ML20237K856
| ML20237K856 | |
| Person / Time | |
|---|---|
| Site: | 05000538 |
| Issue date: | 08/21/1987 |
| From: | Oliphant V MEMPHIS STATE UNIV., MEMPHIS, TN |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8708270322 | |
| Download: ML20237K856 (15) | |
Text
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/ g iff 11 MEMPHIS STATE UNIVERSITY
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MEMF HIS TENNESSEE 38152 g/
} {'\[<!:2P Oflice of the Vice President Telephone: 901/454-2991 for Advancement and Continuirog Education ,Q g?
August 21, 1987 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: DOCUMENT CONTROL DESK
Dear Sir:
Enclosed please find copies of the technical specifications for Ludlum, Model 3 Geiger Counters and Model 42-4, 43-5, and 44-9 Detectors. These instruments were referenced in our response to question number 16 dated May 22, 1987. This question was included in your letter of April 22, 1987. I am supplying this information as a further clarification of the information given in our response. I have requested, in the interest of tire, that I.R.M.
send the technical specifications for the F.A.G. Nuclear Survey Meter, Model-40 directly to your office.
I am also enclosing a copy of a resume from Dr. Bobby Leonard, of The Institute for Resource Management, who will be representing I.R.M. throughout the decommissioning process.
I would also like to verify the information given to Mr. John Minns of your office in his phone conversation with Mr. Bob Riley, the Radiation Safety Officer for Memphis State University. This conversation concerned the status of the reactor fuel, which has been returned to the U.S. Department of Energy and is currently being stored at Oak Ridge National Laboratories. The Radium 226-Beryllium start-up source is in storage in building 113 and is licensed under Tennessee Radioactive Materials License No. R-79177-C89.
Please let me know if there is any additional information I may provide. Thank you for your very kind assistance in this matter.
yinerely, -
p~% g B2 O g Q g Van N. 01iphant p Vice President Advancement and Continuing Education 11 E Enclosure g C: Mr. Bob Riley, Radiation Safety Officer, MSU An EqualOpportunity/Mfirmative Action University
fudlum oeiger cmmters THE MODEL 2 S b/
A brand new counter, designed in the Seventies for use in the Seventies. Two *
"D" cell flashlight batteries will operate this unit-INCLUDING THE SPEAKER
-for 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />. Rugged is the word, even the meter is housed in a cast alutninum l bezel. A new transistorized regulated high voltage makes this a truly outstanding kJ NT i geiger counter.'The audio system is standard on this 0 to 50 MR/Hr meter. Any GM N probe offered by Ludlum will work on this unit as viell as many of the scintillator since an adjustable high voltage is provided.
1HGHLIGHTS: . 300 Hours from two standard "D" size batteries, replaceable MODEt 2 from the front panel . Individual range calibration potentiometers . Ruggedized meter . Fully transistorized . Temperature compensated . Electronically regu-lated power supply . Easily serviced fold-out circuit boards . Taut band meter
. Corrosion resistant . All components derated to insure long life . Liberal one ,
{
year warranty.
SPECIFICATIONS- # )
Range: Three linear ranges from 0-50 MR/Hr. Meter scale presentation 0-5 MR/Hr '
(CPM upon request) with multiples of X.1, XI, and X10.
Response: Toggle switch selection for 3 or 11 seconds.
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Sensitivity: 40 millivolts.
Reset: Push button switch for meter reset. YJgi DN
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High Voltage: 900 volts for Geiger probe. Externally adjustable from 400 to 1500 volts.
k ;J Audio: A built-in Unimorph speaker system with On-Off switch.
Connector: Series "C",
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Linearty: Plus or minus 5% of full scale. i Calibration Stability: Less than 159 variance to battery end point. MODn 3 ]
Meter: 50 Micro-amp,2%" diameter, taut-band suspension.
Size: 3.4" X 3.5" X 7.0" (H X W X L exclusi~ of handle). l
- FH+hbho - t Weight: 3.5 pounds less detectors.
