ML20116F975
ML20116F975 | |
Person / Time | |
---|---|
Site: | Neely Research Reactor |
Issue date: | 06/24/1996 |
From: | Karam R AFFILIATION NOT ASSIGNED |
To: | |
References | |
REN-A-004, REN-A-4, NUDOCS 9608070241 | |
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! *' 00CKElED
, RESUME i
MAME:
95 33[ 18 . Pi2 :26 Ratib A. Karam, Ph. D.
- 0FFICE OF SECPETARY e ADDRESS
- DCCKETiNG & SERVICE
- . BRANCH
- OFFICE RESIDENCE !
I Neely Nuclear Research Center 6133 Kings Mountain Court i Georgia Institute of Technology Stone Mountain, GA 30087 l 900 Atlantic Drive, N. W. Telephone (770) 564'2983 Atlanta, GA 30332 i Telephone: (404) 894-3620 ,
l '
! EDUCATION:
Ph. D., Nuclear Engineering, University of Florida, 1963 M. S., Nuclear Engineering, University of Florida, 1960
! B. S., Chemical Engineering, University of Florida, 1.958 i
i
! EXPERIENCE AND BACKGROUND:
- 1984 - Present Director, Neelv Nuclear Research Center, Georgia
- Institute of Technology, Atlanta, GA 30332.
Accomplished the following
- o Developed and obtained USNRC approval for an l
{ Emergency Preparedness Plan for the 5 MW Georgia !
l Tech Researen Reactor (GTRR). 'l I
l
- o Developed a plan and obtained USNRC approval for dismantlement and decommissioning of the Georgia Tech AGN-201 reactor. Decommissioning was ;
completed in 1986.
o Coordinated in record time, i.e., 8 months, the planning, procedure writing, procedure ;
implementation and personnel training / retraining i for.the GTRR restart program.
o Increased GTRR program funding to the levels needed !
to more than cover expenses from 1983 - 1996. l o Restructured the Georgia Tech Radiation Safety Office and built it on a foundation of technical excellence governed by detailed, written procedures.
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. R. A. Karam
- Page 2 o Restructured reactor operating personnel and redirected the " operational culture" from one of
- casual informality to one governed by written,
. approved procedures. Sensitivity training to USNRC regulations and requirements was strongly featured.
i o wrote proposals and directed research activities ;
with a volume of $11 million dollars.
o Organized the Education, Research and Development Association of Georgia Universi'ler and obtained a multi-million dollar contract with Westinghouse and !
the Department of Energy. -
a
! 1972 - Present Professor of Nuclear Encineerina and Health {
j Physics, Georgia Institute of Technology, Atlanta, !
l GA 30332. Accomplishments include the followings i 2
o Originated and taught the following courses: l
- NE 6201 Advanced Reactor Physics I
, NE 6202 Advanced Reactor Physics II .- '
!' NE 6235 Reactor Safety NE 6237 Fast Reactors ;
j NE 6205 Reactor Laboratory 1
o Taught the following courses:
NE 4201 Reactor Physics I
- NE 4202 Reactor Physics II NE 4205 Reactor Laboratory 4
NE 6260 Radiation Shielding i NE 6229 Reactor Applied Theory ~
j NE 3211 Introduction to Nuclear Engineering i L l o Coordinated graduate curriculum for the School of i Nuclear Engineering for 10 years. j G
- o Supervised 12 Ph. D. students and numerous M. S.
I candidates.
! o Edited the following books:
- 1. " Energy and the Environment -
Cost Benefit Analysis." Pergamon Press, 1975, with K. Z.
Morgan.
- 2. " Environmental Impact of Nuclear Power Plants." Pergamon Press, 1975.
- 3. " Advanced Reactors: Physics, Design and 1 Economics." Pergamon Press, 1974, with J.
j , Kallfelz.
