ML20235B955
| ML20235B955 | |
| Person / Time | |
|---|---|
| Site: | 07000539 |
| Issue date: | 07/26/1982 |
| From: | Fritz K CINCINNATI, UNIV. OF, CINCINNATI, OH |
| To: | Holt B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20235B936 | List: |
| References | |
| 06678, 6678, NUDOCS 8902150509 | |
| Download: ML20235B955 (20) | |
Text
_ _ - _ _ - _,
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o UNIVERSITY OF CINCINNATI
- RADIATION SAFETY OFFICE Telephone (513) 872-4115 234 Goodman Street J Pavikon Cincinnati. Ohio. 45267 096 0050 July 26, 1982 4g Ms. B.J. Holt Licensing Section U.S. Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellen, Ill. 60137
Dear Ms. Holt:
Pursant to title 10, Code of Federal Regulation, Part 70, Section 70.22, it is requested that Special Nuclear Material License Number SNM-490 be renewed.
As stated on our present license, the maximum quantity of special nuclear material to be possessed at any one time would be as follows:
Plutonium:
160 grams encapsulated as Pu-Be neutron sources 1 Source of 16 grams 1 Source of 32 grams 1 Source of 48 grams 1 Source of 64 grams Other information as requested in Regulatory Guid'e 10.3 is enclosed Thank you for your consideration of this request.
Sincerely, r.:*?. V..
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(\\%-
D:ta hJ Kenneth M. Fritz g"
Radlation Safety Officer by University of Cincinnati
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Nuclear Regulatory Conmrission 7/26/82 Applicant:
University of Cincinnati Clifton Ave.
Cincinnati, OH 45221 The principal officers of the University are:
President and Executive Vice President Henry R. Winkler, Ph.D.
Home:
363 Lafayette Ave., Cincinnati, OH 45220 Business:
204 Van Wormer Administration Building University of Cincinnati, Cincinnati, OH 45221 Senior Vice President for Administration and Operations Lawrence C. Hawkins, B. A., Ed.D.
Home:
3935 Wess Park Drive, Cincinnati, OH 45217 i
Business:
200 Van Wormer Administration Building University of Cincinnati, Cincinnati, OH 45221 University Dean for Graduate Education and Research Eula Bingham, Ph.D.
Home:
922 Edwards Road, Cincinnati OH 45208 Business: 305 Braunstein Hall University of Cincinnati, Cincinnati, OH 45221 The University of Cincinnati is part of the Ohio State University System and is under the centrol of the Ohio Board of Regents.
The principal Officers of the University are all citizens of the United States.
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. l Activities to be Performed:
The 1, 2, 3, and 4 Ci.
Pu-Be sources are used as neutron sources for experiments performed by students in the Radiation Measurements Laboratory and the Nuclear 1
Reactor Laboratory classes.
All source movements are made by the instructor, who wears a film badge and disposable gloves.
The sources are handled with tongs.
Transfer of the source from a storage container to the device in which it is to be used is accomplished as quickly as possible.
Sources are transported from the storage location to the point of use in a neutron howitzer.
i Foil Activation.
E1ther the one or the two Ci source is used for foil activation.
The source is removed from the storage well and placed in a neutron howitzer. The l
neutron howitzer is a cylinder of parafin 18 inches in diameter and 23 inches high I
with a 1.5 inch diameter hole extending 12 inches deep on the axial center line.
The class makes gamma and neutron surveys at the top of the container and at the sides of the container before proceeding with the experiment. Foil activation experiments are performed in room 504A, Old Chemistry Building.
(cf. enclosed drawing).
Neutron Source for Subcritical Reactor.
(License No. SUD-265).
Either the 3 or 4 Ci source is used as a neutron source in the suberitical reactor. The source, which is placed in the center of the suberitical reactor, is only in the reactor during the time the facility is in use by a class.