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THE MODEL 3 -- S $ g he 6 0 eC5 o rt b h k MODEL 44 6 i
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Thin Wall GM j This unit incorporates all of the deluxe features found in the Model 2 plus an additional range The four scale unit allows operation from 0 to 200 MR/Hr. Four scales of 0-2 MR/Hr with multiples of X.1, X1, X10,and X100.(0-5K CPM or 0-50
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CPS upon request)
DETECTOR SPECIFICATIONS AND ORDER INFORMATION ON REVERSE $1DE.
MODEL 44-9 Pan oke GM
- i MODEL 42 4 MODEL 43-2 MODEL 43-5 MODEL 44 2 Srnol! Area Alpha Scintillator Alpha Scintillofor Scintillator 1"x1" Not (TI) 10" Spher. Neutron Scintillator LUDLUM MEASUREMENTS, INC. . 501 Oak . Sweetwater, Texas 79556 Telepnone (915) 235-5494 l
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MODEL 44-7 End Window GM MODEL 42 4 Neutron Detector !
The Model 42-4 is a portable neutron detector.*
Detector: LND 7232 This instrument provides t,he monitor of a unknown Window: 1.5 to 2 mg/cm2 mica neutron spectrum with instrumentation allowing !
Window Diameter: 1.25,, direct interpretation with speed and accuracy.
' Well: .125" stainless steel Achieving a spectral response closely approximating i Dimension: 1.375" X 5%" long the dose curve for neutron energies from thermal to l 7 MEV, the detector retains capability through '12 i Weight: % poun6 MEV and exhibits high sensitivity, good gamma re-Replaceable GM tube jection and excellent stability.
I Sensitivit : Thermal neutrons . . 1 millirem /HR-MODEL 44-9 Pancake GM 74 CPI 1 MEV neutrons . . . I millirem /HR-58 CPM.
Detector: LND 7311/8767 Gamma Rejection: 1500 MR/HR.
Window: 1.5 to 2 mg/cm2 mica Detector: 4mm x 4mm LiS1 (EU) Harshaw Scintilla-Window Diameter: 1.75" ' tion crystal coupled to RCA 931A photomultiplier Mounting: Aluminum holder, handle and window tube by optical quality acrylic light pipe.
Protector Moderator: 10" diameter high density polyethylene j Dimensions: 2%" wide,11" long 1.050" dia. Handle. sphere fitted with stainless steel handle and poly-Weight: % pound ethylene feet.
Weight: 18 pounds.
I Dimensions: Maximum height,12 inches. Maximum 1 length,12 linches. Maximum width,10 inches. l MODEL 44-6 Thin Wall GM
Reference:
- 1. Los Alamos Scientific Laboratory Re-Detector: LND 725 p rt No. LA-2717 "A Neutron Monitoring Instru- !
Wall Thickness: 30 mg/cm2 Stainless Steel Rotary Beta Shield: 1000 mg/cm2 Stainless Steel ment tional Having To The -a Response Dose Approximately Rate From Propor-hermal to 7.0 MEV" by D. E. Hankins, August,1962. 2. Bramblett. Ewing j Dimensions: 1-3/16" x 6-1/2"
' Efiiciency for Radium 226: 1700 CPM per MR/Hr. and Bonner, "A New Type of Neutron Spectro-Weight: 12 ozs. meter," Nuclear Instruments and Methods, Sept.
1,1960.
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MODEL 43 5 Alpha Scintillator MODEL 44 2 High Energy Gamma Scintillator Multiplier Tube: RCA 6199 Detector: 1" X 1" Na! (TI)
Scintillator: ZnS (Ag) Multiplier Tube: RCA 6199
- Window: 1 mg/crr.2 aluminized mylar Dimensions: 7%" X 2" Counting Area: 50 cm2 active area Weight: 14 ozs.
Dimensions: Outside window 7%" X 2%" Length including handle 15" Weight: 2 pounds MODEL 44 3 Low Energy Gamma Scintillator
+
Sp ifications same as model 44-2 except MODEL 43 2 Alpha Scintillator (small) Detector: Imm xl" Nal(TI)
Multiplier Tube: RCA-6199 Ideal for 1125 Scintillator: Img/cm 8aluminized mylar Window: 1 mg/cm2 aluraimzed mylar Counting Arca: 1%" diameter (11.6 cm 2)
Dimensions: 6%"x 2" Weight: 14 ozs.
