NERC-LV-539-9
RESULTS OF SAMPLING NATURAL GAS WELLS IN THE
VICINITY OF PROJECT GASBUGGY
by
Technical Support Section
^Environmental Surveillance
National Environmental Research Center
U. S. ENVIRONMENTAL PROTECTION AGENCY
Las Vegas, Nevada
'?! S*f Published February 1973
'i l'j* * f
,,/ - *
This surveillance performed under a Memorandum of
Understanding No. AT(26-1)-539
for the
U. S. ATOMIC ENERGY COMMISSION
-------
This report was prepared as an account of work sponsored by the
United States Government. Neither the United States nor the United
States Atomic Energy Commission, nor any of their employees, nor
any of their contractors, subcontractors, or their employees,
makes any warranty, express or implied, or assumes any legal lia-
bility or responsibility for the accuracy, completeness or useful-
ness or any information, apparatus, product or process disclosed,
or represents that its use would not infringe privately-owned
rights.
Available from the National Technical Information Service,
U. S. Department of Commerce,
Springfield, VA. 22151
Price: paper copy $3.00; microfiche $.95.
ou.
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NERC-LV-539-9
RESULTS OF SAMPLING NATURAL GAS WELLS IN THE
VICINITY OF PROJECT GASBUGGY
by
Technical Support Section
Environmental Surveillance
National Environmental Research Center
U. S. ENVIRONMENTAL PROTECTION AGENCY
Las Vegas, Nevada
Published February 1973
This surveillance performed under a Memorandum of
Understanding No. AT(26-l)-539
for the
U. S. ATOMIC ENERGY COMMISSION
-------
ABSTRACT
Project Gasbuggy was the first experiment to investigate the feasibility of
using a nuclear explosion to stimulate production of natural gas from a
gas bearing formation. The detonation occurred on December 10, 1967> ami on
October 30 and 31, 1969, production from 28 gas wells located within five
miles of Gasbuggy surface ground zero was resumed. Radiological sampling
of natural gas was established on Trunk L and Lateral L-7 since these
collection lines represented gas from all 28 wells. Natural gas samples
were taken once every three to four weeks from November 5, 1969> to
November 10, 1970.
Samples were analyzed for radon-222, tritium, carbon-14, radiokryptons, and
radioxenons. The samples were collected through particulate filters which
were counted for gross alpha and gross beta activity and analyzed by gamma
spectroscopy. The gas was collected in high pressure bottles for gas
analysis. Only naturally occurring radon-222 was detected in the gas at
concentrations from 12 to 59 pCi/1.
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TABLE OF CONTENTS
ABSTRACT
LIST OF FIGURES iii
LIST OF TABLES iv
INTRODUCTION i
SURVEILLANCE PROGRAM 2
EQUIPMENT AND PROCEDURES 3
SAMPLE ANALYSIS 4
RESULTS 5
SUMMARY 5
REFERENCES 12
APPENDICES 13
ii
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LIST OF FIGURES
Figure Page
1. Gasbuggy Area Map 6
2. Trunk L Sampling Location 7
3. Lateral L-7 Sampling Location 8
4. Sampling Equipment 9
iii
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LIST OF TABLES
Table Page
1. Table 1 - Natural Gas Sampling Results 10
2. Table 2 - Pressure Filter Sampling Results 11
iv
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INTRODUCTION
Project Gasbuggy was conducted to study the feasibility of natural gas
production stimulation by fracturing a gas producing formation with nuclear
explosives. The detonation was executed near Farmington, New Mexico, on
December 10, 1967.
Operating under a Memorandum of Understanding with the Atomic Energy
Commission, the National Environmental Research Center-Las Vegas (NERC-LV)*
conducted a program of natural gas sampling to document levels of radio-
activity in gas produced within 3 miles of the Gasbuggy surface ground
zero (SGZ). Previous surveillance by NERC-LV for Project Gasbuggy included
environmental surveillance for the Gasbuggy detonation , the Gasbuggy
2 3
Emplacement Re-entry (GB-ER) , the GB-2R Re-entry Phase I , and the
4
Production Test Phase . Gas flow from the wells within 5 miles of Gasbuggy
SGZ began October 30, 1969. The sampling program covered in this report
began November 5, 1969, and ended November 10, 1970.
*Formerly the Southwestern Radiological Health Laboratory of the Public
Health Service .
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.SURVEILLANCE PROGRAM
Before Project Gasbuggy was detonated on December 10, 1967, all natural gas
wells within 5 miles of Gasbuggy SGZ (Figure 1) were taken off production.
