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in subjects: "Radiochemical analysis."  
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Manual of analytical methods for the Industrial Hygiene Chemistry Laboratory

Description: This Manual is compiled from techniques used in the Industrial Hygiene Chemistry Laboratory of Sandia National Laboratories in Albuquerque, New Mexico. The procedures are similar to those used in other laboratories devoted to industrial hygiene practices. Some of the methods are standard; some, modified to suit our needs; and still others, developed at Sandia. The authors have attempted to present all methods in a simple and concise manner but in sufficient detail to make them readily usable. I… more
Date: August 1, 1991
Creator: Greulich, K. A. & Gray, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Surface radiological investigation of Trench 5 in Waste Area Grouping 7 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: A surface radiological investigation of areas encompassing Trench 5 on the Oak Ridge Reservation (ORR) was conducted from May 1990 through November 1990. This survey was led by the author, assisted by various members of the Measurement Applications and Development (MAD) group of the Health and Safety Research Division (HASRD) of Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The purpose of the investigation was to determine the presence, nature, and extent of surface radiological… more
Date: August 1, 1991
Creator: Goff, D.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analytical Chemistry Laboratory Progress Report for FY 1991

Description: The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1991 (October 1990 through September 1991). This is the eighth annual report for the ACL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a r… more
Date: December 1, 1991
Creator: Green, D. W.; Heinrich, R. R.; Graczyk, D. G.; Lindahl, P. C. & Boparai, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data evaluation technical memorandum on the K-1407C Retention Basin at the Oak Ridge K-25 Site, Oak Ridge, Tennessee

Description: The K-1407-C Retention Basin was a surface impoundment at the Oak Ridge K-25 Site. The basin was used primarily for storing potassium hydroxide scrubber sludge generated at the K-25 Site. In addition, from 1960 to 1973, metal hydroxide sludges that were removed from the K-1407-B Holding Pond were discharged to the K-1407-C Retention Basin. The sludge in the K-1407-B Pond contained discharge from the K-1420 Decontamination and Uranium Recovery, the K-1501 Steam Plant, the K-1413 Laboratory, and … more
Date: October 1, 1991
Creator: Beal, D.; Bock, J.; Hatmaker, T.; Zolyniak, J.; Goddard, P. (Oak Ridge K-25 Site, TN (United States)) & Kucsmas, D. (Oak Ridge National Lab., TN (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Treatment requirements for decontamination of ORNL low-level liquid waste

Description: Experimental studies have been made to provide data for the development of improved processes for decontaminating low-level liquid wastes (LLLWs) that exist and continue to be generated at Oak Ridge National Laboratory. The concept underlying this work is that there is a net benefit if the major radionuclides ({sup 137}Cs, {sup 134}Cs, {sup 90}Sr, and actinides) can be separated into small volumes, thereby reducing the activity of the bulk of the waste so that it can be disposed of or managed a… more
Date: October 1, 1991
Creator: Lee, D.D. & Campbell, D.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The behavior of fission products during nuclear rocket reactor tests

Description: The experience base regarding fission product behavior developed during the Rover program, the nuclear rocket development program of 1955--1972, will be useful in planning a renewed nuclear rocket program. During the Rover program, 20 reactors were tested at the Nuclear Rocket Development Station in Nevada. Nineteen of these discharged effluent directly into the atmosphere; the last reactor tested, a non-flight-prototypic, fuel-element-testing reactor called the Nuclear Furnace (NF-1) was conne… more
Date: January 1, 1991
Creator: Bokor, P.C.; Kirk, W.L. & Bohl, R.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

[Studies of target fragmentation in intermediate energy, relativistic and ultra-relativistic nuclear collisions]. Nuclear chemistry progress report, August 1, 1990--August 1, 1991

Description: The work described herein is part of a project involving the study of low energy (< 10 MeV/A), intermediate energy (10--100 MeV/A) and relativistic (> 250 MeV/A) heavy ion reactions. In the low energy regime, we published a monograph on the properties of the heaviest elements and used that publication as a basis for making a set of ``best`` semi-empirical predictions of heavy element decay properties. The intermediate energy research effort focussed upon the completion of studies already begun … more
Date: August 1, 1991
Creator: Loveland, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The effect of isotope on the dosimetry of inhaled plutonium oxide