The Model 2 or 3 is supplied with a 39" cable, two "D" cell batteries, and an instruction manual. Choose a detector and add the price of the counting uait with the price of the detector for the cost of a complete unit. You may order a variety of detectors with your new counting unit if you wish. Orders may be placed, either by
. telephone or mail, with your area Ludlum representative or direct with the factory. Firm quotations will be given upon request. The FOB point is Swcetw ter, Texas.
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J udlum mom 42.is 42 2. 42 4 NEUTRON DETECTORS GENERAL DESCRIPTION For detection of neutrons, the basic detector utillies the n. alpha or n.p reaction. By either scintillation i er proportional methods, the electronic pulse generated by the reaction is much larger than the gamma e reaction from gamma background.
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Neutron detectors can "see" gamma radiation as low as 10 MR/Hr. By using discrimination. garr.ma counts can be reduced to very low levels in the range of one to ten R/Hr. It will be noticed that a very stull change in discrimination level will cause a marked change in gamma response in the 10 MR/Hr to 10 R/Hr range.
In a field of a R/Hr, the gamma photon level is measured in the level of million per second. Thnogh the efficiency for the gamma.e reaction is almost insignificant In most neutron detectors, several reactions will ocr.ur within . .. .
the resolution time of the detector and a composite pulse a; large as the neutron reaction will be developed and counted. In that the efficiency for the gamma.e reaction increases with decreasing energy, a neutron detector will tend to be more sensitive to low energy gamma radiation. This explains the strange observation that gamma sensitivity remains relatively constant or increases slightly as a thermal detector is placed in a large moderator.
MODEL 421 THERMAL SCINTILLATION NEUTRON DETECTOR f" DETECTOR: One.!nch diameter NE 400 Boron Glass -
detector with ZnS( Ag) activation. n. alpha reaction. #
. IN '
OPERATING POINT: 900 volts with discrimmation at 3 millivolts. W ggf h %n EFFICIENCY: Approximately 60 counts per minute Q 3)
- per n/cm'/ seconds. p GAMMA REJECTION: Excess of 10 R/Hr. s%g$47 f
ENERGY RESPONSE: 1/v for thermal neutrons. Di s DIMENSIONS: 7" long by 2" diameter.
WEIGHT: 14 ounces. MODEL 42 4 NEUTRON DETECTOR The Model 42 4 is a portable neutron detector.*
7 o This instrument provides the monitor of a unknown neutron
% -4 J % Vh[. g' q spectrum with instrumentation allowing direct interpretation with speed and accuracy. Achieving a spectral response bt TI . s m $iJ@* h fj closely approximating the dose curve for neutron g energies from thermal to 7 MEV (see Fig.1), the detector
{B retains capability through 12 MEY and exhibits high sensitivity, good gamma rejection and excellent stability.
MODEL 42 2
- FAST NEUTRON SCINTILLATION DETECTOR ,,,, ,, ,
,$;",,[j'H'R 8 DETECTOR: NE.404 crystal 2" diameter. Proton recoil typ, GAMMA REJECTION: 1500 MR/HR.
utill:1ng ZnS( AG) for detection of the proton. DETECTOR: 4mm a 4mm Li'l(EU) Harshaw Scintill: tion EFFICIENCY: Function of energy and gamma rejection crystal coupled to RCA 931 A photomultiplier tube by optical selected. At 1 R/Hr gemma rejection (radium 226) quality acrylic light pipe.
approximately 15 counts per minute per n/cm*/ seconds MODERATOR: 10" diameter high density polyethylene from 5 MEY neutrons. sphere fitted with stainless steel handle and polyethylene feet.
GAMMA REJECTION: I R/Hr. ELECTRICAL REQUIREMENTS: Counting system capable
' OPER ATING ' POINT: 900 volts at 3 mv discrimination levei of 5 millivolts input sensitivity,900 volts D.C.
WEIGHT: I pound. CONN ECTOR: Series C Teflon filled,500 VDC.
SlIE: 7%" long by 2%" diameter. WEIGHT: 18 pounds.
DIMENSIONS: Maximum height.12 inches. Maximum length,12 inches. Maximum width.10 inches.