1 i
i i
b
1 R. A. Karam Page 3 i l
- 4. " Societal Cost of Nuclear and Other Energy j Alternatives." Pergamon Press, 1981, with L. I Weaver. ;
- 5. " Anticipated and Abnormal Transients in l Nuclear Power Plants." Two volumes, ANS, l 1987. l i
o Research activities included: Doppler Broadening; perturbation theory; neutron transport; anharmonic effects on crystalline binding and effects on :
reactor parameters; advanced reactor concepts based on metallic fuels; cross section generation; fuel cycles; and reactor safety.
o Research interests now includes computerized control of reactor. speration using artificial intelligence; operational safety; emergency planning; procedure development; and environmental effluents, measuring techniques and methods 1963 - 1972 Scientist and Encineer. Argonne National Laboratory. Achievements included the followings o Developed measuring techniques for adjoint flux and die-away modes of prompt neutrons and normalization integral.
o Developed measuring techniques for small reactivity changes and flux profiles. '
o Developed analytical methods to handle exact perturbation theory for situations where severe
- flux depressions existed as a function of space and energy.
o Managed the zero power reactor VI program for LMFBR development.
o Participated in the development of the fast neutron ;
dosimeter. '
o Developed methods for measuring delayed neutron
, emission-from Th-232 to Cf-252.
i o Written safety analysis reports for the EPR-VI assemblies.
r 1 l
. R. A. Karam Page 4 i
o Dr. Karam is a consultant to several national and international organizations . He is also a fellow !
in the American Nuclear Society. He published more than 80 technical papers.
1972 - Present Consultant to various organizations, some of which ,
are listed below: )
l
- 1. Georgia Power Company, Reactor Safety Keview ]
Subcommittee, 1985 to present.
- 2. Southern Company, technical support, 1985 -
present.
- 3. Veterans Administration, evaluate programs of nuclear reactor at Omaha, Nebraska, 1986 -
present.
- 4. Nuclear Assurance Corporation, design of transport and storage casks, 1983 - present.
- 5. Department of Energy, evaluation of LMR designs, 1985 - 1987.
- 6. Batelle Pacific Northwest, dose release in H 2 O from spent fuel.
- 7. Japan Atomic Energy Research Institute, program evaluation, 1974
- 8. Brazil Institute of de Energia Atomica, set up Reactor Physics Program, 1973 - 1974.
- 9. Wells Fargo, develop procedures for handling radioactive substances, 1975 - 1976.
- 10. Board of Directors, Nuclear Services, 1972 -
1974.
- 11. Board of Directors, Energy Technology, Inc.,
1974 - 1976.
- 12. Oak Ridge Associated Universities, Cross Section Evaluation, 1972 - 1982.
O e
R.A. Karam Page 5 HONORS:
o Fellow, American Nuclear Society, cited for outstanding contributions in reactor physics and nuclear engineering education.
o Listed in most Who's Who PROFESSIONAL SERVICES AT GEORGIA TECH:
o Chairman, Nuclear Engineering Schools's Graduate Curriculum Committee, 1972 - 1982 o Chairman, School's Program and Tenure Committee, 1977 -
1979 o Member, Nuclear Safeguard Committee, 1972 - 1978 o Member, Dean's Planning Committee, 1982 - 1983 ,
o Chairman, Ph. D. Preliminary Examination Committee,1983
- 1984 o Member, Dean's Tenure and Promotion Committee, 1983 -
1984 o Chairman, committees of 14 doctoral candidates o Member, numerous committees of Ph. D. and M. S. students' committees o Member, Editorial Board of Annals of Nuclear Energy,1981
- present AT AMERICAN NUCLEAR SOCIETY:
o Chairman, Atlanta Section of ANS, 1977 - 1979 o Secretary, Reactor Physics Division of ANS, 1978 - 1980
, o Executive Committee, Reactor Physics Division, ANS,1980 ,
- 1983 i o Executive Committee, ANS Atlanta, 1979 - 1984 o Co-Chairman, Technical Program, Topical, Advanced Reactors: Physics, Design and Economics, 1974 o Member, National Technical Program Committee, ANS l
p -
. v..
