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ICPP custom dissolver explosion recovery

Description: This report discusses the recovery from the February 9, 1991 small scale explosion in a custom processing dissolver at the Idaho Chemical Processing Plant. Custom processing is a small scale dissolution facility which processes nuclear material in an economical fashion. The material dissolved in this facility was uranium metal, uranium oxides, and uranium/fissium alloy in nitric acid. The paper explained the release of fission material, and the decontamination and recovery of the fuel material.… more
Date: June 11, 1992
Creator: Demmer, R. & Hawk, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Technical Division quarterly progress report, October 1--December 31, 1976

Description: The first in a series of quarterly progress reports on ERDA budgeted activities subcontracted to Allied Chemical Corporation at the Idaho National Engineering Laboratory is presented. The work is performed by the Technical Division and is divided into three subjects. Fuel cycle research and development includes fluidized-bed calcination and post treatment of commercial nuclear fuel process waste; the storage of fission product noble gas; the catalyzed reaction between NO/sub x/ and NH/sub 3/; t… more
Date: March 1, 1977
Creator: Slansky, C. M. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Idaho Chemical programs annual technical report, fiscal year 1975

Description: The operating experience in fuel processing, waste calcining, and other waste management activities at the ICPP for FY 1975 is summarized. A campaign of coprocessing zirconium and aluminum fuels to recover uranium, the second electrolytic processing campaign to convert recovered and purified uranyl nitrate solution to UO/sub 3/, and four operating periods of the Rare Gas Plant to recover /sup 85/Kr and xenon were successfully completed, with all systems functioning well except for minor difficu… more
Date: June 1, 1976
Creator: Buckham, J. A.; Bower, .R. & Struhs, R. T. (eds.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Division quarterly progress report, January 1--March 31, 1977

Description: Progress is reported in three categories: Fuel Cycle Research and Development, special materials production, and projects supporting energy development. Results are presented on the fluidized-bed calcination of high-level radioactive waste from the reprocessing of spent commercial nuclear fuel, on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other projects include the development of storage technology for /sup 85/Kr waste; a stu… more
Date: May 1, 1977
Creator: Slansky, C. M. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria for the new waste calcining facility at the Idaho Chemical Processing Plant

Description: The New Waste Calcining Facility (NWCF) at the Idaho Chemical Processing Plant (ICPP) is being built to replace the existing fluidized-bed, high-level waste calcining facility (WCF). Performance of the WCF is reviewed, equipment failures in WCF operation are examined, and pilot-plant studies on calciner improvements are given in relation to NWCF design. Design features of the NWCF are given with emphasis on process and equipment improvements. A major feature of the NWCF is the use of remote mai… more
Date: January 1, 1976
Creator: Anderson, F. H.; Bingham, G. E.; Buckham, J. A.; Dickey, B. R.; Slansky, C. M. & Wheeler, B. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Technical Division quarterly progress report, April 1--June 30, 1977

Description: Fuel Cycle Research and Development: Results are presented on the fluidized-bed calcination of high-level radioactive waste from reprocessing on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other projects include the development of storage technology for /sup 85/Kr waste; a study of the hydrogen mordenite catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I on silver exchanged mordenite; p… more
Date: July 1, 1977
Creator: Slansky, C. M.; Dickey, B. R.; Musgrave, B. C. & Rohde, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INEL integrated spent nuclear fuel consolidation task team report

Description: This document describes a draft plan and schedule to consolidate spent nuclear fuel (SNF) and special nuclear material (SNW) from aging storage facilities throughout the Idaho National Engineering Laboratory (INEL) to the Idaho Chemical Processing Plant (ICPP) in a safe, cost-effective, and expedient manner. A fully integrated and resource-loaded schedule was developed to achieve consolidation as soon as possible. All of the INEL SNF and SNM management task, projects, and related activities fro… more
Date: September 12, 1994
Creator: Henry, R. N.; Clark, J. H. & Chipman, N. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calcination of Fluorinel-sodium waste blends using sugar as a feed additive (formerly WINCO-11879)