REFERENCE:
- 1. Los Alamos Scientific Laboratory Report i a f Q q@t I
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1; No. LA 2717 "A Neutron Monitoring Instrument Having a Response Approximately Proporti. ..J To The
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Dose Rate From Thermal to 7.0 MEY" by D. E.
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% HuHns. August.1962. 2. Bramblett, Ewing and Bonner,
% New Type of Neutron Spectrometer." Nuclear j
j b;ncts'jagedn h7.M k Instruments and Methods. Sept. I,1960.
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.. g LUDLUM MEASUREMENTS, INC. - 501 oak street . sweetwater, Texas 79556 Telephone (915) 2354494
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THE FRIARY WINCHESTER ON THE SEVERN 1600 WINCHESTER ROAD ANNAPOLIS MARYLAND 21401 (301) 757 6503 July 30, 1987 Mr. Robert Riley Radiation Safety Officer Safety Services Memphis State University Psychology Lecture Hall Memphis, TN 38152
Dear Bob:
You have requested that I provide you with information relative to my experience with the decommissioning of nuclear reactor facilities. I am enclosing a copy of my resume which provides general information regarding my background.
Specifically, I have held three Senior Reactor Operators' Licenses as follows:
North Carolina State University, Raleigh Reactor, R-3,10 kw Illinois Institute of Technology Research Institute, Research Reactor, 15 kw Armed Forces Radiological Research Institute,1 Mw TRIGA Reactor I was director for the decommissioning of the following reactors:
N.C. State University - R-1 Reactor 11TR1 Reactor University of Wyaning - AI L-77 Colorado State University - AGN 201 University of Nevada - L-77 Polytechnic of New York - AGN 201 I participated in the planning and assisted in the decommission for tha following:
Army Power Reactor, SM-1A, Fort Greeley, Alaska,10 Mw Walter Reed Army Reacor, 50 kw University of Delaware, AGN-201
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Mr. Robert' Riley a'
-July.30,'1987 Page.Two j 4
i L . Finally, l participated in the installation and startup of the following: l Neutron Radiology, TRIGA-250. kw i Kyang Hee University, Korea, AGN-201
.N.C. State University, R-1
~
N.C. State University, R-3, 10 kw N.C. State University, Pulstar, 1 Mw j
If you should need any further information to assist in the approval for the 'l decommissioning of the Memphis State University reactor..please contact me.
Best regards,
- M Bobby . Leonard, Ph.D.
President BEL kpp..
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'B0BBY E. LEONARD - CURRICULUM VITAE EXPERIENCE: 1986 - Present General Partner Leonard Group Limited Prtshp.
Annapolis, MD ,
1985 - 1987 President Applied Construction, Inc.
e , Annapolis, MD Hartsville, SC' )
'i 1985 - 1987 President Applied Support, Inc.
x- Annapolis, MD L Hartsville, SC
- j. 1986 - Present President Academy of IRM, Inc.
Annapolis, MD
)
1970-1987 President and Institute for Resource l f Senior Scientist Management, Bethesda, MD 1968-76 Adjunct Professor Catholic University of ,
Radiological Physics America i 1969-70 Consultant Hittman Associates, Inc.
1968-70 Consultant Nuclear Systems Associates ;
i 1966-70 Head, Research Reactor and Radiological i Branch Physics Divisions, AFRRI ;
h- 1966 Acting Head, Nuclear N.C. State University l Reactor Project I I
1965 Assistant Professor Department of Nuclear .
Engineering, North Caro- !
lina State University
'1964-66 Member State of North Carolina Radiological Emergency Team 1962-65 Research Associate N.C. State University Nuclear Reactor
. . ,_ - ~ . -_ Project 1961-62 Operations Engineer, N.C. State University Nuclear Reactor Project 1960-61 Research Consultant Research Triangle Insti-tute, Durham, N.C.
00(ATION: B.S. Civil Engineering 1952 North Carolina State University B.S. Physics 1956 Johns Hepkins University M.S. Nuclear Engineering 19S8 North Carolina State University Ph.D. Nuclear Engineering 1966 North Carolina State University L' .
I SOCIETIES: American Nuclear Society, Past Chairman, Washington Section). -
American Institute of Physics (past msnber). ;
(
Amrican Ihysics Society (pas? member). j Sigma Xi Honor Society.
