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HPGe Compton-suppression and pair spectrometer

Description: A HPGe detector incorporated into a Compton suppression and pair spectrometer yields a continuum suppression factor of over 30. Cryostat housing requirements to obtain such suppression are discussed, sample spectra are presented, and several experiments making use of the HPGe dual system are discussed.
Date: May 19, 1976
Creator: Camp, D. C.
Partner: UNT Libraries Government Documents Department
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Portable microcomputer unit for the analysis of plutonium gamma-ray spectra

Description: A portable microcomputer has been developed for the IAEA to perform in-field analysis of plutonium gamma-ray spectra. The unit includes a 16-bit LSI-11/2 microprocessor, 32K words of memory, a 20-character display for user prompting, and a 20-character thermal printer for hardcopy output. Only the positions of the 148-keV Pu-241 and 208-keV U-237 peaks are required for spectral analysis. The unit was tested against gamma-ray spectra taken of NBS plutonium standards and IAEA spectra. Results obt… more
Date: October 1, 1981
Creator: Ruhter, W. D. & Camp, D. C.
Partner: UNT Libraries Government Documents Department
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Nondestructive, energy-dispersive, x-ray fluorescence analysis of actinide stream concentrations from reprocessed nuclear fuels

Description: In one plan for reprocessing LWR spent fuel, after separation from fission products and transplutonics, part of the U and all of the Pu in a nitrate solution will form a coprocessed stream which is then evaporated and sent to a hold tank for accounting. The remaining U fraction will be purified and sent to a separate storage tank. These two streams can be monitored using x-ray fluorescence analysis. This report discusses equipment, spectra, cell calibration, and dynamic concentration measuremen… more
Date: June 27, 1979
Creator: Camp, D. C. & Ruhter, W. D.
Partner: UNT Libraries Government Documents Department
open access

Nondestructive, energy-dispersive, x-ray fluorescence analysis of product stream concentrations from reprocessed nuclear fuels

Description: Energy-dispersive x-ray fluorescence analysis (XRFA) can be used to measure nondestructively pure and mixed U/Pu concentrations in process streams and hold tank solutions. The 122-keV gamma ray from /sup 57/Co excites the actinide K x rays which are detected by a HPGe detector. A computer- and disk-based analyzer system provides capability for making on-stream analyses, and the noninvasive measurement is easily adapted directly to appropriate sized pipes used in a chemical reprocessing plant. M… more
Date: November 26, 1979
Creator: Camp, D. C. & Ruhter, W. D.
Partner: UNT Libraries Government Documents Department
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Transmission-corrected x-ray fluorescence analysis of uranium and plutonium solutions using a dual transmission source

Description: The energy-dispersive x-ray fluorescence analysis (XRFA) technique has been implemented at several spent nuclear fuel reprocessing facilities for nondestructive measurements of uranium and/or plutonium concentrations in process streams and product storage tanks. An important factor in these quantitative measurements is the absorption of the fluoresced x-rays by the solution matrix, which must be taken into account to accurately quantify the U or Pu concentrations. We describe a new, accurate me… more
Date: November 24, 1987
Creator: Ruhter, W. D. & Camp, D. C.
Partner: UNT Libraries Government Documents Department
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Nondestructive assay of mixed uranium--plutonium oxides by gamma-ray spectrometry

Description: Gamma-ray spectroscopy measurements have been made on mixed uranium and plutonium oxides in sealed containers to determine the uranium and plutonium enrichment and isotopics. Experimental results obtained using two different methods were in good agreement with the known contents. The first method is applicable to thick samples of freshly reprocessed mixed oxide and determines isotopic abundances from measured absolute gamma-ray intensities. Measurement times depend on plutonium enrichment, but … more
Date: January 5, 1979
Creator: Ruhter, W. D. & Camp, D. C.
Partner: UNT Libraries Government Documents Department
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How to Create, Modify, and Interface Aspen In-House and User Databanks for System Configuration 2:

Description: The goal of this document is to provide detailed instructions to create, modify, interface, and test Aspen User and In-House databanks with minimal frustration. The level of instructions are aimed at a novice Aspen Plus simulation user who is neither a programming nor computer-system expert. The instructions are tailored to Version 10.1 of Aspen Plus and the specific computing configuration summarized in the Title of this document and detailed in Section 2. Many details of setting up databanks … more
Date: October 27, 2000
Creator: Camp, D W
Partner: UNT Libraries Government Documents Department
open access

