NTIS
Reports can be ordered by: phone at 1-800-553-NTIS (U.S.
customers); (703)605-6000 (other countries); fax at (703)605-6900;
and email at orders@ntis.gov. NTIS is located at 5285 Port
Royal Road, Springfield, VA, 22161, USA.
|
| Order
Number
Source
Number |
Date
Published / Title / Author & Affiliation / Sponsor Agency |
Abstract
/Keywords |
NTIS/DE88010138
4p |
1988.
Acute Toxicity of Uranium Hexafluoride, Uranyl Fluoride and
Hydrogen Fluoride.
Author:
Just RA
Oak
Ridge National Lab., TN. |
Uranium
hexafluoride (UF sub 6 ) released into the atmosphere will react
rapidly with moisture in the air to form the hydrolysis products
uranyl fluoride (UO sub 2 F sub 2 ) and hydrogen fluoride (HF).
Uranium compounds such as UF sub 6 and UO sub 2 F sub 2 exhibit
both chemical toxicity and radiological effects, while HF exhibits
only chemical toxicity. This paper describes the development
of a methodology for assessing the human health consequences
of a known acute exposure to a mixture of UF sub 6 , UO sub
2 F sub 2 , and HF. 4 refs., 2 figs., 5 tabs. Portions of this
document are illegible in microfiche products. Uranium hexafluoride--safe
handling, processing, and transporting conference, Oak Ridge,
TN, USA, 24 May 1988. |
NTIS/DE89001994
Portions
of this document are illegible in microfiche products.
12p |
1988.
Environmental Monitoring at the US Department of Energy's
Hanford Site, Washington.
Author:
Gray RH
Battelle
Pacific Northwest Labs., Richland, WA. |
Environmental
monitoring objectives are to detect and assess potential impacts
of site operations on air, surface and ground water, foodstuffs,
fish, wildlife, soil and vegetation. Data from monitoring effects
are used to calculate the overall radiological impact to humans
working onsite or residing in nearby communities, and to assess
the impact of Hanford operations on the environment. In 1987,
measured Hanford Site perimeter concentrations of airborne radionuclides
were below applicable DOE and Environmental Protection Agency
guidelines. Tritium and nitrate continued to be the most widespread
constituents in onsite ground water. Chromium, cyanide, fluoride,
and carbon tetrachloride were found in
ground-water wells near operating areas. Concentrations
of radionuclides and nonradiological water quality in the Columbia
River at a municipal water intake were in compliance with applicable
standards. Foodstuffs irrigated with river water taken downstream
of the Site showed low levels of radionuclid [abstract truncated] |
NTIS/DE89613841
U.S. Sales
Only.
97p |
1988.
Environmental Monitoring Program of the Uranium Enrichment
Facility Almirante Alvaro Alberto.
Authors:
Hiromoto G
Jacomino VMF
Venturini L
Moreira SRD
Gordon AMPL
Instituto
de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil). |
In this
report, the Environmental Monitoring Program of the Uranium
Enrichment Facility Almirante Alvaro Alberto is outlined and
the results obtained during the preoperational period are presented.
Information concerning the population distribution, the use
of water and land, the local agricultural production and the
local meteorology are also available. In order to evaluate the
levels of the background radiation, sample of water, air and
biological and terrestrial indicators were analysed. Measurements
were performed of natural gamma emitters concentrations levels
and of uranium in air, surface water, precipitation, groundwater,
river sediment, soil, grass, vegetation and various foodstuffs.
For direct measurement of background radiation levels a solid
state dosimeter network was used. Results are also presented
for the analysis of non radioactive pollutants in the water
samples and for the particles and gaseous fluorides concentration
in the atmosphere. (Atomindex citation 20:041496) In Portugese. |
NTIS/PB92-205939
33p |
1988.
Rank Analysis of Urine Data to Identify Differentially Exposed
Subcohorts for a Uranium Enrichment Mortality Study.