i R.A. Karam Page 6 o-Member, Technical Program Committee, Anticipated ' and l Abnormal Transients in LWR's, 1983 )
o Assistant Chairman, National ANS Annual Meeting, June, i 1980 l i
o Candidate for Board of Directors, American Nuclear '
Society, 1985 !
o Chairman, Glenn Murphy Award Committee, American Society for Engineering and Education o Member, ANS Award Committee, 1985 - present o Chairman, Atlanta Section Honors and Awards Committee, 1985 o Chairman, Technical Program Committee, Anticipated and Abnormal Transients in Nuclear Power Plants, Topical held in April, 1987 INVITED LECTURES:
o " Basic Requirements for Standards in Reactor Physics,"
ANS, 1974 o " Generation of Effective Cross Sections," International Conference held at Brookhaven National Laboratory, 1975 i
o "The Thorium Cycle Potential in a Breeder Economy," ANS, '
1977 -
o "The Pressure Vesuel Question," ANS, 1977 !
o " Denatured Breeders," ANS, 1981 o "The Effective Delays Neutron Fractions and the i Reactivity Coefficient," ANS, 1982
, o " Comparison of Measured and Calculated Delayed Neutron Yields," American Chemical Society, March 1982 o " Heterogeneity and Anisotropy Effects on Group Cross
, Sections," Brc khaven National Laboratory, 1982 o "The U-233/U-238 LMFBR Operating on an Extended Burn-up Cycle," National Science Foundation, 1982
- - - ,- w -me - 1
R.A. Karam Page 7 o " Safety Considerration of Thorium-Based Liquid Metal Reactors" o International Conference on Waste Disposal and Radiation Problems, American Nuclear Society, 1979 PAPERS PUBLISHED IN REFEREED SCIENTIFIC JOURNALS
- 1. " Conceptual Design for an Epithermal Neutron Beam Facility at the Georgia Tech Research Reactor." Sixth International Symposium on Neutron Capture Therapy for Cancer, Nov. 1-4, Koba, Japan, 1994 with Kate Klee.
- 2. " Georgia Tech Research Reactor Conversion to Low Enrichment-Calculational Capability Assessment Proceeding of an International Meeting on Reduced Enrichment for Research and Test Reactors. " Newport, Rhode Island, ANL/RERTR/TM-18, July, 1993. '
- 3. "A Simple and Accurate Numerical Method for Evaluation of Resonance Line Shape. " Annals Nuclear Energy, Vol.18, No. 5, pp.49-257, 1991.
- 4. "On the Evaluation of the Cubic, Quartic and Thermal Phonon Shifts and Cubic Phonon Widths." Annals Nuclear Energy, Vol.
18, No. 5, pp. 254-268, 1991.
- 5. "Anharmonic Effects on the Resonance Line Shape of U23e in UO2 . " Annals Nuclear Energy, Vol. 18, No. 8, pp. 427-442, 1991.
- 6. " Analysis of Partial-Refueling, Ultra-Long Life Core Using Metallic Fuel for 1000 MW(e) LMFBRS. " Nuclear Technology, 86, pp. 49-59, July 1989.
- 7. " Metallic Fuel for the Na-Cooled Reactors with an Extended 4
Burn-up Cycle." Annals of Nuclear Energy, H , 137, 1985.
8.. " Space, Energy and Anisotropy Effects on U-238 Effective
! Capture Cross Section in the Resonance Region." Annals of Nuclear Energy, H , 41, 1984, with B. Meftah.
- 9. " Space, Energy and Anisotropy Effects on Diffusion Coefficients in the Resonance Region. " Annals of Nuclear Energy, H , 41, 1984, with B. Meftah.