How to Create, Modify, and Interface Aspen In-House and User Databanks for System Configuration 1:

Description: The goal of this document is to provide detailed instructions to create, modify, interface, and test Aspen User and In-House databanks with minimal frustration. The level of instructions are aimed at a novice Aspen Plus simulation user who is neither a programming nor computer-system expert. The instructions are tailored to Version 10.1 of Aspen Plus and the specific computing configuration summarized in the Title of this document and detailed in Section 2. Many details of setting up databanks … more
Date: October 27, 2000
Creator: Camp, D W
Partner: UNT Libraries Government Documents Department
open access

Nondestructive, energy-dispersive x-ray fluorescence analysis of product-stream concentrations from reprocessed LWR fuels

Description: Energy-dispersive x-ray fluorescence analysis can be used for quantitative on-line monitoring of the product concentrations in single- or dual-element process streams in a reprocessing plant. The 122-keV gamma ray from /sup 57/Co is used to excite the K x-rays of uranium and/or plutonium in nitric acid solution streams. A collimated HPGe detector is used to measure the excited x-ray intensities. Net solution radioactivity may be measured by eclipsing the exciting radiation, or by measuring it s… more
Date: January 5, 1979
Creator: Camp, D. C.; Ruhter, W. D. & Benjamin, S.
Partner: UNT Libraries Government Documents Department
open access

Analysis of plutonium gamma-ray spectra by small portable computers

Description: A sophisticated program for isotopic analysis of plutonium gamma-ray spectra using small computers has been developed. It is implemented on a DEC LSI-11/2 configured in a portable unit without a mass storage device for use by IAEA inspectors in the field. Only the positions of the 148-keV /sup 241/Pu and 208-keV /sup 237/U peaks are needed as input. Analysis is completed in 90 seconds by fitting isotopic component response functions to peak multiplets. 9 refs., 2 figs., 1 tab.
Date: May 15, 1985
Creator: Ruhter, W.; Gunnink, R.; Camp, D. & DeCarolis, M.
Partner: UNT Libraries Government Documents Department
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Mild coal gasification screw pyrolyzer development and design

Description: Our objective is to produce information and design recommendations needed for the development of an efficient continuous process for the mild gasification of caking bituminous coals. We have focused on the development of an externally heated pyrolyzer in which the sticky, reacting coal is conveyed by one or more screws. We have taken a multifaceted approach to forwarding the development of the externally-heated screw pyrolyzer. Small scale process experiments on a 38-mm single screw pyrolyzer h… more
Date: August 1, 1990
Creator: Camp, D.W.
Partner: UNT Libraries Government Documents Department
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An isotopic analysis system for plutonium samples enriched in sup 238 Pu

Description: We have designed and built a gamma-ray spectrometer system that measures the relative plutonium isotopic abundances of plutonium oxide enriched in {sup 238}Pu. The first system installed at Westinghouse Savannah River Company was tested and evaluated on plutonium oxide in stainless steel EP60/61 containers. {sup 238}Pu enrichments ranged from 20% to 85%. Results show that 200 grams of plutonium oxide in an EP60.61 container can be measured with {plus minus}0.3% precision and better than {plus m… more
Date: August 1, 1991
Creator: Ruhter, W. D. & Camp, D. C.
Partner: UNT Libraries Government Documents Department
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Nondestructive assay instrumentation for a Savannah River Plant upgrade project

Description: We have designed and are developing three different computer-based spectrometer systems. Two will measure the concentration of Pu solutions by gamma-ray and by stimulated x-ray fluorescence emissions of solid samples in closed containers. All systems are coupled to remote terminals and bar code readers, and also to mini-computer based multichannel analyzers, which in turn are linked to another computer to provide a state-of-the-art nondestructive assay capability. Installation at the Savannah R… more
Date: October 25, 1984
Creator: Camp, D.; Eckels, D.; Gunnink, R.; Prindle, A. & Ruhter, W.
Partner: UNT Libraries Government Documents Department
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Nondestructive and Quantitative Characterization of TRU and LLW Mixed-Waste Using Active and Passive Gamma-Ray Spectrometry and Computed Tomography