Trunk L and Lateral L-7, the gas gathering lines for all gas wells within
5 miles of SGZ were cut and capped on December 6, 1967. The wells were
shut down to insure that no radioactivity from the Gasbuggy detonation
entered the commercial natural gas being sent to homes and industry. On
October 30, 1969, production from 27 of the 28 gas wells located within
five miles of SGZ was resumed. On October 31 production was resumed on
the 28th well.
Sampling of gas from these wells began on November 5, 1969. This program
involved taking natural gas samples from both Trunk L (Figure 2) and
Lateral L-7 (Figure 3). Samples were analyzed for radon-222, tritium,
carbon-14, radioxenons, and radiokryptons. During collection the gas
was passed through particulate filters which were counted for gross alpha,
gross beta, and gamma activity.
In order to meet the objective that the natural gas not flow longer than
30 days between the collection of one sample and the reporting of the
next sample analysis to the El Paso Natural Gas Company, samples were
originally collected every three weeks. This time period was extended to
33 or 34 days so that fewer sampling missions would be necessary. The
sampling frequency was changed to every four weeks on February 3, 1970.
To eliminate the need for taking natural gas samples periodically, a
natural gas burner was developed by NERC-LV as a simple and inexpensive
monitor for radioactivity in natural gas. During October 1970, this burner
system was installed at Trunk L. The burner system consists of a combustion
chamber with a condensation column exhaust and a few necessary control
units. The indicator of residual radioactivity in the natural gas is
tritium. A liquid scintillation analysis is made on the condensate water
2
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and the tritium concentration in the natural gas is determined. The major
disadvantage of this system at the present is that a sample of the
condensate has to be collected and shipped to NERC-LV for analysis. Con-
currently, a project is underway at NERC-LV to develop and test a tritium
detection and printout system to complete the tritium monitor. This system
could be secured at the site and utilized to provide continuous data on
the natural gas at any given location .
EQUIPMENT AND PROCEDURES
Four-liter oxygen cylinders were connected by a quick-disconnent coupling
to a sample manifold, including a pressure gauge and pressure filter
holder (Millipore No. XX45 04700) containing a 47-mn-diameter Acropor
membrane filter of 0.45 ym pore size manufactured by Gelman Instrument Co.
The six sampling cylinders used for each collection were evacuated in the
laboratory before each sampling mission. The Acropor filters were placed
in their holders at the laboratory and were not removed until they were
returned to the laboratory. Three gas samples were taken at each location
using the same filter for all three samples at one location.
To collect a sample, the sample manifold, including the pressure filter
holder, was connected to the trunk line (Figure 4). The manifold was purged
by venting to the atmosphere and was then connected to the sampling cylinder.
The cylinder was filled with gas and the pressure was recorded. Then the
cylinder was emptied and the resulting pressure was recorded. This pro-
cedure was repeated seven times to flush the cylinder and ensure that a
representative sample was obtained. After filling the cylinder for the
eighth time, all valves were closed and the cylinder was disconnected from
the manifold. The entire procedure was repeated for each gas sample taken.
The total volume of gas passed through the filter was determined from the
cylinder volume and the pressure readings made at each flushing.
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During each sampling, a photograph was taken showing the assembled apparatus
with the cylinder number, date, and pipe line designation plainly visible
(Figure 2). At each location a psychrometer was used to obtain a wet bulb
and a dry bulb temperature reading. All data collected were put on an
individual data sheet (Appendix A) for each sample. These data included
date and time of collection, location, names of collectors, cylinder number,
wet and dry bulb temperatures, gas temperature if available, barometric
pressure, meteorological conditions, and cylinder pressures filled and empty.
SAMPLE ANALYSIS
All samples were returned to Las Vegas by EPA aircraft for laboratory
analysis. Radon analysis was performed by transferring a portion of the
gas sample to a Lucas alpha scintillation counting cell for alpha counting
of radon and its daughters . Thirty-minute counts were made every half hour
until a maximum count rate was achieved. Based on a 30-minute count and a
sample volume of 125 ml, the minimum detectable concentration (MDC) for
radon was 0.04 pCi/1. All MDC's are based on a 3o counting error..
The other radionuclides were separated from each other by combusting the
natural gas. The water of combustion was separated by freezing and all
gases were adsorbed on charcoal at liquid nitrogen temperatures and separated
from each other by a series of low temperature chromatographic steps. Samples
were analyzed for tritium and carbon-14 by liquid scintillation spectrometry.