- 10. " Interface Effects in Multi-Region Reactors." Annals of Nuclear Energy, H , 33, 1984, with B. Meftah.
y O
R.A. Karam Page 8
, 11. " Metallic Combinations of Pu-Th and U232 -Th or Pu-Th and U:23 U 22' as Possible Alternatives to (Pu-U)O2 in LMFBR's." Nuclear i
Technology, 51, 535, 1982.
! 12. " Denatured Breeders . " Annals of Nuclear Energy, 1, 115, 1981, 1 i
with C. C. Lee.
j 13. " Spectral Shift Effects Induced by Doppler Bordering on i
Reactivity Coefficient. " Nuclear Science and Engineering, !
- 21, 278, 1981, with A. Alapour. l
! 14. " Delay Neutron Yields: Time Dependent Measurements and a Predictive Model." Physical Rev. C., H , 1113, 1981, with R.
- Waldo.
1
- 15. " Spatial Dependence of Effective Resonance Cross Sections."
.; Annals of Nuclear Energy, 1, 215, 1981, with B. Meftaty. -
1 1 16. " Chemical Binding Effects on Resonance Line Shape and Neutron
] Capture Rates." Annals of Nuclear Energy, 1, 255, 1981, with i H. St. John.
- 17. " Measured Delay Neutron Yields." Trans. American Nuclear Society, H, 879, 1981.
! 18. " Denatured Breeders." Invited paper, Trans. American Nuclear
- Society, H , 535, 1981.
I 19. " Effects of Source Anisotropy and Nonuniformity on Resonance i
Cross Sections in Multiregion Problems." Trans. American Nuclear Society, M , 664, 1981, with B. Meftah.
- 20. " Denatured Fuels in LMFBR's. " Trans. American Nuclear Society, M , November, 1980, with A. Alapour.
- 21. " Effects of Resonance Profile Representation on Reactor
. Integral Parameters." Trans. American Nuclear Society, M ,
i
. November, 1980.
- 22. " Optimization and Comparison of the Growth Potential of Metallic Pu-Th and U232 -Th with Mixed Pu-U Oxide in LMFBR's." I i
Trans. American Nuclear Society, November 12-16, 1979, with C. I C. Lee.
- 23. " Safety Considerations of Thorium-Based Liquid Metal Fast Breeder Reactors. " International Conference on Waste Disposal and Radiation Problems, 1979, with C. C. Lee.
1 l
4 A
2
g-R.A. Karam Page 9
- 24. " Liquid Metal Fast Breeder Reactors with Thori un-Based 3 Metallic Fuels." International Conference on Waste Disposal
- .and Radiation Problems, 1979, with C. C. Lee.
i
- 25. " Breeding Performance of Metallic Pu-Th, U233-Th , U233-U23e
] Versus (Pu-U)O2 Fuels in LMFBR's. " International Symposium on l Fast Reactor Physics, IAEA Report No. IAEA-SM-244-60, 1979, i with C. C. Lee.
l l 26. "The Pressure Vessel Question." Trans. American Nuclear Society, H , November, 1977.
4
- 27. "The Thorium-U " Cycle as an Alternative to LMFBR's. "
2 Trans.
!, American Nuclear Society, H , November 1977.
i 28. "A General Method for Generating Effective Resonance Cross l Sections for Heterogeneous Media." Nuclear Science and l
Engineering, H, 215, 1976, with K. D. Kirby.
! 29. " Spacial Dependence of Broad Group Cross Sections," in i Advanced Reactors: Physics. Desian and Economics,* J. M.
! Kallfelz and R. A. Karam, eds., Pergamon Press, 1975, with C.
j Mildrum.
- 30. "On the Discrepancy Between Measured and Calculated Central j Reactivity Coefficients." Nuclea.7 Science and Engineering,
- H , 201, 1973.
j 31. "On the Discrepancy Between Measured and Calculated Central 4
Reactivity' Coefficients." Trans. Junerican Nuclear Society, j H, 504, 1972.
l 32. "On the Discrepancy Between Measured and Calculated Reactivity l Coefficients." Proc. International Meeting on Fast Reactor
- Physics, Tokyo, Japan, 1973.
