (for both acid-scrub and solid sorbent-based processes), sorbent particle size, run … more
Date: January 1, 1979
Creator: Holladay, D.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical aspects of nuclear waste treatment

Description: The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desira… more
Date: January 1, 1980
Creator: Bond, W. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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