Authors:
Bloom TF
Brown DP
National
Inst. for Occupational Safety and Health, Cincinnati, OH. |
As part
of a cohort mortality study at a uranium enrichment facility,
investigators used urinalysis data collected by the facility
to identify three department based subcohorts exposed to uranyl-fluoride
(7783815). Each subcohort was considered to represent employees
at greater exposure risk. Details are presented concerning the
development and application of the methods of subcohort identification.
Inhalation of uranyl-fluoride was the
primary exposure of concern at the facility. For the
first subcohort selection method all workers who were ever employed
in departments in which at least 100 urine uranium (7440611)
analyses had been reported over the 28 year span of the data
base were included. An additional method was used which allowed
two additional subcohorts to be taken from the first cohort.
The method was based on the assumption that a department having
a greater percentage of measurements exceeding action level
criteria had a greater exposure potential. The usefulness of
these methods fo [abstract truncated] |
NTIS/DE88001369
Portions
of this document are illegible in microfiche products.
93p |
1987.
Hydrofluoric
Acid Spill Area: Environmental Information Document.
Authors:
Huber LA
Bledsoe HW
Savannah
River Lab., Aiken, SC.
Supporting
Agency: Department of Energy,
Washington, DC. |
The
Hydrofluoric Acid Spill Area is located in the Central Shops
Area of the Savannah River Plant (SRP).
It is uncertain if a spill occurred at this site or if contaminated
soil or containers were buried here. Soil cores from the Hydrofluoric
Acid Spill Area have not been collected or analyzed. Four groundwater
monitoring wells were installed around the spill area in 1984
and have been sampled quarterly since early 1985. The potential
impacts of lead and fluoride were assessed because of their
measured groundwater concentrations. The closure options considered
for the Hydrofluoric Acid Spill Area are waste removal and closure,
no waste removal and closure, and no action. The predominant
pathways for human exposure to chemical and/or radioactive constituents
are through surface, subsurface, and atmospheric transport.
Modeling calculations were made to determine the risk to human
population via these general pathways for the three postulated
closure options. An ecological assessment was conducted [abstract
truncated] |
NTIS/DE88705041
U.S. Sales
Only.
8p |
1987.
Study on the Radiotoxicology of Enriched Uranium.
Authors:
Zhu S
Zheng S
Wang G
Wang C
Cao G
China
Nuclear Information Centre, Beijing. |
A study
on the retentive peculiarity of soluble enriched uranium UO22
were observed. After iv once or consecutive ip qd x 3d to Wistar
male rats, the dynamic retention of radioactivity in the body
showed that the enriched uranium UO2/F2 was chiefly localized
in the kidney, and then in the skeleton and liver. The radioactivity
of the enriched uranium UO2/F2/ in the skeleton rose steadily
while the concentration in the kidney and liver dropped. When
enriched uranium UO2/F2/ accumulated in the organism, it caused
chromosome aberrations in bone marrow cells. Results indicated
that the chromosome aberration rates were elevated when the
dose of the enriched uranium UO2/F2/ was increased, at the same
time, the cell division was depressed. Penetration of the enriched
uranium UO2/F2/ was dominantly increased in abraded skin. This
value is about 25 to 32 times as compared with that in intact
skin. Retention of the enriched uranium UO2/F2/ through abraded
skins was dominantly localized in kidney and skelet [abstract
truncated] |
NTIS/DE87010911
Paper
copy only, copy does not permit microfiche production.
65p |
1987.
Investigation Report: Toxic Gas Release from the beta-gamma
Incinerator at the Savannah River Plant on
December 9, 1986.
Department
of Energy, Aiken, SC. Savannah River Operations Office. |
On December
9, 1986, a scheduled functional test of the Halon fire suppression
system in the Feed Lag Storage Area (FLA) of the BGI facility
was initiated by manually activating the Halon system. Interlocks
that shutdown ventilation in the FLA operated as designed, and
the 756-lb charge of Halon 1301 was released into the FLA as
intended. Normal building air flow designed to minimize spread
of contamination, plus a momentary increase in pressure in the
FLA resulting from the discharge of Halon, caused an estimated
450 lb of Halon to enter the adjacent process room through a
number of small openings in the sheetmetal separating wall.
