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Transfer measurement statistic derived from Purex processing measurements` quality control program, second half of 1965

Description: This report gives an analysis of the audit data obtained during the last half of 1965 at eight transfer stations: L9 plutonium product, K6 uranium product, F15 salt waste, D5 dissolved feed, F18 utility waste, G8 organic wash waste, R8 organic wash waste, and U3 laboratory waste. Two ways of improving the Purex quality control program are described.
Date: March 31, 1966
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department

Transfer measurement statistics derived from Purex Processing Measurements` Quality Control Program

Description: The Purex Processing Measurements Quality Control Program was designed to provide for orderly accumulation of measurements data suitable for statistical evaluation and to identify those elements of a measurement which, if improved, would result in significant reduction in overall measurement variation. This report gives an analysis of the audit data obtained at four transfer stations: L9 plutonium product loadout, K6 uranium product to storage, F15 salt waste to F16 and D5 dissolved feed to process. Estimates of variation caused by analytical, sampling and volume or weight instrumentation were computed and combined to give variation associated with a single batch transfer. Procedures for collection of future data that are more suitable for statistical evaluation are suggested. Methods used to compute random and fixed variation estimates are discussed.
Date: November 23, 1965
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department

Assessment of aircraft impact probabilities at the Idaho Chemical Processing Plant. Revision 1

Description: The purpose of this study is to evaluate the possibility of an aircraft crash into a facility at the Idaho Chemical Processing Plant (ICPP). The ICPP is part of the Idaho National Engineering Laboratory (INEL). Based on the data used in this study, an air crash into any single facility at the ICPP is incredible. An air crash into aggregate areas incorporating the following is extremely unlikely: (1) ICPP radiological materials storage facilities, (2) ICPP major processing facilities, and (3) the ICPP land surface area, which excludes buildings. According to Westinghouse Idaho Nuclear Company safety analysis procedures, if the probability of a radiological release event is determined to be incredible, no further review is required. Therefore, an aircraft crash scenario is not required in the safety analysis for a single facility but should be discussed relative to the ICPP aggregate areas.
Date: June 1, 1994
Creator: Lee, L. G.; Mines, J. M. & Webb, B. B.
Partner: UNT Libraries Government Documents Department

Thorium utilization program. Quarterly progress report for the period ending August 31, 1975

Description: This publication continues the quarterly series presenting results of work performed under the National HTGR Fuel Recycle Program (also known as the Thorium Utilization Program) at General Atomic Company. Results of work on this program prior to June 1974 were included in a quarterly series on the HTGR Base Program. The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel and the design and development of an integrated line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials. Work is also described on the evaluation of alternate techniques for fuel reprocessing to surmount possible operating problems with the reference flow sheet and the development of the conceptual design of a target recycle facility to identify the requirements of large-scale recycle of HTGR fuels. (auth)
Date: September 30, 1975
Partner: UNT Libraries Government Documents Department

Development of a geometrically favorable canyon dissolver

Description: A prototype has been constructed for initial full-scale evaluation using nonfissile materials. There are four charging ports, 6 inches in diameter, connected to a 3-inch annulus. The fuel element or scrap would be loaded into disposable containers, which would be charged to the dissolver ports. For high fissile material, only the bottom four feet of the container would be used, completely isolating the fissile material in a 6-inch well below the annulus. Recirculation and mixing are provided with a central air lift which is capable of recirculating 50 to 100 gallons per minute. Dissolver solution flows up the central air lift pipe, down a conical spillway to the annulus. Flow continues from the annulus to the charging ports through a series of holes in each charging port. The solution then contacts the charge and continues down the ports to the central air lift. Extensive flow studies have been done on one-eighth, one-quarter, and full-scale models.
Date: January 1, 1985
Creator: Graham, F R
Partner: UNT Libraries Government Documents Department

A critical review of alternate methods of Purex solvent treatment

Description: This document is a HAPO report dated September 20, 1957. At the time of this report, there had been many different methods suggested for improving the Purex organic recovery system. Some of these suggestions been tried in the plant and others had not. Information concerning this system and, particularly, methods for improving it were wide spread. At the time of this report was no immediate source of information available on the proposed and investigated methods for improving the Purex solvent recovery system.
Date: September 20, 1957
Creator: Gordon, N. R.
Partner: UNT Libraries Government Documents Department

Change of scope relocation of Purex cooling water swamp project CA-683

Description: It has been proposed that facilities be provided which can be used to divert the Purex cooling water from the facilities already proposed on this project to a depression within the 540 ft. elevation contour at approximate plant coordinates 34,300 N, 40200 W. These facilities are in addition to the change of scope referred to in reference (1). The purpose of these new facilities is to forma hydrologic dam as part of the ground water table which would aid in the confining of contamination and/or restricting the movement of contamination in the south easterly direction.
Date: October 26, 1956
Creator: Wood, V. W.
Partner: UNT Libraries Government Documents Department