]
l 33. " Comparison of ENDF/B Versions I, II, and Preliminary III." l 1 Trans. American Nuclear Society, l b 458, 1972. l j 34. " Anisotropic Effects in a 4000-Liter UO Fast Core, EPR-6
. Assembly 6A." Trans. American Nuclear Society, 11, 21, 1971.
l 35. " Analysis of Heterogeneity and Sodium Void Effects in a 270- 1
< Liter Uranium Carbide Fast Core, EPR-6 Assembly 5." Nuclear !
Science and Engineering, D , 5, 1971.
i: 36. " Analysis of Central Reactivity Worths in Fast Critical
].
Assemblies." Nuclear Science and Engineering, iq, 414, 1970.
I
( -
,. -m,w -
R.A. Karam Page 10
- 37. " Analysis of Sodium-Void Coefficients." Trans. American Nuclear Society, M , 284,.1970.
- 38. " Measurements of the Normalization Integral and the Spatial Distribution of the Importance of Fission Neutrons." Nuclear Science and Engineering, H , 192, 1969.
- 39. " Analysis of the Die-Away of Prompt Neutrons with Two-Group Time Dependent Diffusion Equations in Reflected Reactors. "
Nuclear Science and Engineering, H , 285, 1969.
- 40. " Central Reactivity Worth Measurements and Calculations."
Trans. American Nuclear Society, H , 647, 1969.
- 41. " Critical Mass Sensitivity to the Treatment of Heterogeneity Effects in a Large UC Fast Core, Assembly 5 of ZPR-6. " Trans.
American Nuclear Society, H , 718, 1969. ..
- 42. " Computer-Aided Calibration of a Fine Autorod, Nuclear Appl.
and Technology, 2, 342, 1969.
- 43. " Sodium-Void Effects in a 4000-Liter UO2 Core, Assembly 6 of ZPR-6." Trans. American Nuclear Society, H , 270, 1969.
- 44. "Large UC Fast Core, Assembly 5 of ZPR-6." Trans. American Nuclear Society, H , 243, 1968.
- 45. " Sodium-Void Effects in a Large UC Fast Core." Trans.
American Nuclear Society, H 244, 1968.
- 46. " Heterogeneity Effects in Large UC Fast Core." Trans.
American Nuclear Society, H , 245, 1968.
- 47. "A 4000-Liter UO' Fast Core Assembly 6 of ZPR-6." Trans.
American Nuclear Society, H , 597, 1968.
- 48. " Computer Calibration of e Fine Autorod. " Trans. American Nuclear Society, H ,566, 1968.
- 49. " Flux Intrastructure in a Large, Plate-Type Heterogeneous UO2 Fast Core." Trans. American Nuclear Society, H , 598, 1968.
- 50. " Zoned-Core Concepts." Trans. American Nuclear Society, M ,
270, 1967.
l R.A. Karam Page 11
- 51. " Measurement of the Spatial Distribution of the Importance of Fission Neutrons in Fast Reactors." Trans. American Nuclear Society, 1, 490, 1966.
- 52. " Measured Sodium-Void Coefficient and Fission Ratios in a Large Zoned Fast Reactor." Trans. American Nuclear Society, 1, 487, 1966.
- 53. " Comparison of Measured and Calculated Worths of various Materials in a Zoned Fast Assembly." Trans. American Nuclear Society, 1, 232, 1966.
- 54. " Measured and Calculated Flux Distributions in a Zoned Fast Reactor." Trans. American Nuclear Society, 1, 229, 1966.
- 55. " Analysis of the Die-Away. of Prompt Neutrons." Trans.
American Nuclear Society, H , 593, 1967.
- 56. " Spatial Dependence of Prompt Neutron Chains in Re lected Reactors." Trans. American Nuclear Society, 1, 225, 1965.
- 57. "An Experimental Study of X-Ray 'Attentuation of Polyethylene = Lead Shields. " International Journal of Applied Radiation'and Isotopes, H , 529, 1964 with J. Wethington.