About 240 lb of the Halon was drawn into
the incinerator where it thermally decomposed into hydrogen
fluoride and bromine. These gases were discharged through the
incinerator stack. About 10:20 a.m., some employees, working
approximately 1500 ft downwind, began to experience eye and
respiratory irritation. An orange-yellow plume was observed
to be coming from the BGI [abstract truncated] |
NTIS/PB87-188991
55p |
1987.
Mortality among Uranium Enrichment Workers,
Authors:
Brown DP
Bloom T
National
Inst. for Occupational Safety and Health, Cincinnati, OH. |
A retrospective
cohort mortality study was conducted on workers at the Portsmouth
Uranium Enrichment facility (SIC-1094) in Pike
County, Ohio, in response to a request from the Oil,
Chemical and Atomic Workers International Local 3-689 for information
on long term health effects. Primary hazards
included inhalation exposure to uranyl-fluoride (13536-84-0)
containing uranium-235 (15117961) and uranium-234 (13966295),
technetium-99 (14133767) compounds, and hydrogen-fluoride
(7664-39-3). Uranium-238 (7440611) presented a nephrotoxic
hazard. Statistically significant mortality
deficits based on U.S. death rates were found for all causes,
accidents, violence, and diseases of nervous, circulatory, respiratory,
and digestive systems. Standardized mortality rates were
85 and 54 for all malignant neoplasms and for other genitourinary
diseases, respectively. Deaths from stomach cancer and lymphatic/hematopoietic
cancers were insignificantly increased. A subcohort selected
for greatest potential uranium expos [abstract truncated] |
NTIS/DE86011327,
Portions
of this document are illegible in microfiche products.
21p |
1986.
Fluoride Levels in Vegetation in the Vicinity of the Portsmouth
Gaseous Diffusion Plant. Final Report.
Author:
Jackson DR
Battelle
Columbus Labs.,
OH.
Supporting
Agency: Goodyear Atomic Corp.,
Piketon, OH
Department of Energy, Washington,
DC. |
Battelle
initiated a survey of vegetation samples at new and established
sites in the vicinity of the Portsmouth Gaseous Diffision Plant.
Forty-nine vegetation samples were collected and analyzed for
fluoride. Three samples from inside the plant boundaries contained
fluoride in concentrations great enough to be of concern to
grazing livestock (>40 ppm). All other samples were below
the action level. Fluoride concentrations
in vegetation reported by Battelle were somewhat greater than
identical samples analyzed by GAT. This differences may be accounted
for by the fact that GAT rinsed their samples prior to the analysis
for fluoride while Battelle did not. Battelles' samples were
not washed because fluoride containing particulates on the surface
of vegetation can be readily ingested by livestock and may contribute
to the total amount of fluoride absorbed by the livestock.
Results of the vegetational survey were not correlated with
the deposition pattern modeled by Battelle. Apparently, levels
o [abstract truncated] |
NTIS/NUREG-1189-V2
425p |
1986.
Assessment of the Public Health Impact from the Accidental
Release of UF6 at the Sequoyah Fuels Corporation Facility
at Gore, Oklahoma, Docket No. 40-8027, License No.
SUB-1010. Appendices.
Nuclear
Regulatory Commission,
Washington, DC. |
Following
the accidental release of UF6 from the
Sequoyah Fuels Facility on January 4, 1986, an Ad Hoc
Interagency Public Health Assessment Task Force was established.
The Task Force consists of technical staff members from various
agencies who have prepared this assessment of the public health
impact associated with the accidental release. The assessment
is based on data from the accident available as of February
14, 1986, and describes the chemical and radiological effects
from the intake of uranium and fluoride.
Volume 2 of the report consists of Appendices which provide
more detailed information used in the assessment. |
NTIS/NUREG-1179-V1
145p |
1986.