Based on a 100-minute count and an approximate 4-liter sample of gas, the
MDC's for tritium and carbon-14 were 1 pCi/1 and 20 pCi/1, respectively.
Samples ware analyzed for xenon and krypton by beta counting in a glass
envelope Geiger counter. Based on a 30-minute count and an approximate
12-liter sample of gas, the MDC for both xenon and krypton was 100 pCi/total
-, 7,8
sample
The filters were counted for gross alpha and gross beta using a Beckman
Wide Beta counter. Based on a 10-minute count, the MDC's for gross alpha
-------
and gross beta were 1 pCi/total filter and 2 pCi/total filter, respectively.
A gamma scan was performed on the filters using a gamma spectrometer.
Based on a 10-minute count, the MDC for a single isotope was 50 pCi/total
filter7.
Sample results were recorded on a Natural Gas Sample Report Form (Appendix
B). To expedite reporting, the written report was hand-carried to the
Atomic Energy Commission, Nevada Operations Office, who reported the
results to El Paso Natural Gas Company by telephone and mail.
RESULTS
Natural gas sampling results are given in Table 1 and filter sampling
results are found in Table 2. Only naturally occurring radon-222 was
found in any of the samples from either Trunk L or Lateral L-7. Baseline
levels of radon-222 in natural gas in northwestern New Mexico (0.2 to
Q
158.8 pCi/1) were established before Project Gasbuggy. The levels in
the wells sampled after the detonation remained the same following Project
Gasbuggy as seen from the results. No tritium, carbon-14, radiokryptons,
or radioxenons were detected.
SUMMARY
Natural gas samples from Trunk L and Lateral L-7, serving all 28 producing
gas wells within 5 miles of Project Gasbuggy, were analyzed for tritium,
carbon-14, radon-222, radiokryptons, and radioxenons. Only naturally
occurring radon-222 was detected. Levels varied from 12 pCi/1 to
59 pCi/1 or about the same as before Project Gasbuggy. Particulate filter
results showed no gross radioactivity levels above background for specific
radionuclides.
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GRAND JUNCTION
PAGOSA
SPRINGS
DURANGO
/
COLORADO
NEW MEXICO
50 MILES
100 MILES
H
Figure 1. Gasbuggy area map.
6
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Figure 2. Trunk L Sampling Location.
7
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• '-;'V"
Figure 3. Lateral L-7 Sampling Location.
8
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Figure 4. Sampling Equipment.
9
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TABLE 1. NATURAL GAS SAMPLING RESULTS
(Concentrations (pCi/1))1
Sampling Date
November 5, 1969
November 13, 1969
December 2, 1969
December 22, 1969
January 13, 1970
February 3, 1970
March 3, 1970
March 31, 1970
April 28, 1970
May 25, 1970
June 23, 1970
July 21, 1970
August 17, 1970
September 15, 1970
October 13, 1970
November 10, 1970
222Rn
282
313
31
21
35
22
34
19
35
31
34
22
38
19
42
21
45
21
34
20
14
20
34
18
42
35
59
31
38
35
21
12
i^c
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
3H
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Kr
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Xe
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Extrapolated to time of collection
2Trunk L Results
3Lateral L-7 Results
ND - Not detectable
10
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TABLE 2. FILTER SAMPLING RESULTS
Sampling Date
November 5, 1969
November 13, 1969
December 2, 1969
December 22, 1969
January 13, 1970
February 3, 1970
March 3, 1970
March 31, 1970
April 28, 1970
May 25, 1970
June 23, 1970
July 21, 1970
August 17, 1970
September 15, 1970
October 13, 1970
November 10, 1970
Volume
(Liters)
18001
20002
1560
1600
3200
3600
2860
3050
3125
2730
1720
2160
2880
3150
2800
3100
3000
3200
3400
3600
2900
3100
2800
3000
3300
3700
2900
3000
3200
3300
3100
3300
Gross
Alpha
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Gross
Beta
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Gamma
Scan
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
GSN
xTrunk L Results
2Lateral L-7 Results
ND - Not detectable
GSN - Gamma Spectrum negligible
11
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REFERENCES
1. Re.poit o{j 0^-Site. SuSLViiiltance. £01 Pn.oj2.ct Gatbuggy, ttanck 1967 -
Jane. 1968. SWRHL-99r. Southwestern Radiological Health Laboratory.