Description: The technology being proposed by LLNL is an Active and Passive Computed Tomography (A P CT) Drum Scanner for contact-handled (CH) wastes. It combines the advantages offered by two well-developed nondestructive assay technologies: gamma-ray spectrometry and computed tomography (CT). Coupled together, these two technologies offer to nondestructively and quantitatively characterize mixed- wastes forms. Gamma-ray spectroscopy uses one or more external radiation detectors to passively and nondestruc… more
Date: November 12, 1991
Creator: Camp, D. C. & Martz, H. E.
Partner: UNT Libraries Government Documents Department
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Nondestructive assay instrumentation for Savannah River Plant reprocessing accountability

Description: We have designed, developed, and calibrated three different types of nondestructive assay systems for the Savannah River Plant (SRP). These systems will be delivered to SRP in 1986 and become part of the nuclear material accounting instrumentation at one of SRP's reprocessing facilities. Among the various types of nondestructive assay systems to be implemented are a neutron counter (Los Alamos National Laboratory - LANL), a four-station calorimeter (Mound Laboratories), a waste solution assay s… more
Date: June 21, 1985
Creator: Ruhter, W. D.; Camp, D. C.; Gunnink, R. & Prindle, A. L.
Partner: UNT Libraries Government Documents Department
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Near-real-time actinide concentrations via energy dispersive XRFA for process control and material accountability

Description: A Co-57 based XRFA system has been installed on-line at ICPP to monitor uranium concentrations after first cycle decontamination. A small, medium, or large collimator is used to restrict fission product (fp) background count rates. Using two 50 mCi sources, 1 gU/1 can be measured to +-2% in 10 min with the medium collimator. A computer-based MCA runs the system automatically, controls an insertable U foil (allows calibration anytime) and an automatic W shutter (permits removal of fp background)… more
Date: November 18, 1983
Creator: Camp, D. C.; Ruhter, W. D.; Johnson, C. E. & Piper, T. C.
Partner: UNT Libraries Government Documents Department
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Mild coal gasification: Product separation, pilot-unit support, twin screw heat transfer, and H sub 2 S evolution

Description: Our general objective is to further the development of efficient continuous mild coal gasification processes. Our efforts this year have been in four main areas. A new thrust has been to identify and develop efficient processes to separate the vapor product stream into particulate-free liquid and mist-free gas. We continued work aimed at predicting heat transfer rates (hence throughput) in externally-heated twin-screw pyrolyzers. We sought to provide technical support for the design, installati… more
Date: August 9, 1991
Creator: Camp, D. W.; Wallman, P. H. & Coburn, T. T.
Partner: UNT Libraries Government Documents Department
open access

Preliminary minimum detectable limit measurements in 208-L drums for selected actinide isotopes in mock-waste matrices

Description: Preliminary minimum detectable levels (MDLS) of selected actinide isotopes have been determined in full-scale, 55-gallon drums filled with a range of mock-waste materials from combustibles (0.14 g/CM{sup 3}) to sand (1.7 g/CM{sup 3}). Measurements were recorded from 100 to 10,000 seconds with selected actinide sources located in these drums at an edge position, on the center axis of a drum and midway between these two positions. Measurements were also made with a {sup 166}Ho source to evaluate … more
Date: July 30, 1992
Creator: Camp, D. C.; Wang, Tzu-Fang & Martz, H. E.
Partner: UNT Libraries Government Documents Department
open access

Pu abundances, concentrations, and isotopics by x- and gamma-ray spectrometry assay techniques

Description: Two x- and gamma-ray systems were recently installed at-line in gloveboxes and will measure Pu solution concentrations from 5 to 105 g/L. These NDA technique, developed and refined over the past decade, are now used domestically and internationally for nuclear material process monitoring and accountability needs. In off- and at-line installations, they can measure solution concentrations to 0.2%. The K-XRFA systems use a transmission source to correct for solution density. The gamma-ray systems… more
Date: October 24, 1986
Creator: Camp, D. C.; Gunnink, R.; Ruhter, W. D.; Prindle, A. L. & Gomes, R. J.
Partner: UNT Libraries Government Documents Department
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