Rupture of Model 48Y UF sub 6 Cylinder and Release of Uranium
Hexafluoride, Sequoyah Fuels Facility, Gore,
Oklahoma, January 4, 1986,
Authors:
Smith RD
Cain CL
Chappell R
Nuclear
Regulatory Commission,
Washington, DC. |
At 11:30
a.m. on January 4, 1986, a Model 48Y UF6 cylinder filled with
uranium hexafluoride (UF6) ruptured while it was being heated
in a steam chest at the Sequoyah Fuels Conversion Facility near
Gore, Oklahoma. One worker died because
he inhaled hydrogen fluoride fumes, a reaction product
of UF6 and airborne moisture. Several other workers were injured
by the fumes, but none seriously. Much
of the facility complex and some offsite areas to the south
were contaminated with hydrogen fluoride and a second reaction
product, uranyl fluoride. The interval of release was
approximately 40 minutes. The cylinder, which had been overfilled,
ruptured while it was being heated because of the expansion
of UF6 as it changed from the solid to the liquid phase. The
maximum safe capacity for the cylinder is 27,560 pounds of product.
Evidence indicates that it was filled with an amount exceeding
this limit. |
NTIS/DE87013041
Portions
of this document are illegible in microfiche products.
271p |
1986.
H-Area Seepage Basins: Environmental Information Document.
Authors:
Killian TH
Kolb NL
Corbo P
Savannah
River Lab., Aiken, SC.
Supporting
Agency: Department of Energy,
Washington, DC. |
The basins
contain liquid low-level radioactivity and chemicals from the
H-Area separations facility. Wells monitor the water table in
the vicinity of the basins and also underlying aquifers to detect
any vertical contaminant migration. A
statistical analysis of monitoring data from this site indicates
elevated levels of chloride, fluoride,
manganese, mercury, nitrate, sodium, and total radium in the
groundwater. The predominant pathways for human exposure to
contaminants are surface, subsurface, and atmospheric transport.
Modeling calculations were performed to determine the risks
to humans via these pathways for the postulated closure options.
Modeling calculations were also performed to determine ecological
impacts. The environmental impact evaluation indicates that
the relative human health risks for all closure options are
low. Tritium, the dominant radionuclide, reached a maximum risk
in Year -29 (from 1985) of 2.7E-04 HE/yr. Results of the atmospheric
pathway modeling indicate that risks [abstract truncated] |
NTIS/DE86011148
60p |
1986.
Environmental
Monitoring Report. United States Department of Energy, Paducah
Gaseous Diffusion Plant. Calendar Year 1985.
Paducah
Gaseous Diffusion Plant, KY. |
Air, water,
soil, sediments, grass, and groundwater in the vicinity of the
Paducah Gaseous Diffusion Plant were continuously or periodically
sampled during 1985. Analyses for materials known to be in plant
effluents were made to provide effluent control information
and to determine compliance with applicable environmental standards.
Low sulfur coal is burned in the steam plant to meet Kentucky
emission limits for sulfur dioxide. Air analyses for radioactivity
indicated concentrations at each offsite sampling station continue
to remain at low levels as indicated by calculations of potential
radiation dose to the public. Off-site analyses for fluorides
in grass met the Kentucky Air Quality Requirements. All
on-site and off-site airborne fluoride samples met the Kentucky
one-week and one-month standards for gaseous HF. Soil
samples were analyzed for uranium and showed no significant
deviation from normal background concentrations. The results
of water sample analyses of the Ohio River show the chro [abstract
truncated] |
NTIS/NUREG-1189-V1
100p |
1986.
Assessment
of the Public Health Impact from the Accidental Release of
UF6 at the Sequoyah Fuels Corporation Facility at Gore,
Oklahoma, Docket No. 40-8027, License No. SUB-1010.
Main Report.
Nuclear
Regulatory Commission, Washington, DC. |
Following
the accidental release of UF6 from the Sequoyah Fuels Facility
on January 4, 1986,
an Ad Hoc Interagency Public Health Assessment Task Force was
established. The Task Force consists of technical staff members
from various agencies who have prepared this assessment of the
public health impact associated with the accidental release.
The assessment is based on data from the accident available
as of February 14, 1986, and describes
the chemical and radiological effects from the intake of uranium
and fluoride. Volume 1 of the report describes the effects from
the intake of uranium and fluoride and summaries the findings
and recommendations of the Task Force. See also NUREG-1189-V2. |
NTIS/PB90-179276
18p |
1985.