At all other times, it is in the locked storage vault. The class performs a neutron and gamma survey prior to working around the suberitical reactor.
The suberitical reactor is located in room 412, Old Chemistry Building. (cf. enclosed drawing).
heutron Source for the Graphite Sigma Pile.
Either the 3 or 4 Ci source is used I
as a neutron source in the graphite pile for diffusion length and Fermi age measurements. The source is placed 14 inches below the center of a graphite pile
-l 80 inches high, by 67 inches deep, by 67. inches wide. The class performs a neutron and gamma survey prior to working around the pile. The source is in the graphite pile only during the time the facility is in use by a class. At all other times, it is 'in the locked storage vault.
The graphite sigma pile is located in room 412, Old Chemistry Building. (cf. enclosed drawing).
Specifications of Special Nuclear Material Plutonium 239 as Pu-Be scaled sources. 4 sealed sources, 1, 2, 3 and 4 Ci each.
1 Curie source - Mound Laboratory, number M1162,16 grams Pu239.
2 Curie source - Mound Laboratory, number M1150, 32 grams Pu239.
3 Curie source - Mound Laboratory, number M1151, 48 grams Pu239.
4 Curie source - Mound Laboratory, number M1163, 64 grams Pu239.
l Total weight as Pu-Be sources: 160 grams.
Total activity as Pu-Be sources: 10 curies.
Description of Facilities and Equipment:
1.
Handling Tocls No.
Length
- Tyye, 1
12 ft Dual Grip 1
6 ft Dual Grip 2
2ft Niptongs 1
5ft Hook Pole j
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2.
Survey Instruments Radiation Window No._
Manufacturer Model.
Detected Range Thickness 2
Eberline E-120 0-50 mR/hr 30 mg/cm 10 1
Eberline PNC-1 N
0-500,000 cpm B F3 1
Eberline PNR-4 N
0-5,000 mR/hr B F3 A
0-2,000,000 cpm 1.5 mg/cm 1
Eberline PAC-4S 1
Victoreen.
740-G 0-100,000 mR/hr
.00025 mylar 3.
Calibration: Conducted by Howard Boeing, Laboratory Associate The PNC-1 neutron survey meter is calibrated by using the 1, 2, 3 and 4 curie Pu-Be sources and a portable parafin filled howitzer. The neutron sources are placed in the howitzer and the detector head is placed at various distances from the source. Data is then compiled in each of the instrument ranges and compared with data taken when the instrument was first received with a certified calibration.
The PNR-4 is calibrated the same way as the PNC-1 except parafin bricks are used instead of the howitzer.
Calibration procedures for the X and(3-instruments. are enclosed. They are calibrated twice a year by_the Radiation Safety Office.
4.
Storage:
1 The Pu-Be sources are stored in room 415B of the Old Chemistry Building (see attached drawing). The Pu-Be sources are kept in a watertight aluminum tube near the bottom of a 12 foot deep water filled well. Room 415B is kept at negative air pressure and contains a glove box with absolute filter and a disposal sink.
Security of the materials is maintained by a locked. gate inside the _ room and the entrance door is a steel fire door which is locked at all times. -Keys to this door i
are issued only to staff and faculty who have had adequate radiation safety training and have approval of the Laboratory Director and the Laboratory Manager. The Univer--
sity Police and the Cincinnati Fire Department also have one key each. The sources are further protected by 3 more steel fire doors. Keys to these doors are restricted to faculty, staf f members and graduate students who have approval of the Laboratory Director or Laboratory Manager and their Faculty Advisor.
Personnel Monitoring:
Personnel monitoring'is conducted using the R. S. Landauer film badge service pur-suant to Section 20.202 of 10CFR20. The films measure beta,' gamma and neutrons and are exchanged on a monthly basis.
