Determination of actinides in urine and fecal samples
Patent
·
OSTI ID:868684
- Larimer County, CO
A method of determining the radioactivity of specific actinides that are carried in urine or fecal sample material is disclosed. The samples are ashed in a muffle furnace, dissolved in an acid, and then treated in a series of steps of reduction, oxidation, dissolution, and precipitation, including a unique step of passing a solution through a chloride form anion exchange resin for separation of uranium and plutonium from americium.
- Research Organization:
- WESTINGHOUSE IDAHO NUCLEAR CO
- DOE Contract Number:
- AC07-84ID12435
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Number(s):
- US 5190881
- OSTI ID:
- 868684
- Country of Publication:
- United States
- Language:
- English
Actinide separations for .alpha. spectrometry using neodymium fluoride coprecipitation
|
journal | May 1986 |
Determination of americium and curium by using ion-exchange in nitric acid-methanol medium for environmental analysis
|
journal | December 1976 |
Separation of plutonium in urine without sample ashing for determination by .alpha.-spectrometry
|
journal | July 1981 |
Neodymium fluoride mounting for .alpha. spectrometric determination of uranium, plutonium, and americium
|
journal | December 1983 |
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Related Subjects
/436/422/
acid
actinides
americium
anion
anion exchange
ashed
carried
chloride
chloride form
determination
determining
disclosed
dissolution
dissolved
exchange
exchange resin
fecal
form
furnace
including
material
method
muffle
oxidation
passing
plutonium
precipitation
radioactivity
reduction
resin
sample
sample material
samples
separation
series
solution
specific
step
steps
treated
unique
uranium
urine
acid
actinides
americium
anion
anion exchange
ashed
carried
chloride
chloride form
determination
determining
disclosed
dissolution
dissolved
exchange
exchange resin
fecal
form
furnace
including
material
method
muffle
oxidation
passing
plutonium
precipitation
radioactivity
reduction
resin
sample
sample material
samples
separation
series
solution
specific
step
steps
treated
unique
uranium
urine