NIOSH (National Institute for Occupational Safety and Health)
Testimony on the Safety of Nuclear Facility Workers by P.
J. Bierbaum on April 22, 1985.
National
Inst. for Occupational Safety and Health, Cincinnati, OH. |
The testimony
concerned the National Institute for Occupational Safety and
Health (NIOSH) activities related to the health and safety of
workers employed at nuclear facilities. Three NIOSH studies
were noted, including an evaluation in progress at the Feed
Materials Production Center in Fernald, Ohio, a study of radiation
exposure at the Goodyear Atomic Corporation (GAC) in Piketon,
Ohio, and a study of deaths from cancer at the Portsmouth Naval
Shipyard in Kittery, Maine. In the first study the union representatives
at the FMPC had several health and safety issues that they wanted
NIOSH to evaluate. Additional requests have been made by the
union at this facility in relation to reported uranium (7440611)
releases from the site. NIOSH recommended that all potentially
exposed workers undergo bioassay testing to determine lung burdens
of uranium. At GAC workers requested an
evaluation because of exposure to radiation from uranium-hexafluoride
(7783-81-5). Total mortality for radiation workers was si [article
truncated] |
NTIS/DE85010613
109p |
1985.
Environmental Monitoring at Argonne National Laboratory. Annual
Report for 1984.
Authors:
Golchert NW
Duffy TL
Sedlet J
Argonne
National Lab., IL. |
The
results of the environmental monitoring program at Argonne
National Laboratory for 1984 are presented and discussed.
To evaluate the effect of Argonne operations on the environment,
measurements were made for a variety of radionuclides in air,
surface water, ground water, soil, grass, bottom sediment,
and milk; for a variety of chemical constituents in surface
water, ground water, and Argonne effluent water; and of the
environmental penetrating radiation dose. Sample collections
and measurements were made on the site, at the site boundary,
and off the Argonne site for comparison purposes. The potential
radiation dose to off-site population groups is also estimated.
The results of the program are interpreted in terms of the
sources and origin of the radioactive and chemical substances
(natural, fallout, Argonne, and other) and are compared with
applicable environmental quality standards. 20 refs., 8 figs.,
46 tabs. (ERA citation 10:026100)
Keywords
include: Fluorides |
NTIS/DE85012322
21p |
1985.
Reaction of Uranium and the Fluorocarbon FC-75.
Author:
Young RH
Du
Pont de Nemours (E.I.) and Co., Aiken, SC. Savannah River
Lab.
Supporting
Agency: Department of Energy,
Washington, DC. |
Because
of criticality concerns with water cooling in enriched uranium
upgrading, a fluorocarbon has been evaluated as a replacement
coolant for internal module components in the Plasma Separation
Process (PSP). The interaction of bulk uranium and of powdered
uranium with FC-75 has been investigated at temperatures between
200 and 700 exp 0 C. The gas pressure and the metal temperature
were monitored as a function of time. Modest temperature changes
of 50 to 100 exp 0 C were observed for the bulk uranium/fluorocarbon
reaction. Much larger changes (up to 1000 exp 0 C) were noted
for the reaction involving high surface area uranium powder.
These temperature transients, particularly for the powdered
uranium reaction, were short-lived (<10 seconds) and indicative
of the formation of a protective layer of reaction products.
Analysis of residual gas products by infrared spectroscopy indicated
that one potentially serious hazard, UF sub 6 , was not present;
however, several small toxic fluorocarbons [abstract truncated] |
NTIS/DE86013803
21p |
1985.
Process
for Reducing beta Activity in Uranium.
Authors:
Briggs GG
Kato TR
Schonegg E
Department
of Energy, Washington, DC. |
This invention
is a method for lowering the beta radiation hazards associated
with the casting of uranium. The method reduces the beta radiation
emitted from the as-cast surfaces of uranium ingots. The method
also reduces the amount of beta radiation emitters retained
on the interiors of the crucibles that have been used to melt
the uranium charges and which undergone cleaning in a remote
handling facility. The lowering of the
radioactivity is done by scavenging the beta emitters from the
molten uranium with a molten mixture containing the fluorides
of magnesium and calcium. The method provides a means
of collection and disposal of the beta emitters in a manner
that reduces radiation exposure to operating personnel in the
work area where the ingots are cast and processed. 5 tabs. (ERA
citation 11:004809) Patent Application, [abstract truncated]
|
NTIS/DE84014303
22p |
1984.