Purex Plant flowsheet for high capacity study

Description: This report contains a flowsheet which was prepared to serve as a guide for an engineering study to be made to determine the costs and revisions required to increase the capacity of the Purex Plant to a 4.0 capacity factor. The needs for such a study are outlined in documents HW-62952 (Ref. 1) and HW-63927 (Ref. 2), which include increased 100 Area production forecasts and maximizing Palm recovery by continuous recovery equipment as primary factors. The flowsheet, shown graphically on the flowsketch and specifically in tabular form under Table 1, is a ``best estimate`` of process conditions and modifications which will be in operation by the third quarter of FY 1962. The modifications included are: Formaldehyde Treatment of Concentrated Wastes -- IWW (Ref. 5 and 6); A Continuous Palm Recovery Cycle; A Palm Ion Exchange Purification and Loadout Facility (Ref. 3); Alkaline-Permanganate Washing of the No. 2 Organic System Solvent; and Rough-cut Fission Product Recovery and Shipping (Ref. 4). Since the fission product recovery and shipping operations do not effect the equilibrium conditions of the plant, they are not included in the flowsheet.
Date: March 28, 1960
Creator: Geier, R. G. & Duckworth, J. P.
Partner: UNT Libraries Government Documents Department

The self-concentration of high level Purex wastes in the hot semiworks waste concentrator

Description: Prior to the startup of the Purex Plant it was considered desirable to study the ``self-concentration`` of wastes likely to be encountered in the Purex waste storage system. Consequently, a 39-inch diameter 35-foot high tank was built at the Hot Semiworks. This tank was designed to represent a core of the 75-foot diameter Purex waste tanks. During the period of Purex testing at the Hot Semiworks the tank was filled with ``typical`` Purex waste and self-concentration phenomena were studied. As pertinent data were developed from the studies it was informally transmitted to interested parties for use in establishing safe waste storage criterion for the Purex system. This document summarizes the Hot Semiworks waste self-concentrator basic data. No attempt has been made to cross-correlate this data with actual Purex experience although data are sufficiently detailed to permit calculation of such correlations.
Date: January 12, 1959
Creator: DeWitt, R. D. & Sloat, R. J.
Partner: UNT Libraries Government Documents Department

Addendum to HW-34882: Technical appraisal of Redox ruthenium problems and their resolution

Description: In the light of Redox Plant performance since the start-up on 2-3-55, coupled with a review of the technological factors involved in the current flowsheet, a departure from the process program outlined in HW-34882 is herewith presented as an addendum to that document which will also serve to detail the corresponding items in the latest Redox Test Program, HW-35069. The purposes of this document are to: (1) Discuss the need for modifications of the program given in HW-34882, and (2) Present the details of the proposed revisions.
Date: February 24, 1955
Creator: Harmon, M. K.
Partner: UNT Libraries Government Documents Department

E-metal dissolvers, Redox

Description: In December 1957, the proposal for Project CG-772, ``E-Metal Dissolvers -- Redox`` was returned for reconsideration in order that the units might be designed to accommodate higher enrichment fuels, if practical. Alternate design approaches have been under consideration since that time. It is the purpose of this document to summarize the parameters involved and to present the recommendation developed from the joint thinking of Hanford Laboratories, Research and Engineering, Facilities Engineering, and Redox Operation.
Date: February 19, 1958
Creator: Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department

Considerations for additional 321 Building mercury dissolving studies

Description: Studies in the 321 Building dissolver during December 1953 and January 1954, were successful in developing a laboratory-proved mercury-catalyzed dissolving flowsheet into a suitable plant procedure. However, this flowsheet was not adapted for Redox plant operation because of uncertainty about the possible presence of hydrogen above the lower explosive limit in the off-gases. Subsequent laboratory work has resulted in a better understanding of the hydrogen evolution, and has resulted in developing low hydrogen evolution flowsheets. When one of these flowsheets is selected for further work, it will be tested in the 321 Building dissolver with non-irradiated slugs to provide information for scaling-up the single-slug laboratory data to a plant-scale operation. It is the purpose of this memorandum to outline the factors considered to be pertinent to the 321 Building investigation, to be used as a guide in making preparations for the runs to be performed.
Date: August 11, 1954
Creator: Curtis, M. H.
Partner: UNT Libraries Government Documents Department

Definitive process design, Redox multi-purpose dissolver installation

Description: This document provides the required definitive scope design for dissolver equipment capable of nuclear safe processing by geometry of E-Metal and certain other fuels enriched to a maximum of one per cent U-235 equivalent. Using only a single dissolver installation of this design, it will be possible to process the current E-Metal monthly commitment in less than two weeks (five-day week). The proposed dissolver system is to incorporate design flexibility required to permit conversion to Zirflex processing of NPR fuels.
Date: May 6, 1959
Creator: Gustafson, L. D.
Partner: UNT Libraries Government Documents Department

Process Specifications for Operational Control: Purex Plant. Revision 1

Description: The Process Specifications for Operational Control of the Purex Plant(l) have been revised to define the operational control changes as a result of (a) converting the Purex Plant from three to two cycles, and (b) the use of the Plutonium Anion Exchange Unit (N-Cell) for routine plutonium concentration in place of the L-Cell Concentration Package. The flowsheets specified in Figures I-1, -2, and -3, and Table I fulfill the requirements for nuclear and chemical safety within the process as defined in Purex Process Specifications. The flowsheet also provides adequate recovery and decontamination to meet the product purity requirements itemized in Section 3.04. To clarify the two-cycle flowsheet and to simplify its use, the specifications are listed on graphic flow diagrams with the notation that process control allows a deviation of plus or minus five percent on all specifications except TBP concentration in solvent.
Date: November 17, 1958
Creator: Irish, E. R.
Partner: UNT Libraries Government Documents Department