Description: Methods were studied for using sugar as a feed additive for converting the sodium-bearing wastes stored at the Idaho Chemical Processing Plant into granular, free flowing solids by fluidized-bed calcination at 500{degrees}C. All methods studied blended sodium-bearing wastes with Fluorinel wastes but differed in the types of sugar (sucrose or dextrose) that were added to the blend. The most promising sugar additive was determined to be sucrose, since it is converted more completely to inorganic … more
Date: June 1, 1992
Creator: Newby, B. J.; Thomson, T. D. & O`Brien, B. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of aluminum and silicon reactants and process parameters on glass-ceramic waste form characteristics for immobilization of high-level fluorinel-sodium calcined waste

Description: In this report, the effects of aluminum and silicon reactants, process soak time and the initial calcine particle size on glass-ceramic waste form characteristics for immobilization of the high-level fluorinel-sodium calcined waste stored at the Idaho Chemical Processing Plant (ICPP) are investigated. The waste form characteristics include density, total and normalized elemental leach rates, and microstructure. Glass-ceramic waste forms were prepared by hot isostatically pressing (HIPing) a pre… more
Date: June 1, 1993
Creator: Vinjamuri, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The use of selective extraction chromatographic columns as an alternative to solvent extraction for the separation of uranium followed by the use of Arsenazo III as a calorimetric reagent for uranium determination

Description: The use of U/TEVA{reg_sign} Spec columns as an alternative to solvent extraction for separation of uranium prior to its determination by various techniques (calorimetric, phosphorescence, and mass spectroscopy) was investigated. U/TEVA{reg_sign} Spec columns have several advantages over the widely used 4-methyl-2-pentanone solvent extraction method. Among the advantages are: (1) no hazardous liquid organic waste, that creates regulatory waste disposal problems, is generated; (2) a clean separat… more
Date: October 1, 1994
Creator: Miller, C. J. & Del Mastro, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Idaho Chemical Processing Plant spent fuel and waste management technology development program plan: 1994 Update

Description: The Department of Energy has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until April 1992, the major activity of the ICPP was the reprocessing of SNF to recover fissile uranium and the management of the resulting high-level wastes (HLW). In 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the continued safe management and disposition of SNF and radioac… more
Date: September 1, 1994
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of aluminum and silicon reactants and HIP soak time on characteristics of glass-ceramic waste forms

Description: The high level liquid waste (HLLW) from nuclear fuel reprocessing is being calcined into solid granules and being stored onsite at the Idaho Chemical Processing Plant (ICPP) since 1963. Final disposal of the calcined waste in a geologic repository requires further consolidation of the calcine in to a solid waste form. One of the solid waste forms being considered for immobilization of the ICPP calcines is the glass-ceramic. The glass-ceramic waste form is a promising option because it can poten… more
Date: April 1, 1993
Creator: Vinjamuri, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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ICPP Fluorinel Dissolution Process (FDP) Plant Protection System (PPS) baseline criteria evaluation

Description: This report documents a baseline criteria evaluation of the FAST Plant Protection System (PPS) at the Idaho Chemical Processing Plant (ICPP). Westinghouse Idaho Nuclear Company (WINCO), Computer Process Application (CPA) personnel originally prepared this report as requested by the FAST Fluorinel Dissolution Process (FDP) Operational Readiness Review (ORR) committee. It was required by the ORR committee for the 1992 restart of FDP operations. However on April 29, 1992, the Department of Energy … more
Date: June 1993
Creator: Allen, Geoffrey W.; Clayton, Ronald J.; Fielding, Kurt D. & Mozes, Mary L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Testing and evaluation of eight decontamination chemicals