Generic
Report on Health Effects for the US Gaseous Diffusion Plants.
Sect. 8, Pt. 1.
Authors:
Just RA
Emler VS
Oak
Ridge Gaseous Diffusion Plant, TN. |
Toxic
substances present in uranium enrichment plants include uranium
hexafluoride (UF sub 6 ), hydrogen fluoride (HF), uranyl fluoride
(UO sub 2 F sub 2 ), chlorine (Cl sub 2 ), chlorine trifluoride
(ClF sub 3 ), fluorine (F sub 2 ), uranium tetrafluoride (UF
sub 4 ), and technetium (Tc). The
current knowledge of the expected health effects of acute exposures
to these substances is described. 10 references, 2 figures,
6 tables. (ERA citation 09:036379) |
NTIS/DE85001420
142p |
1984.
Formerly
Utilized MED Sites Remedial Action Program. Radiological Survey
of the Harshaw Chemical Company, Cleveland,
Ohio.
Authors:
Wynveen RA
Smith WH
Sholeen CM
Justus AL
Flynn KF
Argonne
National Lab., IL.
Supporting
Agency: Department of Energy,
Washington, DC. |
During
the MED era, the Harshaw Chemical Company processed large quantities
of normal uranium to produce both oxide and fluoride compounds.
This
work was done under contract to MED and its successor, AEC.
Records indicated that at the time the AEC contract was terminated,
the facility was decontaminated by Harshaw and released from
AEC control in 1960. However, a search of AEC records indicated
that documentation was insufficient to determine whether the
decontamination work was adequate by current guidelines. Hence,
a radiological assessment of the site ws initiated in 1976.
The entire grounds and all buildings were surveyed using surface
survey instruments to detect surface contamination and radiation
detectors to determine general radiation levels. Extensive
surface contamination was found throughout the site. While
the major contamination was found in Plant C, significant levels
of contamination also were found in 16 other buildings and at
32 exterior locations. The contaminating material se [abstract
truncated] |
NTIS/DE86700473
U.S. Sales
Only
66p |
1984.
Toxicity
Levels to Humans During Acute Exposure to Hydrogen Fluoride.
Authors:
Halton DM
Dranitsaris P
Baynes CJ
Atomic
Energy Control Board, Ottawa (Ontario). |
A
literature review was conducted of the acute toxicity of hydrogen
fluoride (HF) with emphasis on the effects of inhalation of
gaseous HF.
The data and findings of the relevant references were summarized
under four categories: animal studies, controlled human studies,
community exposure and industrial exposure. These were critically
reviewed and then lethal concentration-time relationships were
developed for humans, corresponding to LCsub(LO), LCsub(10)
and LCsub(50) levels. The effects of age, health and other physiological
variables on the sensitivity to HF were discussed, as well as
antagonistic and synergistic effects with other substances.
(Atomindex citation 16:077051) |
NTIS/DE85006578
98p |
1984.
Evaluation
of Improved Chemical Waste Disposal and Recovery Methods for
N Reactor Fuel Fabrication Operations: 1984 Annual Report.
Authors:
Stewart TL
Hartley JN
Battelle
Pacific Northwest Labs., Richland, WA.
Supporting
Agency: Department of Energy,
Washington, DC. |
Pacific
Northwest Laboratory personnel identified and evaluated alternative
methods for recovery, recycle, and disposal of waste acids produced
during N Reactor fuel operations. This work was conducted under
a program sponsored by UNC Nuclear Industries, Inc.; the program
goals were to reduce the volume of liquid waste by rejuvenating
and recycling acid solutions and to generate a residual waste
low in nitrates, fluorides, and
metals. Disposal methods under consideration included nitric
acid reclamation, grout encapsulation of final residual waste,
nitrogen fertilizer production, biodenitrifaction, chemical
or thermal destruction of NO sub 3 , and short-term impoundment
of liquid NO sub 3 sub 4 wastes. Preliminary testing indicated
that the most feasible and practicable of these alternatives
were (1) nitric acid reclamation followed by grouting of residual
waste and (2) nitrogen fertilizer production. This report summarizes
the investigations, findings, and recommendations for the 1984
fiscal y [abstract truncated] |
NTIS/PB86-120805
Customers
in the European Community countries should apply to the Office
for Official Publications of the European Communities, B.P.