Surveys:
The following surveys have been recently made for the uses of these sealed sources described previously :
Foil Activation with 1 curie Pu-Be source:
Location-Y (mR/hr) n(mR/hr)
Total (mR/hr)
Top of howitzer 0.6 1.0 1.6 (contact)
Side of howitzer 1.6 1.5 3.1 (contact) 3 feet from side 0.1 0.5 0.6
' Control Mo. 06678 i
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Students are kept out of immediate area (p 10 feet away) which is roped.of f, except when they are near the howitzer during their experiment.
They.are-closer than 10 feet for about 10 minutes per year and receive < 1 millirem'per year exposure from this experiment.
r Neutron Source for Suberitical Reactor using 4 Ci Pu-Be source mR mR '
y mR Location J hr n
'hr Total hr Top of reactor 1.9
. 1.1 3.0
~
(contact)
Side of reactor 1.2 0.7 1.9 l
(contact) 3 feet away 0.1 0.1 0.2 Students spend about 30 minutes per year about 2 feet from top,' receiving (1 milli-rem exposure.
Neutron Source for-the Graphite Sigma Pile I
uning 4 Ci source l
y mR mR mR l
1,ocation u hr n hr Total hr Face of pile 0.42 0.9.
1.32 l
6 feet away 0.10 0.3 0.4 12 feet away
( 0.1 0.1 -
0.2 Students are near face of pile for about 5 minute's and' receive less than 1 m1111 rem.,
Alpha Survey Meter Calibration Procedure:
The calibration source used is an Eberline Instrument Corporation Plutonium Alpha
~'
Calibration set S94-1, S94-2 and S94-3 and S94-4.
1.
Place the detector over the appropriate source for calibrating the X1 scale.
1 Record the CPM reading then rotate the detector 180* and record'the reading.
j in this position.
2.
If the average CPM obtained -in Step 1 does not agree with the certified value.
of the source, adjust't,he calibration control for the X1 range (inside the -
instrument case) so that the average reading obtained does agree with the certi-fled value.
3.
Repeat Step 1 and 2 for each range of the instrument.
4.
If the SAP-1 attenuator is used, the certified value of the source must be multi-plied'by 0.38,to obtain the actual 2PI emission rate.
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5.
Calibrations are perfonned by Carla Chifos
, Deputy R'adiation Safety' Officer or I. Lee Ashcraf t, Environmental Technician.
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G-M Survey Meter Calibration Procedure-h 1.
All G-M survey meters are calibrated at lea'st onc'e every six months and are always calibrated immediately'following repair or battery replacement.
Calibration is accomplished by taking-readings at various points O
2.. --from the calibration source and adjusting the meter readings to within ~
The points.
i 10% of the calculated exposure rates fon those points.
are chosen so that two readings,.which are separated by at least-50% of'the scale, are taken in each scale.
3.
The calibration source used is a 1 mg Ra. needle. manufactured by the Radium Chemical Company, Inc. Filtration is.0.5 mm Pt equivalent and the calibration of the. source activity is traceable to NBS.
standards.
4.
All calibrations are done by Carla Marie Chifos, Deputy Radiation:
U Safety Of ficer, and I. Lee Asl5craf t, Environmental I
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Technician.
Film badges are worn.
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lon Chamber Survey Meter (Cutie Pie) Cal'ibration ' Procedure i
1, All Cutie Pies are. calibrated at'least'once every six months'and are always calibrated immediately following repair or battery re-q placement.
i-Calibration is accomplished by taking readings at(various points 2.
from the calibration source and adjusting the meter readingo to.
F within + 10% of the calculated exposure rates for those points.
p The points are chosen so
- hat two readings, which are separated by at least 50% of the scale, are taken 'iro each scale.
The calibration' source used is an EON Corporation Gamma Survey
- 3. - Instrument Calibrator', Model 64-764, Serial number-123, marketed by Nuclear Associates, Inc.
The calibrator' contains approximately 60 mci:
+
.the, design and. manufacture meet NRC requirements.
4.