February 1970.
2. Hill, Dixon H. and John R. McBride. 0^-Site. Radiological
lance. PJiogiam ^Ofi. PtojlLCt Ga&buggy. Radiological Health Data and
Reports, Vol. 10, No. 12, pp 535-546, December 1969.
3. PA.ojc.ct Gasbuggy 0^-Site. Radiological Safety Re.poit, G8-2R Pha&e. 1
Pnoatiam. SWRHL-105r. Southwestern Radiological Health Laboratory.
November 1968.
4. EnviSionme.ntal SuAveiMance. ^on. Pfioje.c£ Ga&bu.ggy, Production Tut Phote..
SWRHL-lOOr. Southwestern Radiological Health Laboratory. June 1970.
5. The. NERC-LV BusineA. - A Monitoi fan. Radioactivity in Natural Go6.
NERC-LV-539-7. National Environmental Research Center-Las Vegas, Feb. 1973.
6. Handbook o& Radio ch&mical Analytical Method*,. SWRHL-11. Southwestern
Radiological Health Laboratory. March 1970.
7. Analytical Capabilities ofi the SouthuieAteAn Radiological Health Labo-
October 1969. Unpublished report.
8. Gait Analyt>it> Capabilities o& the. Southwute.in Radiological He.alth
LabofiOtoiy. SWRHL-91. Southwestern Radiological Health Laboratory.
April 1970.
9. Bunce, Louis A. and Frank W. Sattler. Radon-222 in Natural Go6.
Radiological Health Data and Reports, Vol. 7, No. 8, pp 441-444.
August 1966.
12
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APPENDICES
APPENDIX Page
A. NATURAL GAS SAMPLE DATA SHEET 14
B. NATURAL GAS SAMPLE REPORT FORM 15
13
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NATURAL GAS SAMPLE
CHECK LIST
1. Connect Filter
2. Purge Sample Line
3. Connect Sample Line (quick disconnect)
4. Photograph Sampling System
5. a. Fill Cylinder (1st time)
b. Record pressure of filled cylinder
c. Empty cylinder
d. Record pressure of emptied cylinder
6. Repeat Step 5a-d (2nd time)
7. Repeat Step 5a-d (3rd time)
8. Repeat Step 5a-d (4th time)
9. Repeat Step 5a-d (5th time)
10. Repeat Step 5a-d (6th time)
11. Repeat Step 5a-d (7th time)
12. a. Fill cylinder (8th time)
b. Record pressure of filled cylinder
13. Close all valves
14. Disconnect Sample Line
15. Disconnect Filter System from Cylinder
16. Complete Sampling tag and attach to Filter
System
17. Complete Sampling tag and attach to Cylinder
w
o
M
a ss
w tu
rt rt
P> c
1-1
CO fa
TO O
rt (tt
U>
DATE OF COLLECTION:,
TIME OF COLLECTION:,
LOCATION
COLLECTED BY (PHS) :_
(EPNG) :_
REMARKS:
COLLECTION DATA
CYLINDER NO.:
TEMPERATURE-DRY BULD:_
WET BULB:"
GAS TEMP. IF AVAILABLE,
BAROMETRIC PRESSURE:
METEOROLOGICAL CONDITIONS:
NO. OF CYLINDER CYLINDER
TIMES FILLED EMPTY
CYLINDER PRESSURE PRESSURE
FILLED
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APPENDIX B
Natural Gas Sample
Report Form
NATURAL GAS SAMPLE REPORT
COLLECTION INFORMATION
DATE OF REPORT:
DATE OF COLLECTION:_
TIME OF COLLECTION:_
DATE OF ANALYSIS:
LOCATION:
FILTER LAB NO. :
COLLECTED BY (PHS) :_
(EPNG) :_
SAMPLE PRESSURE:
CYLINDER NO.:
CYLINDER LAB NO.:
ANALYTICAL RESULTS
AS COUNTED
(dpm)
1
CONCENTRATION
(At collection
time, pCi/1)
Gas Analysis
Radon-222 activity
Carbon-14 activity
Tritium activity
Krypton activity
Xenon activity
Pressure Filter Analysis
Volume of Gas Sampled through Filter
Gross Alpha
Gross Beta
Gamma Scan
DETECTABLE LIMITS OF ANALYTICAL METHODS
Gas Analysis
Radon-222 0.1 pCi/total portion counted2
Carbon-14 0.111 pCi/m. C02 @ STP3
Tritium 0.4 pCi/ml of water collected3
Krypton 100 pCi/total portion counted1*
Pressure Filter Analysis5
Gross Alpha 1 pCi/total filter
Gross Beta 2 pCi/total filter
Gamma Scan 50 pCi/total filter
1Variance is based on counting error only (2a).