2985, Luxembourg.
83p |
1984.
(Decontamination
by Ultrafiltration of Low-Activity Uranium-Contaminated Waste
Waters from Fuel Element Production),
Author:
Muller HM
Commission
of the European Communities, Luxembourg. |
It can
be demonstrated that waste waters which contain uranium in a
filterable form, such as laundry and floor-cleaning waste, can
be sufficiently decontaminated by means of ultrafiltration.
In the case of process waste solutions, which contain uranium
in a dissolved form, high decontamination factors could be achieved
by means of flocculation or coprecipitation. Various methods
were tested: The phosphate precipitation, whereby the uranium
is probably coprecipitated as Ca(UO2)2(PO4)2, was found to be
the most reliable method. Difficulties
were encountered when complex-forming anions, notably carbonate,
oxalate and fluoride were present. These necessitate specific
pretreatment steps. Whether ultrafiltration then still remains
an economical option must be judged in each individual case.
In combination with a phosphate precipitation, ultrafiltration
is a suitable method for the decontamination of low-activity,
uranium-contaminated waste waters. Text in German. |
| NTIS/DE84011539
Portions
are illegible in microfiche products.
129p |
1984.
Acute
Toxicity of the Hydrolysis Products of Uranium Hexafluoride
(UF Sub 6 ) when Inhaled by the Rat and Guinea Pig. Final
Report.
Authors:
Leach LJ
Gelein RM
Panner BJ
Yulie CL
Cox CC
Rochester
Univ. Medical Center, NY. |
This
report presents the experimental animal data base from which
human health consequences may be predicted from exposures mimicing
accidental discharges of uranium hexafluoride (UF sub 6 ) in
the uranium industry.
Rats or guinea pigs were exposed for two, five, or ten minutes
duration to air having 0.44 g U/m exp 3 + 0.16 g HF/m exp 3
to 276.67 g U/m exp 3 + 94.07 g HF/m exp 3 . Survivors of each
exposure were observed for 14 days for signs of U or HF intoxication.
Selected animals were necropsied and samples of major organs
were studied histopathologically. When enriched UF sub 6 (94
percent exp 235 U) was used, the urine and feces from each animal
were measured daily for U content. Selected samples of urine
were bioassayed in order to trace the course of renal injury
during the two week postexposure period. 28 references, 51 figures,
23 tables. (ERA citation 09:031808) |
NTIS/DE84015354
Portions
are illegible in microfiche products.
85p |
1984.
Report
on Toxicological Studies Concerning Exposures to UF sub 6
and UF sub 6 Hydrolysis Products.
Author:
Just RA
Oak
Ridge Gaseous Diffusion Plant, TN. |
This
report presents estimates of the toxicity of uranium and hydrogen
fluoride. Recommendations
for the use of this information in safety analysis reports are
given. 6 references, 2 figures, 4 tables. (ERA citation 09:038618) |
NTIS/DE84009118
36p |
1984.
Development
of Processes for the Solubilization of Uranium from Waste
Leach Residue.
Authors:
Seeley FG
Kelmers AD
Laggis EG
Oak
Ridge National Lab., TN.