All ' calibrations are done by Carla Marie Chifos,. Deputy Radiation Safety 0f ficer, and Irvin Lee Ashcraf t, Environmental Technician.
Film badges and pocket dosimeters are worn.
Personnel doing the calibration avoid entering the direct beam while the source is in the exposed position.
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__ II Alpha-Emitting Sealed Source Leak Test Procedure 1.
The test sample is obtained by wiping the source with a moistened filter disc, which has been marked to indicate which side has actually wiped the While it is wiping the source and af terwards, the. disc is held with source.
forceps, or other appropriate remote handling device.
2.
The disc is glued, marked side up, onto a one inch aluminum planchet.
3.
Counting is done with an Eberline FC-1 gas flow proportional counter 2 thin window, and an utilizing instrument grade P-10 gas, a 0.1 mg/cm Eberline MS-2 spectroscaler. The window is sufficiently thin to minimize
' losses by absorption.
4.
The counting procedure and calculations are as follows :
A.
Count a blank planchet for 50 minutes. Divide the total counts by 50 to determine the background cpm.
B.
Count the known C/sstandard for 5 minutes and divide the gross counts by 5 to determine the gross-standard cpm.
Subtract the background cpm to determine the net standard cpm.
C.
Divide the net standard cpm by the standard dpm to determine the j
standard counting efficiency.
The standard dpm are corrected for decay whenever the standard is counted.
Efficiency is typically rul6%.
D.
Determine the Minimum Detectable Activity by the following expression:
Background cpm 3
MDA (uC1) = 3[
50 min eff (com) 6M 2.22x10 (dpm)
(dpm) 6 The MDA is typically -- 6.0x10 uC1, significantly less than 0.005 uCi.
E.
Count the test sample for 10 minutes, determining the sample net cpm as noted above.
F.
Determine the sample activity in microcurien by the following expression:
Sample activity (uCi) = Net sample cpm ef f (cpm _)
0b" 2.22 x 10 (dpm)
(uci) 5.
If the test reveals the presence of 0.005 microcurie or more of removable alpha contamination, it shall be immediately withdrawn from use and shall be decontaminated and repaired by a person appropriately licensed to make such repairs or it shall be disposed of in accordance with Commission regulations.
A report shall be filed within 5 days of the test with the Materials Branch, Directorate of Licensing, USNRC, Washington, D.C. 20545, describing the source, the test results, the extent.of con-tamination, the apparent or suspected cause of source failure, and the corrective action taken.
A copy of the report shall be sent to the Director, USNRC, Region III, Directorate of Regulatory Operations, 799 Roosevelt Road, Glen Ellyn, Illinois 60137.
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O O
EMERGENCY PR0CEDURES If any unusual occurrence arises in which there may be a possibility of a radiation hazard condition, the following procedures must be instituted IMMEDIATELY.
1.
Personnel access to the affected area shall be restricted immediately.
2.
The University Radiation Safety Officer or his deputy will be notified immediately:
Radiation Safety Officer Mr. Ken Fritz Radioisotope Laboratory, Medical Center Telephone: 872-4115 Home Phone:825-9110 l
3.
The Director of the Nuclear Research Laboratory shall next be notified immediately:
' Laboratory Director Dr. J. N. Anno 509 Old Chemistry Telephone:
475-3544 Home Phone: 231-1477 4.
The Laboratory Associate will be notified immediately:
Laboratory Associate H. Boeing 507' 01d Chemistry Telephone:
475-6311 Home Phone: 941-7766 5.
Jh) further action except for the con'tinued exclusion of personnel will be taken until the Radiation Safety Officer, his Deputy, or the Laboratory 1
Director arrives.
6.
Upon their arrival, an exploration shall be undertaken by the Radiation Safety Of ficer or other competent persons he may designate using appropriate 4
survey instruments to determine the extent of the radiation hazard, if any.
7.
Notices shall be posted indicating the radiation levels in the affected areas.
