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in subjects: "Strontium 90"

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Radiochemical analyses of samples from beneath a solid radioactive waste disposal pit at Los Alamos, New Mexico

Solid radioactive wastes are disposed of by burial in pits excavated in rhyolite tuff at the Los Alamos Scientific Laboratory (LASL). Contaminants in the waste include fission products, uranium, and transuranic elements. In 1976, horizontal core holes were drilled beneath a waste disposal pit that was used from 1963 to 1966. Samples of the core were analyzed for gross alpha, gross beta, total uranium, /sup 90/Sr, /sup 137/Cs, /sup 238/Pu, /sup 239/ /sup 240/Pu, and /sup 241/Am. The measured gro… more

Date: June 1, 1980

Creator: Purtymun, W. D.; Rogers, M. A. & Wheeler, M. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tumors of the skin and soft tissues

The majority of the body surface is covered by the skin. Many internal disorders are reflected in the condition of the skin. One of the major functions of the skin is protection of the other organ systems from a variety of environmental insults. In this role, the skin itself is exposed to factors that can ultimately cause chronic diseases and cancer. Since it is relatively easy to recognize skin abnormalities, most skin cancers are brought to professional attention sooner than other types of ca… more

Date: October 1, 1991

Creator: Weller, R. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Input and decayed values of radioactive liquid wastes discharged to the ground in the 200 Areas through 1975

Low and intermediate level liquid wastes from chemical separations processing of spent reactor fuel elements have been discharged to the ground in the 200-Areas since 1944. Large volumes of process cooling water, normally free of radioactive contaminants, are discharged to surface ditches or natural surface depressions (ponds). Lesser volumes of liquid waste such as steam condensates, process condensates, scavenged process waste supernatants, and plutonium processing wastes have been, or are be… more

Date: July 8, 1976

Creator: Anderson, J. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Evaluation of the radionuclide concentrations in soil and plants from the 1975 terrestrial survey of Bikini and Eneu Islands

In June 1975 a radiological survey was conducted of the terrestrial environment of Bikini and Eneu islands (Bikini Atoll) to evaluate the potential radiation dose to the returning Bikini population. In this report, we present measurements of the radionuclide concentration in soil profiles and in dominant species of edible and nonedible, indicator plants. The use of these data to derive relationships to predict the plant uptake of radionuclides from soil is described. Approximately 620 soil and … more

Date: January 21, 1977

Creator: Colsher, C. S.; Robison, W. L. & Gudiksen, P. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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End of life fission product distributions in F-1 experiment fuel rods

Fission product migration and end-of-life distributions were examined in the F-1 (X094) series of sealed, mixed-oxide fuel rods irradiated in the fast flux of EBR-II. Cesium, rubidium, iodine, and strontium data obtained from axial gamma scanning, mass spectrometry, and radiochemical analyses are presented. The results show significant migration of cesium, probably as both a volatile species and as the noble gas precursor. Cesium metal species leaving the fuel region accumulate predominately at… more

Date: May 1, 1980

Creator: Goodin, D. T.; Langer, S. & Bell, W. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Sediment and radionuclide transport in rivers. Phase 3. Field sampling program for Cattaraugus and Buttermilk Creeks, New York

A field sampling program was conducted on Cattaraugus and Buttermilk Creeks, New York during April 1979 to investigate the transport of radionuclides in surface waters as part of a continuing program to provide data for application and verification of Pacific Northwest Laboratory's (PNL) sediment and radionuclide transport model, SERATRA. Bed sediment, suspended sediment and water samples were collected during unsteady flow conditions over a 45 mile reach of stream channel. Radiological an… more

Date: August 1, 1982

Creator: Ecker, R. M.; Walters, W. H. & Onishi, Y.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Quarterly report on the strontium heat source development program, Advanced Nuclear Systems and Projects Division for April-June 1980

Oak Ridge National Laboratory completed metallographic examination of the metal specimens from the 30,000-h compatibility tests with /sup 90/SrF/sub 2/. Electron microprobe analysis of the specimens is now under way. Results show that chemical attack of the 30,000-h specimens was not much greater than that observed in the 6000- to 20,000-h tests. Work continues on qualification testing of the as-fabricated prototype outer capsules. As-fabricated Hastelloy S and Hastelloy C-4 outer capsules pass… more

Date: July 1, 1980

Creator: Fullam, H. T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Research and development activities Waste Fixation Program. Quarterly progress report, January--March 1977

Research and Development activities of the Waste Fixation Program for January through March 1977 are described in this report. The objective of this program is to develop processes to convert high-level radioactive liquid waste (HLLW) to solid forms that are demonstrated to be physically, chemically, and radiolytically stable and inert. Several significant results were obtained during this reporting period.