Sigma Pi Sigma Physics Honor Society Phi Kappa Phi Honor Society Sigma Phi Epsilon Social Fraternity SPECIAL DuBach S. Grant Scholastic Award, Sigma P ' Epsilon,1952.
AWARDS:
U.S. Atanic Energy Commission Fellowship, 1960-61.
Leaders in American Science, Vo).. VIII, 1968-69.
Amer.ican Men of Science, lith Edition,1970.
m o's Who in Atoms, 1976-77 Edition.
Who's 20 in North American, 1976-77 Edition.
- Chairman, American Nuclear Society Washingtr, '9ction, 1977-7.8.
IRM REIORI'S:
Isonard, " Shielding Analysis for the Mississippi State University l Research Reactor", IRM Technical Report 101 (1967). '
Isonard, " Safety Analysis Report - Mississippi State University Re-actor", IRM Technical Report 103 (1967).
IAonard, " Transient Analysis of the Mississippi State University Reactor", IRM Technical Report 104 (1968). i Leonard, " Estimated Fission Product Activity and Nuclear Decay Heat of the Irradiated Fuel in the Illinois Institute of Technology Research Reactor", IRM Technical Report 102 (1967).
Leonard, " Planning for the Deactivation of the Illinois Institute of Technology Research Reactor", IRM Technical Report 105 (1967).
Also published as an IIT Research Institute Report.
Leonard, Maler and Davis, " Application for a License to Package and Transport the IITRI Fbel Solution to Savannah River Plant",
IRM Technical Report 125 (1970).
_ _ _ _ _ _ _ _ _ _ _ . _ _ _ ___ l
.A '
MAJOR Director, Dimantling of N.C. State Reactor R-1 (1961).
- SPECIAL
, PRW ECIS: Planner, N.C. State PUISTAR Reactor (1965) .
Consultant and Chief Planner, Deactivation of IIT Research Insti-tute Reactor, 1967-68.
- Consultant, Construction of Mississippi State University Research
- Reactor, 1967-1969.
a Chief Conceptual Designer, AFRRI 500,000 Curie Co-60 Gamma Irra-diation Facility (1967).
Director, Decommissioning of IIT Research Institute Research Re-
}. actor R-3 (1970).
PUBLICA- " Nuclear Physics Laboratory Manual", (published locally),1958, TIONS: (With A. W. mitner). !
" Measurement of the Spontaneous Fission Neurmn Field of Natural Uranitzn", Journal of Nuclear Energy, Part A Reactor Science, Vol. [
. II, No. 1, pp. 1-7 (With A. W. Waltner) . j
" Nuclear Reactor Laboratory Manual", (published locally), 1961, B. E. Leonard, et al. .
" Cosmological Spaces Admitting Geodesic Correspondence", Journal of the Elisha Mitchell Scientific Society, Vol. 77, No. 2, Nov- _
i ember 1961. (With W. R. Davis).
" Power Calibration of Nuclear Reactors by the Integrated Flux Method", Technical Report No. 1, Physical Sciences Research, School of Physical Sciences and Applied Mathematics, N.C. State, 1962 (with E. J. Story).
" Reactivity Measurements in Nuclear Reactors", Technical Report No. 2, Physical Sciences Research, School of Physical Sciences ,
and Applied Mathematics, N.C. State, Decenber,1962 (with E. J. I Story).
" Measurements of the Transfer Function of the North Carolina State Heterogeneous Reactor", Technical Report No. 3, Physical Sciences Research, School of Physical Sciences and Applied 1 "hematics, N.C. State (with H. K. Kim) .
"A New Approach to heactor Kinetics", Technical Report No. 4, Nu-clear Reactor Project, School of Engineering, N.C. State, Feb.
1964.
1
t PUBLICA- " Termination of Reactor Excursions ty Control Mechanisns", Tech-TIONS nical Report No. 5, Nuclear Reactor Project School of Engineering, j (cont): N.C. State,1964.
l
" Temperature Coefficient and Power-Temperature Coupling Measure- a nents and Analysis", Technical Report No. 6, Physical Sciences Re-
.i search, N.C. State,1965.
l I
" Neutron Slowing Down in Finite Moderator Media fran a Fast Neu-
)
tron Burst", Ph.D. Theses, N.C. State University,1965. !
l I " Investigation of the Rise Portion of Pulsed Neutron Curves, Neu- {
tron Dynamics and Control, A.E.C. Synposium, Series No. 7, CONF- !