- 58. " Measurement of Rossi- in -Reflected Reactors." Trans.
American Nuclear Society, 2, 283, 1964.
- 59. " Measurement of and Power Calibration of Fast Reactor." !
Trans. American Nuclear Society, 2, 248, 1964. I
- 60. " Neutron Decay Spectrometer." Review of Scientific Instruments, H , 600, 1964, with T. F. Parkinson.
l l
- 61. " Spectrum Measurement with Neutron Decay Spectrometer." !
Trans. American Nuclear Society, 1, 259, 1963. I 6 2,, "The Resonance Adsorption Integral of Rhenium. " Conf. Neutron Cross Section, 1, CONF-660303, 171, 1966.
- 63. "
An Experimental Study of Polyethylene-Lead Shields. " Trans.
4 American Nuclear Society, 2, 221. 1060. j TECHNICAL REPORTS
- 1. A 4000-Liter UO 2 Fast Core, Assembly 6 of EPR-6, Argonne National Laboratory Rept. No. ANL-7410, 75, 1969. !
1 3 , , . ,,e-,.3 ,,,, _.
l 1
e R.A. Karam Page 12
- 2. Sodium-Void Effects in a Large UO 2 Fast Core, EPR-6, Assembly 6, ibid., p. 125.
- 3. Heterogeneity Effects in a Large UO2 Fast Core, EPR-6, Assembly 6, ibid., p. 133.
- 4. Measured Physics Parameters in a Large UC Fast Core, Assembly 5 of EPR-6, Argonne National Laboratory Rept. No. ANL-7310, 167, 1968.
1
- 5. Two-Group Space Dependent Kinetics in Reflected Reactors, ibid., p. 480.
- 6. Physics Measurements in Tungsten-Based Fast Reactors, Argonne National Laboratory Report No. ANL-7007, 1967.
- 7. EPR-9 Assemblies No. 6-9 Critical Experiments, Argonne National Laboratory Report No. ANL-7208, 1967. ~
- 8. Measured Physics Parameters in a Zoned Fast UC Core, Assembly 4z, Argonne National Laboratory Report No. ANL-7281, 1966.
- 9. Experimental Verification of Reactor Physics Parameters of Zoned Cores, Intern. Conf. on Fast Critical Expts. and Their Analysis, ANL-7329, 403, 1966. I
- 10. Zoned Core Simulating a 2600-Liter Carbide Fast Core, Argonne National Laboratory Report No. ANL-7110, 114, 1965.
- 11. Note on Rossi- in Reflected Fast Reactors, ibid., p.
172.
- 12. Mn-55 and Co-59 Resonance Detectors, ibid., p. 293. I
- 13. Solid State Neutron Spectrometer, ibid., p. 300. I
- 14. Spatial Dependence of Prompt Neutron Chains, ikid., p. 330. I
- 15. A Statistical Method for the Measurement of .re. , Argonne National Laboratory Report No. ANL-7010, 188, 1965.
- 16. Analysis of Fast Neutron Spectrum Measurement by Magnetic Analysis of Charged Particles Produced by Neutron Interactions, ikid., p. 190.
- 17. Analysis for Large Fast Critical Assemblies, Argonne National Laboratory Report No. ANL-6271, 1966. l l
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O R.A. Karam Page 13
- 18. Physics Parameters in Large Dilute UC Cores, Intern. Conf. on Fast Critical Experiments and Their Analysis, ANL-7320, 231, 1966.
- 19. Suspended-Bed Reactor Prelianinary Design - U233-Th232 Cycle, A report prepared for the U. S. Energy Research and Development Administration under contract No. E(40-1)-5263, May, 1977.
- 20. Time-Dependent Beta-Delayed Neutron Yields and Generalized Z Model for Fission Yield Prediction, Lawrence Livermore Laboratory Report No. UCRL-84249, 1980.
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