Results of the radiation survey will be recorded (giving levels and areas.in-volved).
8.
in the event that appropriate tests indicate that radioactive material has come in contact with an individual or his clothing, the individual must remove the aff.ted items of clothing. These will be retained in the restricted area.
Ex-posed skin will be washed and cleaned appropriately until examination with sur-vey instruments indicates successful decontamination.. Affected persons shall
.not leave the vicinity of the Laboratory until approved by the Radiation Safety il Officer and his designated representative.
Subsequent steps in decontamination and evaluation relating to the unusual oc-9.
currence will be performed under the direction of the Radiation Safety officer.
- 10. Consult the University of Cincinnati Radiation Safety Manual for further details.
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a. c '31'3,'Suppi,cmental Shcet:
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EC -
ItADI ATIO'N SAFETY OFFICER Mr.. K3nneth M. Fritz Durntion of On the Formal Typs off Training Whero Trained Training Job-Course-2 Xavior University 1 year' No Yes University of, Cincinnati 3 years Yes No
- b National Lead Company of Ohio G years Yes No Xavior University 1 ycar No Yes National Lead Company of' Ohio 0 years Yes.
No c
University of Cincinnati 3 years Yes Yes d
Xavier Universi,ty 1 year No.
Yes University of Cincinnati 3 years Yos No Exp3rience with Radiation:
Duration of Maximum Isotope Amount.
Where Experience was Gained-Experience Type of Use Co 50 Ci National Lead Company G years '
Development U
1 Ci National Lead Company 6 years
. Development.
11 3.5 Ci National Lead Company G years Development 3
Atcmic 2 Ci University of Cincinnati
.5 years-Research A Development No. 4-83,
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\\s AEC - 313, Supplemental Shcot floward 11. Docing II Laboratory Associate, Nuclear Laboratory of Basic & Applied Nuclear Research Univsrsity of Cincinnati
. Duration of On the Formal Tyle of Training Job Course Where Trained Training 5 years yes no General Electric (talpO) a l
5 years yes yes University of Cincinnati b
Same as a 5 years yes no University of Cincinnati c
d same as a Experience with Radiation Duration of Where Experience was Gained Experience Type of Use Isotope Maximum Amount Instructional University of Cincinnati 5 years Atomic No, 1 mci 4-83 R&D 0.1 Ci Co Instructional 4 Ci Po 239 R&D Cf 232
'10 mci General Electric (NMpO) 5 years R &.D
- 1 U 228 R&D l
- 1 U 235 R & D, 1
- 1 Th 233
- 1sotope's in the form of Oxides & metals, processed in ton quantitics.
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f AEC - 313, Supplemental Sheet Mr. K:nneth M. Emmerich Research Associate and Manager, Laboratory of Basic and Applied Nuclear Research Typ3 of Duration of On the Formal Training Where Trained Training Job C,ourse a
University of Cincinnati 4 years yes no b
General Electric Company 1 year yes no University of Cincinnati 4 years yes no c
University of Cincinnati 4 years yes no d
Same as c Exp3rience with radiation:
.I' Duration of Icotope Maximum Amount Where Experience was Gained Experience Type of Uso Fission 10 C1 General Electric Company 1 year R&D Products Atomic No.
2 mC1 University of Cincinnati 4 years Instructional 4-83 9
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f' L AEC - 313, Supplemental Sheet
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Phincipal User
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James N. Anno, Professor of Nuclear Engineering and Director, Laboratory of Basic' i
Dr.
L and Applied Nuclear Research Typo of
_ Duration of On tho-Formal Training Whero Trained
- Training Job Courso I
a Oak Ridge, Tennessco X-10 1 year Yes No Battolle Memorial Instituto.