650413, 1966.
" Experimental Data on the Production of Argon-41 in Reactor Expos-ure Rooms", Health Physics Jcurnal, Vol.14, pp. 515, May 1968. j l
" Measurements of the Transient Control Rod Motion and Its Ef fect {
on the AFRRI-TRICA Reactor Pulse", Nuclear Instruments and Meth-ods, Vol. 69, No. 1, p. 157, 1969.
" Increased Dose Requirements for the AFRRI-TRIGA Reactor", AFRRI Internal Report 68-2 (1968). (With R. E. Carter and D. A. 51ughes) .
"An Analytical Pulse Reactor Model with Delayed Neutrons", AFRRI Scientific Report 68-25 (1958).
"An Analytical Reactor Excursion Model with Delayed Neutrons", _
Nuclear Technology, 11, 159 (1971).
"A Paint as a Thermal Neutron Shield", Accepted Health Physics Journal.
"The Average Energy Per Ion Pair, W, for Hydrogen and Oxygen Ions in a Tissue Equivalent Gas", with J. W. Boring, Rad Res 55,1-9 (1973).
"A Precision Test and Research Reactor Excursion Radiation Detec-tion System Using an On-Line Conputer", Nuclear Instruments and Methods, 98 (1972) 501-507.
" Estimates of Kerma and Mass Eneregy Transfer Coefficients in Neutron Fields - A Method", IRM heport (1972).
" Neutron Fluence - to - Kerma Factors and Mass Energy Transfer Coefficients in Neutron Fields", IRM Handbook (1972).
" Evaluation of the Calibration and Use of 50an3 Paired Ionization Gambers to Measure Separate Neutron and Gamma Ray Tissue Absorbed Dose", IRM Technical Note, 1972.
_-____-___J
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PAPERS " Spontaneous Fission Neutron Yield of Natural Uranium", Annual PRESEtHED: American Physical Society Meeting, Southeastern Section,1958.
(With A. W. Waltner) .
" Cosmological Spaces Admitting Geodesic Correspondence", Annual Meeting of N.C. Academy of Science,1961. (With W. R. Davis).
" Investigation of the " Rise" Portion of Pulsed Neutron Curves",
symposium AEC-ASEE, Neutron Dynamics and 2ntrol, University of Arizona, April 5-7, 1965.
" Reactor Laboratory Experiments Demonstrating Delayed Neutron Effects", Trans. American Nuclear Society, Vol. 8, No. . ,1965. j
" Dynamic Reactivity in Nuclear Reactors", Joint Autmatic Control Conference, ASME, Philadelphia, PA, June 1967.
i "The Effect of Delayed Neutrons on Self-Limiting Rector Excur-sions", Trans. Anerican Nuclear Society, Vol 12, No. 1, 1969.
l
" Space-Time Reactivity Effects on a Pulse Reactor", Trans. Ameri- '
can Nucleat Society, Vol.12, No 1,1969.
" Time-Dependent Neutron and Gamnn Ray Dose frm A TRIGA Reactor",
Trans. American Nuclear Society, Vol. 12, 2, 1969. '
"The Radiation Environment of Interest to Radiobiologists frm Special Nuclear Weapons", Classified Seminar, May 1968.
" Pulse Reactor Research and Sme Operational Considerations", In-vited Paper, Trans. American Nuclear Society, Vol. 13, 2, 1970.
" Neutron Fluence-to-Kerma Factors and Mass Energy Transfer Coeffi-cients for Various Materials in Reactor Neutron Fields", Trans.
American Nuclear Society, Vol. 13, 2, 1970.
"TLD 700 (7LiF) Response to Neutrons", Trans. Anerican Nuclear So-ciety, Vol. 13, 2, 1970.
"A Paint to Reduce 41 A r Release and residual Activity in a Reactor Exposure Volume", Trans. American Nuclear Society, Vol. 14., 2, 1970.
" Calculations and Measurements to Estimate the Ef fective W for Neutron Produced Ions in Ionization Chambers", Trans. Anerican Nuclear Society, Vol. 14, 2, 1971.
