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Title: MOUND LABORATORY PROGRESS REPORT FOR JULY 1963

Abstract

8 7 6 2 ; 7 4 7 6 : 7 8 : : ; half life of 3.781 plus or minus 0.010 years based on calorimetric measuiements. The calorimetric assay of the sample will be continued ior several years to decrease the probable error. The decay scheme for /sup 209/Po--/sup 209/Po/ isitopic mixtures is being determined. The gamma spectrum is being studied using two sources of different isotopic composition. Definite peaks were established at 76, 260, 300, 575, and 9l0 kev. Various multiple coincidence experiments indicated that the 300- and 575-kev photons and the 76-kev x-ray are in triple coincidence. Relative intensities of the various gamma rays from the two different sources indicated that the 575-kev photon is associated with /sup 208/ Po decay, while the 260- and 910-kev states are attributed to /sup 209/Po. A theoretical estimate of the partial alpha half life for /sup 208/Po decay to the 2+ level in /sup 204/Pb (at 0.899 Mev) was made. This value (2.5 x 10/sup 6/ years) was determined graphically by extrapolation to an alpha particle energy of 4.2l1 Mev. /sup 209/Po--/sup 2o9/Po sources are being prepared for the investigation of the internal conversion electron spectra of these isotopes.more » Ion exchange techniques are being studied for the separation of /sup 227/Ac from / sup 227/Th, /sup 223/R a, and /sup 226/Ra. Naturally occurring lanthanum, thorium, and barium are being used as experimental substitutes. Composite elution curves indicated that lanthanum and /sup 232/Th can be successfully isolated with 2 M HCl, 3 M HNO/sub 3/, and ammonium acetate as elutrients. A purified form of the original Dowex 50W-X8 column packing matenial was used; the new material (AG-50W-X8) reduced tailing on the elution curves. /sup 228/Th was tentatively assigned a half life of 1.9132 years with an internal probable error of 0.0005 year. The presence of /sup 210/Po and actinium must be positively identified in the sample by chemical analysis and alpha pulse height analyses. Mound Laboratory is studying the separation and purification of /sup 234/U from aged /sup 238/Pu using ion exchange and solvent extraction techniques. A batch containing an estimated 250 milligrams of /sup 234/U in 26.2 grams of plutonium is being processed. The anion exchange separation procedure for this batch was completed. More than 99% of the plutonium was removed from the uranium. A spectrophotometric method is being developed for the determination of /sup 234/ U in samples containing aluminum, iron, and plutonium. The extraneous metallic ions were separated, and the uranium was complexed with 1-(2-pyridylazo)-2- naphthol (PAN). After the color developed, the absorbance was read at 570 m mu . Standard uranium samples were analyzed, and Beer's law was followed between 0 and 80 mu g of uranium. Gram quantities of over 90% pure /sup 13/C are being prepared. Various thermal diffusion column configurations are being used for separation efficiency studies and evaluation of feed gases, such as carbon monoxide or methane. The first five stages of the seven-stage cascade system of hot-wire and concentrictube columns are enriching natural methane to about 23% / sup 13/C while coming to steady state conditions. The concertric tube columns enriched methane from 60 to over 90% /sup 13/C in the total carbon. About 1.5 grams of product containing about 10% impurities were accumulated. The use of alternating current for heating thermal diffusion column wires is being studied. Vibration of the wire is the major problem. Two parallel iron discs were used to align the electrical leads and the column wire in the pool of mercury; however, the discs did not prevent vibration. The mercury pool was replaced by rubber bands, and subsequently by a spring, for tensioning the wire; there was a slight vibration. A braided cable was used as an electrical lead for alternating current and as a vibration damper. Both the vibration and the use of a mercury pool were eliminated. An integral was set up to determine the error introduced into the calibration of« less

Authors:
; ;
Publication Date:
Research Org.:
Mound Lab., Miamisburg, Ohio
Sponsoring Org.:
USDOE
OSTI Identifier:
4026910
Report Number(s):
MLM-1170
NSA Number:
NSA-18-019466
DOE Contract Number:  
AT(33-1)-GEN-53
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-64
Country of Publication:
United States
Language:
English
Subject:
GENERAL AND MISCELLANEOUS; ABSORPTION; ACETATES; ACTINIUM; ACTINIUM 227; ALPHA DECAY; ALPHA PARTICLES; ALUMINUM; AMMONIUM COMPOUNDS; ANIONS; BARIUM; BEER LAW; BETA DETECTION; BETA PARTICLES; CABLES; CALORIMETERS; CARBON 13; CARBON MONOXIDE; CIRCUITS; COINCIDENCE METHODS; CONFIGURATION; COPPER; COUNTERS; DECAY; DIAGRAMS; DOWEX; EFFICIENCY; ELECTRONS; ENERGY LEVELS; ERRORS; GAMMA RADIATION; GOLD; HALF-LIFE; HEATING; HYDROCHLORIC ACID; INTERNAL CONVERSION; ION EXCHANGE; ION EXCHANGE MATERIALS; IONS; IRON; IRRADIATION; ISOTOPE SEPARATION; KRYPTON 85; LANTHANUM; LEACHING; LEAD 204; LIGHT; MEASURED VALUES; MECHANICAL STRUCTURES; METHANE; MIXING; NAPHTHALENE; NEUTRON SOURCES