2Portion varies, but not less than 100 ml @ STP.
3This value is the result of CH, combustion.
^Portion varies, but not less than 15 liters.
5Based on 10 minute counting time.
15
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DISTRIBUTION
1-15 National Environmental Research Center, Las Vegas, Nevada
16 Mahlon E. Gates, Manager, NVOO/AEC, Las Vegas, Nevada
17 Robert H. Thalgott, NVOO/AEC, Las Vegas, Nevada
18 Henry G. Vermillion, NVOO/AEC, Las Vegas, Nevada
19 Chief, NOB/DNA, NVOO/AEC, Las Vegas, Nevada
20 Robert R. Loux, NVOO/AEC, Las Vegas, Nevada
21 Donald W. Hendricks, NVOO/AEC, Las Vegas, Nevada
22 R. M. Pastore, NVOO/AEC, Las Vegas, Nevada
23 Technical Library, NVOO/AEC, Las Vegas, Nevada
24 Mail & Records, NVOO/AEC, Las Vegas, Nevada
25 Martin B. Biles, DOS, USAEC, Washington, D. C.
26 Director, DAT, USAEC, Washington, D. C.
27 Harold F. Mueller, ARL/NOAA, NVOO/AEC, Las Vegas, Nevada
28 Gilbert J. Ferber, ARL/NOAA, Silver Spring, Maryland
29 Stanley M. Greenfield, Assistant Administrator for Research & Monitoring,
EPA, Washington, D. C.
30 William D. Rowe, Deputy Assistant Administrator for Radiation Programs,
EPA, Rockville, Maryland
31 Dr. William A. Mills, Dir., Div. of Criteria & Standards, Office of
Radiation Programs, EPA, Rockville, Maryland
32 Ernest D. Harward, Acting Director, Div. of Technology Assessment,
Office of Radiation Programs, EPA, Rockville, Maryland
33 Bernd Kahn, Chief, Radiochemistry & Nuclear Engineering, NERC, EPA,
Cincinnati, Ohio
34 - 35 Charles L. Weaver, Director, Field Operations Division, Office of
Radiation Programs, EPA, Rockville, Maryland
36 Gordon Everett, Director, Office of Technical Analysis, EPA,
Washington, D. C.
37 Kurt L. Feldman, Managing Editor, Radiation Data & Reports, ORP, EPA,
Rockville, Maryland
38 Regional Administrator, EPA, Region IX, San Francisco, California
39 Regional Radiation Representative, EPA, Region IX, San Francisco, California
40 Eastern Environmental Radiation Laboratory, EPA, Montgomery, Alabama
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DISTRIBUTION (continued)
41 Library, EPA, Washington, D. C.
42 William C. King, LLL, Mercury, Nevada
43 James E. Carothers, LLL, Livermore, California
44 Joseph Tinney, Hazards Control, LLL, Livermore, California
45 Charles I. Browne, LASL, Los Alamos, New Mexico
46 Harry S. Jordan, LASL, Los Alamos, New Mexico
47 Arden E. Bicker, REECo, Mercury, Nevada
48 Savino W. Cavender, REECo, Mercury, Nevada
49 Carter D. Broyles, Sandia Laboratories, Albuquerque, New Mexico
50 Robert H. Wilson, University of Rochester, Rochester, New York
51 Richard S. Davidson, Battelle Memorial Institute, Columbus, Ohio
52 J. P. Corley, Battelle Memorial Institute, Richland, Washington
53 P. L. Randolph, EPNG, El Paso, Texas
54 G. W. Frank, Austral Oil Co., Inc., Houston, Texas
55 G. R. Luetkehans, CER Geonuclear, Las Vegas, Nevada
56 A. E. Doles, EIC, Santa Fe, New Mexico
57 Frank E. Abbott, USAEC, Golden, Colorado
58 John M. Ward, President, Desert Research Institute, University of Nevada,
Reno, Nevada
59 - 60 Technical Information Center, Oak Ridge, Tennessee (for public availability)
61 Dr. Edward H. Fleming, Div. of Applied Technology, USAEC, Washington, D.C.
62 M. M. Williamson, Div. of Applied Technology, USAEC, Washington, D. C.
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