"The Ef fective W (eV/lon pair) for Neutron Prodiced Ion in a Tissue Equivalent Ionization Chamber" , International Conference on Microdosimetry, Stressa, Italy,1971.
SPECIAL Cmmittee for Acquisition of Scientific Documents, Clearirg House 00MMI'ITEES: U.S. Departnent of Ccxmterce.
Advisory Ccruittee, National Envirorinental Foundation, Washing-ton, D.C.
)
CDURSES PY 205, 208 General Phycies TAUGIT: Corequisite: MA 201 This sequence is required in most engineering curricula. A study of classical and modern physics in which the analytical approach is aplayed and calcuhs is applied as needed. Demonstration lec-tures, recitations, problem drill, and laboratory work are coordi-nated to give a working knowledge of basic principles. PY 205, mchanics, sound and heat, PY 208, electircity, light and rtodern physics.
PY 410 Nuclear Physics I Prerequisite: PY 207 or PY 407 An introduction to the properties of the nucleus, and the inter-action of radiation with matter. A quantitative description is given of antural and artificial radioactivity, nuclear reactions, fission, fusion, and the structure of simple nuclei.
PY 510 Nuclear Physics II Prerequisite: PH 410 _ . _
The description and analysis of nuclear energy levels, meson the-ory nuclear resonance, atomic and molecular magnetism, and cosmic radiation. Principles and experiments in neutron physics are dis-cussed. In the laboratory work, emphasis is placed on gaining ex-perience in independent research.
PY 520 Physical Measurements in Radioactivity Prerequisite: PY 410 The principles of experimental masurments on radioactive mter-ials are presented and demonstrated through laboratory work. Em-phasis is placed ora the analytical interpretation of experimental data.
NB 501 Nuclear Reactor Theory I Corequisite: PY 410 An introductory course in reactor theory ; neluding the fission process, neutron energy distribution, lgthargy, neutron slowing and interactions, diffusion, Fermi age theory, the diffusion equa-tion, criticality conditions, and reactor instrumentation.
I l COURSES NE 502 Nuclear Reactor Theory II j l TAUGrr Prerequisite: NE 501 '
l (cont.): l Continuation of reactor theory fran NE 501. Topics include:
treatnent of reactor paraneters for homogeneous and heterogeneous l rewtors, reflects reactors, multi-graap theory, reactor kinetics, temperature ef fcts, control rod theory, perturbation theory, ard transport theory.
NE 530 Introduction to Nuclear Reactor Theory The principles of neutron notion in matter, with emphasis on the analysis of the nuclear chain reactor. Slowing of neutrons, dif-fusion, space distributions of flux, conditions for criticality, group theories, and the time-dependent behavior of fissionable assemblies.
NE 531 Nuclear Reactor Laboratory Prerequisite: NE 530 or NE 501 Observation and neasuranents of static and dynamic nuclear reactor behavior, the effectiveness of control and temperature, and corre-lation with theory. Experiments on the notion and detection of neutrons and gamma rays, with enphasis on the research uses of nu-clear radiations.
NE 532 Nuclear Engineering Laboratory Prerequisite: NE 501 or equivalent -
This laboratory course will provide a series of experiments that are fundamental to Nuclear Engineering. Special emphasis will be
,' Ji
~
on experiments related to nuclear reactor theory, reactor kinet-ics neutron physics, reactor heat transfer and radiochemistry ap-plications. Several experiments in conjunction with an analog
- conputer will be perforned. Familiarization with reserach equip-ment will be gained through active participation of the student in
,m-m .. setting up the varicus neasurenents.
- - - NE440 Nuclear Reactor Control
. n ,- - A u Prerequisite: NE 502 or NE 530 Considers non-steady-state reactor behavior including reactivity effects due to temperature, poisoning, and control rods. Used elanentary servomechanism theory in treating reactor as a cmtrol elenenty. Treats automatic control including control meci.anism and dynamic effects of power plant characterisites.