Description: Results of experimental studies in which animals inhaled {sup 238}PuO{sub 2} or {sup 239}PuO{sub 2} aerosols have shown that the biokinetics and associated radiation dose patterns for these two isotopes differ significantly due to differences in in-vivo solubility caused by the 260-fold difference in specific activity between {sup 238}PuO{sub 2} and {sup 239}PuO{sub 2}. We have adapted a biokinetics and dosimetry model derived from results of the ITRI dog studies to humans and have calculated d… more
Date: December 31, 1991
Creator: Guilmette, R. A., Griffith, W. C. & Hickman, A. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analytical Chemistry Laboratory Progress Report for FY 1991

Description: The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1991 (October 1990 through September 1991). This is the eighth annual report for the ACL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a r… more
Date: December 1, 1991
Creator: Green, D. W.; Heinrich, R. R.; Graczyk, D. G.; Lindahl, P. C. & Boparai, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A device for the determination of low concentrations of oxygen in carbonaceous materials

Description: Oxygen in carbonaceous materials is converted to carbon monoxide (CO) by pyrolyzing the material in a stream of oxygen-free helium. The CO is reacted with Ni{sup 63}, a radioactive isotope of nickel, to form nickel tetracarbanyl (Ni{sup 63}(CO){sub 4}) which is carried by the helium stream into a flow-through gas proportional counter. The quantity of Ni(CO){sub 4} is determined by the radioactivity of the gas as measured by the gas proportional counter. After exiting the flow through counter th… more
Date: December 31, 1991
Creator: Schultz, H.
Item Type: Refine your search to only Patent
Partner: UNT Libraries Government Documents Department
open access

Characterization of spent fuel approved testing material--ATM-104

Description: The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department … more
Date: December 1, 1991
Creator: Guenther, R. J.; Blahnik, D. E.; Jenquin, U. P.; Mendel, J. E.; Thomas, L. E. & Thornhill, C. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Characterization of spent fuel approved testing material---ATM-105

Description: The characterization data obtained to data are described for Approved Testing Material 105 (ATM-105), which is spent fuel from Bundles CZ346 and CZ348 of the Cooper Nuclear Power Plant, a boiling-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy O… more
Date: December 1, 1991
Creator: Guenther, R. J.; Blahnik, D. E.; Campbell, T. K.; Jenquin, U. P.; Mendel, J. E.; Thomas, L. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data evaluation technical memorandum on the K-1407C Retention Basin at the Oak Ridge K-25 Site, Oak Ridge, Tennessee. Environmental Restoration Program

Description: The K-1407-C Retention Basin was a surface impoundment at the Oak Ridge K-25 Site. The basin was used primarily for storing potassium hydroxide scrubber sludge generated at the K-25 Site. In addition, from 1960 to 1973, metal hydroxide sludges that were removed from the K-1407-B Holding Pond were discharged to the K-1407-C Retention Basin. The sludge in the K-1407-B Pond contained discharge from the K-1420 Decontamination and Uranium Recovery, the K-1501 Steam Plant, the K-1413 Laboratory, and … more
Date: October 1, 1991
Creator: Beal, D.; Bock, J.; Hatmaker, T.; Zolyniak, J.; Goddard, P. & Kucsmas, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Surface radiological investigation of Trench 5 in Waste Area Grouping 7 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

Description: A surface radiological investigation of areas encompassing Trench 5 on the Oak Ridge Reservation (ORR) was conducted from May 1990 through November 1990. This survey was led by the author, assisted by various members of the Measurement Applications and Development (MAD) group of the Health and Safety Research Division (HASRD) of Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The purpose of the investigation was to determine the presence, nature, and extent of surface radiological… more
Date: August 1, 1991
Creator: Goff, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

(Studies of target fragmentation in intermediate energy, relativistic and ultra-relativistic nuclear collisions)

Description: The work described herein is part of a project involving the study of low energy (< 10 MeV/A), intermediate energy (10--100 MeV/A) and relativistic (> 250 MeV/A) heavy ion reactions. In the low energy regime, we published a monograph on the properties of the heaviest elements and used that publication as a basis for making a set of best'' semi-empirical predictions of heavy element decay properties. The intermediate energy research effort focussed upon the completion of studies already begun an… more
Date: August 1, 1991
Creator: Loveland, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary waste form characteristics report Version 1.0. Revision 1

Description: This report focuses on radioactive waste form characteristics that will be used to design a waste package and an engineered barrier system (EBS) for a suitable repository as part of the Yucca Mountain Project. The term waste form refers to irradiated reactor fuel, other high-level waste (HLW) in various physical forms, and other radioactive materials (other than HLW) which are received for emplacement in a geologic repository. Any encapsulating of stabilizing matrix is also referred to as a was… more
Date: October 11, 1991
Creator: Stout, R. B. & Leider, H. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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