Date: November 1, 1977

Creator: McElroy, J.L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tank 241-A-105 leak assessment

Tank 241-A-105 is one of 149 single shell tanks constructed at Hanford to contain and store highly radioactive wastes originating from the processing of spent nuclear reactor fuel. Radiation detection and temperature monitoring devices installed beneath the tank indicate that several episodes of leakage of waste from the tank have occurred. The aim of this study was to evaluate the previous estimates and reanalyze the data to provide a more accurate estimate of leakage from the tank. The princi… more

Date: June 1, 1991

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Radionuclide distributions and migration mechanisms at shallow land burial sites. Annual report of research investigations on the distribution, migration and containment of radionuclides at Maxey Flats, Kentucky. [Maxey Flats]

Subsurface waters at Maxey Flats are anoxic systems with high alkalinity and high concentrations of dissolved ferrous ion. Americium and cobalt in these trench waters are made more soluble by the presence of EDTA, while strontium and cesium are unaffected under the same conditions. EDTA is the major organic complexing component in waste trench 27 leachate, but other polar, water-soluble organics are also present. Evidence points to the migration of plutonium between waste trench 27 and inert at… more

Date: July 1, 1982

Creator: Kirby, L. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Minimum detectable activities of contamination control survey equipment

The Instrumentation External Dosimetry (I ED) Section of the Health Physics Department at the Pacific Northwest Laboratory (PNL) has performed a series of tests to determine the ability of portable survey instruments used at Hanford to detect radioactive contamination at levels required by DOE 5480.11. This semi-empirical study combines instrumental, statistical, and human factors as necessary to derive operational detection limits. These threshold detection values have been compared to existin… more

Date: August 1, 1991

Creator: Goles, R. W.; Baumann, B. L. & Johnson, M. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Waste migration studies at the Savannah River Plant burial ground

The low-level radioactive waste burial ground at the Savannah River Plant is a typical shallow-land-burial disposal site in a humid region. Studies of waste migration at this site provide generic data for designing other disposal facilities. A program of field, laboratory, and modeling studies for the SRP burial ground has been conducted for several years. Recent results of lysimeter tests, soil-water chemistry studies, and transport modeling are reported. The lysimeter experiments include ongo… more

Date: January 1, 1985

Creator: Stone, J A; Oblath, S B; Hawkins, R H; Grant, M W; Hoeffner, S L & King, C M

Item Type: Article

Partner: UNT Libraries Government Documents Department

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ORNL process waste treatment plant modifications

The ORNL Process Waste Treatment Plant removes low levels of radionuclides (primarily Cs-137 and Sr-90) from process waste water prior to discharge. The previous plant operation used a scavenging precipitaton - ion exchange process which produced a radioactive sludge. In order to eliminate the environmental problems associated with sludge disposal, the plant is being converted to a new ion exchange process without the precipitation process.

Date: January 1, 1982

Creator: Bell, J.P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Plutonium and Americium Concentration Along Fresh-Water Food Chains of the Great Lakes, U. S. A. Progress Report, July 1976--September 30, 1977

The primary purpose of studying the biogeochemical behavior of transuranic radionuclides in large freshwater lakes began with studies of the distribution of these radionuclides, essentially introduced from the fallout of atmospheric nuclear weapons tests, in Lake Ontario. The recognition that an additional source of supply of these nuclides to Lake Ontario (subsequent to their release into Lake Erie) existed in the form of leakage from the Nuclear Fuel Services reprocessing plant at Springville… more

Date: January 1, 1977

Creator: Bowen, V. T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Status report on LWR spent fuel IAEA leach tests

Spent light-water-reactor (LWR) fuel with an average burnup of 28,000 MWd/MTU was leach-tested at 25/sup 0/C using a modified version of the International Atomic Energy Agency procedure. Leach rates were determined from tests conducted in five different solutions: deionized water, sodium chloride (NaCl), sodium bicarbonate (NaHCO/sub 3/), calcium chloride (CaCl/sub 2/) and Waste Isolation Pilot Plant B brine solutions. Elemental leach rates are reported based on the release of /sup 90/Sr + /sup… more

Date: March 1, 1980

Creator: Katayama, Y.B.; Bradley, D.J. & Harvey, C.O.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Leach and soil column tests with stored redox sludge