6 years
.Yes No
. ?-
b Samo as a c
Oak Ridge, Tennessee X-10 l' year Yes
-No Dattello Memorial Institute 6 years Yes No University of Cincinnati
.6 years
.Yes No
'd Samo as c s
I Experienco with Radiation:
Maximum Duration of Isotopo Amouni Whore Experience was Gained Experience Type of Use Fission Megacuries Battelle Memorial Institute 6 years R&D Products
{ Atomic No. 1 Ci Dattelle Memorial Institute 6 years R&D 4-83 i Atomic No, 1 mci University of' Cincinnati.
6 years Instructional 4-83 1
l 9tnerolNo. 06678 -
...__-__----____L--_-
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JAMES N. ANNO, PhD Associate, Professor of Nuclear Engineering Director, Laboratory of Basic -and Applied Nuclear Research PhD
'65 The Ohio State University (Physics) 4 MS
'61 The Ohio State University (Physics)
BS
'55 The Ohio State Univeralty (Physics)
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Professional and Society Affiliations:
.hp,.,
7 Amer. Nuclear Society Sigma Xi
<:s Amer. Nuclear Soc.-Southwest Ohio Amer.* Physical Society Phi Beta Kappa t
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_ Fields of Special Interest:
.V Engineering Aspects of Nuclear Radiations Lubricat1on Mechanics Secondary Electron Emission
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_ Experience:
i 1970-University of Cincinnati Director, Laboratory of Basic 6 Applied Nuclear Research Associate Professor of Nuclear Engineering 1953-70 Battelle Memorial Institute, Columbus Laboratories
- i 1969-70 Research Fellow, Nuc1 car Engineering and Analysis Division 1967-69 Chief, Lubrication Mechanics Division 1965-67 4 Associate Chief, Structural Physics Division.
1960-65 Associate Chief Applied Nuclear Physics Division
{
1955-60 Operating Supervisor, Battelle Research Reactor 1953-55 Research Technician
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Publications and Reviewed. Paners: (* den'otes refereed j ournal)
- Analysis of Corrosion of Stainless Steel in a Sodium and High Radiation 1
Environment, Nuclear Technology 10, 67 (January,1971), with J.
l
A. Walowit.
GIntegral Form of the Derivation of Rayleigh's Criterion for th
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bility of an Inviscid Cylindrical Jet, e 5 " a-Amer. Journ. of Physic.
JUB,1255 (1970), with J. A. Walowit.
1 CInfluence of Shear Heating on the Motion of an Electrically St Dielectric Fluid Film, Journal of Applied Physics ressed Thin 41, 2258 (1970) q with J. A. Walowit.
6 Load Support and Leakage from Microasperity-Labricated Face Seals 1
International Conference on Fluid Scaling, Philadelphia, Pa., (May
, Fourth I
1969),
Also Journal of Lubrication Technology (In publication),
with J. A. Walowit and C. M. Allen.
o sc Breakdown Voltage for a Thin Dielectric Fluid Film, Journal of Ap-plied Physics, 30, 4326-4328 (August 1968).
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JAMES N. ANNO l
Study of Cathodic Cleaning with the Plasma Arc, Welding Journal, M, No..
4,181-s (April 1968), with H. E. Pattee and M. D. Randall.
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- Microasperity Lubrication, Third International Conf erence on Fluid Seal-b[
ing, England (April 3-5, 1967), with J. A. Walowit and C. M. Allen, Also Journal of Lubrication Technology, 90, Ser$es F, No. 2, 351-355 (April 1968).
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- Factors Influencing the Effects of Reactor Radiations on Electrical Com-ponents, Nuclear Applications, 2, 371 (October 1966).
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- Secondary Electron Production from Approximately 1-Mev Alpha Particles-
.J Emerging from Gold, Journal of Applied Physics (Communication),3_7,,
- U{.ll W
2929 (1966), with L. L. Yarger.
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- Sputtering of Polycrystalline Gold by Fast Neutrons, Journal of Applied
' j, !