Description: This report covers experimental work comparing eight different decontamination chemicals. Seven of these chemicals have some novelty, or are not currently in use at the ICPP. The eighth is a common ICPP decontamination reagent used as a baseline for effective comparison. Decontamination factors, waste generation values, and corrosion rates are tabulated for these chemicals. Recommendations are given for effective methods of non-sodium or low-sodium decontamination chemicals. The two most effect… more
Date: September 1, 1994
Creator: Demmer, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ICPP radioactive liquid and calcine waste technologies evaluation. Interim report

Description: The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus towar… more
Date: June 1, 1994
Creator: Murphy, J. A.; Pincock, L. F. & Christiansen, I. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pyrochemical treatment of Idaho Chemical Processing Plant high-level waste calcine

Description: The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1951 to recover uranium, krypton-85, and isolated fission products for interim treatment and immobilization. The acidic radioactive high-level liquid waste (HLLW) is routinely stored in stainless steel tanks and then, since 1963, calcined to form a dry granular solid. The resulting high-level waste (HLW) cal… more
Date: June 1, 1993
Creator: Todd, T. A.; DelDebbio, J. A.; Nelson, L. O. & Sharpsten, M. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Idaho Chemical Processing Plant safety document ICPP hazardous chemical evaluation

Description: This report presents the results of a hazardous chemical evaluation performed for the Idaho Chemical Processing Plant (ICPP). ICPP tracks chemicals on a computerized database, Haz Track, that contains roughly 2000 individual chemicals. The database contains information about each chemical, such as its form (solid, liquid, or gas); quantity, either in weight or volume; and its location. The Haz Track database was used as the primary starting point for the chemical evaluation presented in this re… more
Date: January 1, 1993
Creator: Harwood, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ICPP waste management technology development program

Description: A program has been implemented at the Idaho Chemical Processing Plant (ICPP) to identify technologies for disposing of sodium-bearing liquid radioactive waste, radioactive calcine, and irradiated spent fuel stored at the Idaho National Engineering Laboratory (INEL). The sodium bearing waste and calcine, have resulted from ICPP reprocessing operations conducted since 1953. The irradiated spent fuel consists of various fuel compositions and ranges from complete fuel elements to fuel pieces for wh… more
Date: June 1, 1993
Creator: Hogg, G. W.; Olson, A. L.; Knecht, D. A. & Bonkoski, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Hydrogeology, waste disposal, science and politics: Proceedings

Description: A total of 48 papers were presented at the Engineering Geology and Geotechnical Engineering 30th Symposium. These papers are presented in this proceedings under the following headings: site characterization--Pocatello area; site characterization--Boise Area; site assessment; Idaho National Engineering Laboratory; geophysical methods; remediation; geotechnical engineering; and hydrogeology, northern and western Idaho. Individual papers have been processed separately for inclusion in the Energy S… more
Date: July 1, 1994
Creator: Link, P. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Friction welding method of hot isostatic press can closure for the ICPP calcine immobilization program

Description: An investigation of various closure techniques was performed in an effort to meet requirements for closure of evacuated waste cans to be used at Westinghouse Idaho Nuclear Company`s Idaho Chemical Processing Plant. Although other sealing techniques are available, welding was considered to be the best for sealing the cans. For various reasons. techniques other than welding are not suitable for cans that are subject to the Hot Isostatic Press (HIP) process. For example. elastomeric seals. solders… more
Date: September 1, 1993
Creator: Berry, S. M.; Reed, T. R. & Swainston, R. C
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Level Waste Tank Farm Replacement Project for the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory. Environmental Assessment

Description: The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0831, for the construction and operation of the High-Level Waste Tank Farm Replacement (HLWTFR) Project for the Idaho Chemical Processing Plant located at the Idaho National Engineering Laboratory (INEL). The HLWTFR Project as originally proposed by the DOE and as analyzed in this EA included: (1) replacement of five high-level liquid waste storage tanks with four new tanks and (2) the upgrading of existing tan… more
Date: June 1, 1993
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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