The leachabilities of /sup 90/Sr, /sup 239/Pu, and /sup 137/Cs from solids in Tank 108-SX were determined. Through 21 leach cycles covering a 3.5 day period, 63 volumes of leachate removed 1.4, 4.6, and 19.2% of the /sup 239/Pu, /sup 90/Sr, and /sup 137/Cs, respectively, from the 108-SX solids. With the exception of the first few leachates, the /sup 239/Pu concentrations in the leachates were less than maximum permissible concentration in drinking water for 168-h/wk exposure. A composite of the… more

Date: May 1, 1970

Creator: Schulz, W. W. & Ritter, G. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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1985 environmental monitoring report

The environmental monitoring program is designed to determine that BNL facilities operate such that the applicable environmental standards and effluent control requirements have been met. The data were evaluated using the appropriate environmental regulatory criteria. The environmental levels of radioactivity and other pollutants found in the vicinity of BNL during 1985 are summarized in this report. Detailed data are not included in the main body of the report, but are tabulated and presented … more

Date: April 1, 1986

Creator: Day, L.E.; Miltenberger, R.P. & Naidu, J.R. (eds.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Design and qualification testing of a strontium-90 fluoride heat source

The Strontium Heat Source Development Program began at the Pacific Northwest Laboratory (PNL) in 1972 and is scheduled to be completed by the end of FY-1981. The program is currently funded by the US Department of Energy (DOE) By-Product Utilization Program. The primary objective of the program has been to develop the data and technology required to permit the licensing of power systems for terrestrial applications that utilize /sup 90/SrF/sub 2/-fueled radioisotope heat sources. A secondary ob… more

Date: December 1, 1981

Creator: Fullam, H. T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Research in radiobiology. Annual report of work in progress in the internal irradiation program

Separate abstracts were prepared for 13 sections of this report. A list is included of publications during the time period covered by this report.

Date: March 31, 1977

Creator: Jee, W.S.S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Process innovations to minimize waste volumes at Savannah River

In 1983 approximately 1.6 x 10/sup 3/ m/sup 3/ (427,000 gallons) of radioactive salt solution were decontaminated in a full-scale demonstration. The cesium decontamination factor (DF) was in excess of 4 x 10/sup 4/ vs. a goal of 1 x 10/sup 4/. Data from this test were combined with pilot data and used to design the permanent facilities currently under construction. Startup of the Salt Decontamination Process is scheduled for 1987 and will decontaminate 2 x 10/sup 4/ m/sup 3/ (5.2 million gallon… more

Date: January 1, 1986

Creator: Doherty, J P

Item Type: Article

Partner: UNT Libraries Government Documents Department

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HYPERFUSE: a novel inertial confinement system utilizing hypervelocity projectiles for fusion energy production and fission waste transmutation

Parametric system studies of an inertial confinement fusion (ICF) reactor system to transmute fission products from an LWR economy have been carried out. The ICF reactors would produce net power in addition to transmuting fission products. The particular ICF concept examined is an impact fusion approach termed HYPERFUSE, in which hypervelocity pellets, traveling on the order of 100 to 300 km/sec, collide with each other or a target block in a reactor chamber and initiate a thermonuclear reactio… more

Date: January 1, 1980

Creator: Makowitz, H; Powell, J R & Wiswall, R

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Hydrologic factors and /sup 90/Sr transport at a low-level waste disposal site

A case study of a solid waste storage area at Oak Ridge National Laboratory is presented. The purpose of the study is to devise effective remedial actions based upon understanding of the underlying processes governing radionuclide migration. Discussion is presented under the following headings: site history; radionuclide transport studies; analysis of field results; and recommended remedial action.

Date: January 1, 1982

Creator: Huff, D.D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Selection and evaluation of processes for recovery of beneficial isotopes from commerical reactor wastes

Conceptual processes were prepared for recovering isotopes from stored high-level liquid wastes to define equipment and facility requirements. Capital costs were estimated for each process. Four different facilities were studied for potential isotope recovery. The processes were for the recovery of: cesium only; strontium only; cesium and strontium; and cesium, strontium, promethium, americium, curium, neptunium, and the platinum metals. The selection of these recovery processes was determined … more

Date: December 1, 1977

Creator: Davis, D.K.; Partridge, J.A. & Koski, O.H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Alternate strategy for commercial high-level radioactive-waste management

A current strategy of geologic disposal of immobilized commercial, high-level, nuclear wastes provides long-term storage (hundreds of thousands of years) for a wide spectrum of wastes from the Purex process which would be immobilized in a borosilicate glass. When implaced in a repository, the temperature increases and peaks within the geologic formations housing the waste repository during the first several hundred years after burial and then declines towards the initial temperature. During thi… more

Date: January 1, 1982

Creator: Northrup, C.J.; Jardine, L.J. & Steindler, M.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department