Physics, 3_7, ~ 621 (1966) with D. W. Norcross and B. F. Fairand.
i
- Secondary Electron Production from Alpha Particles Emerging from Gold, f
Journal of Applied Physics, 3_4,, No. 12, 3495-3499 (December 1963),
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AFission Plate Power Measurement by a Transient Temperature Method, Nuclear Science and Engineering,16, No. 4 (August 1963).
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A Direct-Energy-Conversion Device Using Alpha Particles, Nuclear News, 5, G. ;', '
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No. 12 (December 1962).
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- The Energy Spectrum of Fission Fragmenta Emitted f rom Thin Layers of
",' b.;'s Uranium Dioxide, Journal of Applied Physics,33 (November 1962)
Let ter-to-the-Editor, with R. W. Klingensmith and R., F. Redmond.
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The Triode Concept of Direct Conversion. Battelle Technical Review, 3-9 (October 1962), with S. L. Fawcett.
. 9
.;;]d A New Concept for Direct Conversion, Southwestern Ohio Section, American t II/3 Nuclear Society, Proceedings Vol.
,1_, 13-19 (September 1962).
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- Secondary Electron Production f rom Fission Fragments Emerging from Thin Layers of Uranium Dioxide, Journal of Applied Physics, 33_, No. 5, lj.j,:.
1678-1681 (May 1962).
,fy the Battelle Research Reactor, Research Reactor Journal, L No. 2 l
(January 1962) with A. M. Plummer.
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1 A Modified Pile Oscillator for Thermal Neutron Cross-Section Heasure-Nb ments, Research Reactor Journal,,l_, No. 4 (July 1961).
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Technical Meeting Papers g
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Theoretical and Experimental Study of Cathodic Cleaning with Plasma Atc.
with H. E. Pattee and M. D. Randall.
Presented at Amecican Weld-ing Society National Fall Meeting, San Francisco (October 1964).
[
h Conversion of Alpha Particle Kinetic Energy into Electricity, with A. H
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Plummer, ANL-6802, 170-180 (December Paper presented at AMU-ANL
_ Conference on Direct Energy Conversion, November 4-5, 1963).
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-( _L Batte11a Studies on the Triode Concept of Direct Energy Conversion, with A. M. Plummer, presented at the Summer Institute on Direct i
Conversion, at the University of Illinois (July 2,1963).
l Research Reactor Services, presented at the First Annual Meeting of the Institute of-Nucicar Materials Management, (June 21-22, 1960).
Operation and Experimental Use of the Battelle Research Reactor, with A. M.
l Plummer and J. W. Chautain.
Paper No. 27 presented at the Nuclear t J Engineering and Science Conference at New York, N..Y. (April 1960).
A Modified Pile Oscillator for Thermal Neutron Absorption Cross-Section
{' a Measurements, with R. G. Jung and J. W. Chastain. ANS paper pre-
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sented in Los Angcles, California (June 1958).
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d Experience with a 1-Megawatt Pool-Type Research Reactor, with A. M.
' (
Plummer and J. W. Chastain. Presented at the 1958 Ceneva Con-ference (April 1958).-
_p Experiments with the Battelle Research Reactor, with 'J. W. Chastain; ANS Tl paper presented at the Meeting in Washington, D. C.
(December 1956).
P
.s Experimental Temperature Distributions in Fueled and Non-Fueled Plates in G
the Bulk Shielding Reactor, with K. M. Henry.
ANS paper presented
,5 at the meeting in Chicago, Illinois (June 1956).
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- $,..' $..,i Other Publications:
Secondary Electron Production from A3pha Particles and Fission Fragments, i
Disadrtation, The Ohio State University (1965).
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U. S. Research Reactor Operation, Maintenance. and Use took. With J.'
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W. Chastain, R. F. Redmond, A. M. Pluccer, F. J. Jankowski, W. S.
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Hogan, D. H. Stall, H. R. Nelson, and C. R. Tipton (1958).
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