Supporting
Agency: Department of Energy,
Washington, DC. |
Two processes,
capable of solubilizing enriched uranium from refractory leach
residue solids generated at the Y-12 processing facility, have
been developed and tested on a laboratory scale. Both processes
take advantage of a sinter step, followed by leaching with nitric
acid. One process, designated the Calsinter method, uses a source
of CaO as a sintering media to react with refractory metal silicates
and provide subsequent solubilization of uranium from the sinter
matrix by an acid leach. The sintering step in this case requires
a temperature of approximately 1200 exp 0 C. The
second process employs fluoride in the sinter media to free
the uranium from any refractory silicate, thus rendering it
soluble in subsequent acid leaching. A sintering temperature
of 700 to 900 exp 0 C is used in this process. Both methods
are capable of solubilizing 90 to 99% of the uranium remaining
in the leach residue which, after current solids leaching treatment
at the Y-12 Plant, still contains 1 to 3% enriched u [abstract
truncated] |
| NTIS/DE83011105,
68p |
1983.
Investigation
of Occupational Illnesses at the 222-S Building on December
8, 1982.
Authors:
Louk WL
Hevland ME
Lilly AW
Owens GC
Atomics
International Div., Richland, WA. Rockwell Hanford Operations. |
On the
afternoon of December 8, 1982, three Rockwell Chemical Technologists,
B, D, and E, were transported to Kadlec Hospital with varying
degrees of dermatitis and respiratory problems. One chemical
technologist was held overnight and released to return to work
on December 13, 1982. The other two were not released until
December 16, 1982, and continuing ill effects have prevented
their return to work. The chemical technologists'
symptoms developed initially during a sodium fluoride repackaging
operation in Room 4M of the 222-S Analytical Laboratory. The
sodium fluoride was being repackaged from a 25-lb box of the
material into 500-g quart ice cream cartons. The repackaging
was done inside a chemical fume hood. The closed cartons were
removed from the hood and sealed with tape on a laboratory bench.
Procedurally, the final taping was to be done in the hood. Events
and causal factors associated with the incident are summarized.
It is concluded that extreme sensitivity of the three individuals
to [abstract truncated] |
NTIS/DE86780019
U.S. Sales
Only.
52p |
1983.
Fluorination of Solid UF sub 6 Decomposition Products by Gaseous
Mixtures of CBrF sub 3 and F sub 2.
Author:
Maner A
Karlsruhe
Univ. (Germany, F.R.). Fakultaet fuer Maschinenbau. |
Gaseous
mixtures of CBrF sub 3 and F sub 2 exhibit some advantages in
the removal of solid UF sub 6 decomposition products from uranium
enrichment installations. To facilitate optimal application,
the self decomposition of these mixtures as well as their interactions
with uranyl fluoride have been studied in a stainless steel
cell equipped with AgCl windows for IR analysis. It has been
found that self decomposition with low F sub 2 content causes
BrF sub 3 to show up besides the common reaction products, BrF
sub 5 and CF sub 4 . The fluorination of uranyl fluoride results
in a retardation of the BrF sub 5 formation as compared to the
formation of CF sub 4 due to a temporary accumulation of bromine
in low valency states on the surface of the solid uranium compound.
The reaction rate for the fluorination of uranyl fluoride increases
within certain limits with decreasing F sub 2 content of the
mixture. For the practical application of the more reactive
mixtures with low F sub 2 content it is import [abstract truncated] |
NTIS/DE83011816
40p |
1983.
Environmental Monitoring Report: United States Department
of Energy Paducah Gaseous Diffusion Plant, Calendar Year 1982.
Paducah
Gaseous Diffusion Plant, KY. |
Air, water,
soil, and grass were analyzed for materials known to be in plant
effluents to provide effluent control information and to determine
compliance with applicable air and water quality standards.
Offsite air radioactivity averaged less than 1% of the applicable
Radioactivity Concentration Guide. Offsite analyses for fluorides
in grass met the Kentucky Air Quality Requirements. All onsite
and offsite airborne fluoride samples met the Kentucky standards
for gaseous HF. Soil samples were analyzed for uranium and showed
no significant deviation from normal background concentrations.
There was no detectable change in characteristics of either
the Ohio River or ground water attributable to plant operations.
The chromium and fluoride concentrations in the Ohio River were
in compliance with applicable Kentucky regulations. The concentration
of hexavalent chromium in Little Bayou Creek has occasionally
been in excess of the Kentucky aquatic life standard of 0.05
mg/1 due to cooling tower windage. |