., o a
O COURSES T
NE 545 Nuclear Reactor Kinetics rAUGrr Prerequisite: NE 502 or NE 530 i (cont.):
The kinetic behavior of nuclear reactors is carefully analyzed from both theoretical and experimental viewpoints. Solutions of the basic kinetic equations are develcped and applied to spe-cific reactor behavior. Temperature, void and xenon poisoning effects are considered. Digital and analog cmputer techniques are discussed and utilized. Correlation of theory with observed reactor behavior is made and safety considerations in reactor de-sign are dismssed.
The Catholic University of Anerica NSE 771, Principles of Radiological Physics and Radiation Protec-tion The first seminar course will sphasize the fundamental principles of radiation interaction with biological systems and the subse-quent consequences. Radiation quantities and units will be de-fined. Radiation injury and effects in biology will be discussed for cell, organ and whole-body systes. Effects for the ranges of doses and dose rates fran backgrwnd radiation to nuclear weapons exposures will be presented. The concepts of radiation quality associated with LET, Quality Factor and RBE and how they apply to radiation fields and man will be explained. With this basic foun-dation, the past, present and future national and international j radiation protection standards will be discussed and justified.
The various regulatory groups which establish radiation standards and how they interrelate wil be surveyed. Chronic radiation -
effects will be discussed. The inpact of nuclear reactor facil-ities and nuclear explosions on the enviornment and ecology will be examined. This will include the radiation hazards associated with nuclear reactor containment, transport of radioactive mater-ial, fuel reprocessing, and radioactive waste disposal. The paths of escape of radioisotopes fram reactors and nucler explosions their enviornnental constituents and the effect upon ecology will be presented. The subsequent envircrrnental standards and ,
regulations now effective and proposed will be examined. j NSE 772 Radiation Dosimetry
'The 'second smester will be taught such that NSE 771 is a desir-able but not required prerequisite. Radiological Physics and principles of radiation protection will be briefly reviewed.
Radiation dosimetry fundamentals will then be presented, beginn- j ing with the basic theory of radiation field interaction, the '
deposition of energy by ionization, excitations cnd recoil atoms, the productica of free radicals and subsequent reactions with I noleculos. Basic cavity theory as it applied to x-rays, gamma l
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COURSES rays, electrons, heavy charged particles and neutrons will be TAUGiT discussed. The characteristics and principles of radiation
( cont. ) : dosimetry systems such as ionization chambers, neutron detection systems, film badges, TLD, calorimeters, etc., will be studied.
The remainder of the semester will be devoted to the application of these systems and techniques to various radiation sources such as: Environmental man-made and natural radioactivity, Nuclear reactor power plants, Medical Therapy, Radiation in space, and Nuclear explosions. Routine and emergency health physics prac-l tices in radioisotope laboratories and at various other radiation facilities will be presented. Visits to several radiation facil-ities in the Washington , area will be made during the semester.
Workshop on Energy, the Environment and the Role of Nuclear Power Tcpics covered in course are: World and U.S. Energy Supply and Demand; The Energy Crisis and Energy Source Alternatives; Envir-onnental Factors Affecting Future Energy Sources; Nuclear Power Configurations and General Environmental Considerations; Radia-tion Effects, Protection Standards and "As Low As Practical"; Cal-culation of Radiation Exposure Doses, fran Internal and External Sources (Required for credit, optional for non-credit); Plant Radioactive Material Managanent; Environmental Considerations in Nuclear Ebel Processing; Therman and Olemical Pollution and Heat Dissipation Systens at New Pcwer Plants; M9teorology and Air Transport of Releases; Environmental Monitoring and Surveillance )
Techniques; Calculational Methods in Transport of Releases - Ra-diological, Olemical and Thernan; Biological Effects on Biologi-cal Consequences to Man of Energy Generation; Environmental Re-ports and Impact Statenents; Cost / Benefit Concept; Kuclear In- -
struments and Reactor Operations (Required for credit, optional for non-credit); Transportation and Disposal of Radioactive Material; Nuclear Plant Accident Safeguards, Probabilities and Consequences; Power Plant Siting; The Interveners Position on Nuclear Power; 'Ihe Year 2000 Studies; An approach to Environment-al Concerns Related to our Energy Crisis; The Selection Process of a Utility Conpany for Choosing Fossil Fueled vs. Nuclear Plants; Nuclear Fusion, the Energy Utopia - A Drean or Reality and Possible Concerns.