Citation Formats

Eichelberger, J.F., Grove, G.R., and Jones, L.V. MOUND LABORATORY PROGRESS REPORT FOR JULY 1963. United States: N. p., 1963. Web. doi:10.2172/4026910.
Eichelberger, J.F., Grove, G.R., & Jones, L.V. MOUND LABORATORY PROGRESS REPORT FOR JULY 1963. United States. doi:10.2172/4026910.
Eichelberger, J.F., Grove, G.R., and Jones, L.V. Tue . "MOUND LABORATORY PROGRESS REPORT FOR JULY 1963". United States. doi:10.2172/4026910. https://www.osti.gov/servlets/purl/4026910.
@article{osti_4026910,
title = {MOUND LABORATORY PROGRESS REPORT FOR JULY 1963},
author = {Eichelberger, J.F. and Grove, G.R. and Jones, L.V.},
abstractNote = {8 7 6 2 ; 7 4 7 6 : 7 8 : : ; half life of 3.781 plus or minus 0.010 years based on calorimetric measuiements. The calorimetric assay of the sample will be continued ior several years to decrease the probable error. The decay scheme for /sup 209/Po--/sup 209/Po/ isitopic mixtures is being determined. The gamma spectrum is being studied using two sources of different isotopic composition. Definite peaks were established at 76, 260, 300, 575, and 9l0 kev. Various multiple coincidence experiments indicated that the 300- and 575-kev photons and the 76-kev x-ray are in triple coincidence. Relative intensities of the various gamma rays from the two different sources indicated that the 575-kev photon is associated with /sup 208/ Po decay, while the 260- and 910-kev states are attributed to /sup 209/Po. A theoretical estimate of the partial alpha half life for /sup 208/Po decay to the 2+ level in /sup 204/Pb (at 0.899 Mev) was made. This value (2.5 x 10/sup 6/ years) was determined graphically by extrapolation to an alpha particle energy of 4.2l1 Mev. /sup 209/Po--/sup 2o9/Po sources are being prepared for the investigation of the internal conversion electron spectra of these isotopes. Ion exchange techniques are being studied for the separation of /sup 227/Ac from / sup 227/Th, /sup 223/R a, and /sup 226/Ra. Naturally occurring lanthanum, thorium, and barium are being used as experimental substitutes. Composite elution curves indicated that lanthanum and /sup 232/Th can be successfully isolated with 2 M HCl, 3 M HNO/sub 3/, and ammonium acetate as elutrients. A purified form of the original Dowex 50W-X8 column packing matenial was used; the new material (AG-50W-X8) reduced tailing on the elution curves. /sup 228/Th was tentatively assigned a half life of 1.9132 years with an internal probable error of 0.0005 year. The presence of /sup 210/Po and actinium must be positively identified in the sample by chemical analysis and alpha pulse height analyses. Mound Laboratory is studying the separation and purification of /sup 234/U from aged /sup 238/Pu using ion exchange and solvent extraction techniques. A batch containing an estimated 250 milligrams of /sup 234/U in 26.2 grams of plutonium is being processed. The anion exchange separation procedure for this batch was completed. More than 99% of the plutonium was removed from the uranium. A spectrophotometric method is being developed for the determination of /sup 234/ U in samples containing aluminum, iron, and plutonium. The extraneous metallic ions were separated, and the uranium was complexed with 1-(2-pyridylazo)-2- naphthol (PAN). After the color developed, the absorbance was read at 570 m mu . Standard uranium samples were analyzed, and Beer's law was followed between 0 and 80 mu g of uranium. Gram quantities of over 90% pure /sup 13/C are being prepared. Various thermal diffusion column configurations are being used for separation efficiency studies and evaluation of feed gases, such as carbon monoxide or methane. The first five stages of the seven-stage cascade system of hot-wire and concentrictube columns are enriching natural methane to about 23% / sup 13/C while coming to steady state conditions. The concertric tube columns enriched methane from 60 to over 90% /sup 13/C in the total carbon. About 1.5 grams of product containing about 10% impurities were accumulated. The use of alternating current for heating thermal diffusion column wires is being studied. Vibration of the wire is the major problem. Two parallel iron discs were used to align the electrical leads and the column wire in the pool of mercury; however, the discs did not prevent vibration. The mercury pool was replaced by rubber bands, and subsequently by a spring, for tensioning the wire; there was a slight vibration. A braided cable was used as an electrical lead for alternating current and as a vibration damper. Both the vibration and the use of a mercury pool were eliminated. An integral was set up to determine the error introduced into the calibration of},
doi = {10.2172/4026910},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jul 30 00:00:00 EDT 1963},
month = {Tue Jul 30 00:00:00 EDT 1963}
}

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