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:.   /W10
:. /W10 00CKElED USNRC RESUME i
! *'                                                                                                  00CKElED
95 33[ 18. Pi2 :26 MAME:
:*                                                                                                      USNRC
Ratib A. Karam, Ph. D.
,                                                                  RESUME i
0FFICE OF SECPETARY e
MAME:
ADDRESS:
95 33[ 18 . Pi2 :26 Ratib A. Karam, Ph. D.
DCCKETiNG & SERVICE BRANCH OFFICE RESIDENCE I
;                                                                                              0FFICE OF SECPETARY e               ADDRESS:                                                                       DCCKETiNG & SERVICE
Neely Nuclear Research Center 6133 Kings Mountain Court i
:                                              .                                                        BRANCH
Georgia Institute of Technology Stone Mountain, GA 30087 l
;                                      OFFICE                                             RESIDENCE                             !
900 Atlantic Drive, N. W.
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                                                                                         ,
Telephone (770) 564'2983 Atlanta, GA 30332 i
l                                                                                                                               '
Telephone: (404) 894-3620 l
!              EDUCATION:
EDUCATION:
Ph. D.,   Nuclear Engineering, University of Florida, 1963 M. S.,   Nuclear Engineering, University of Florida, 1960
Ph.
!                                  B. S.,   Chemical Engineering, University of Florida, 1.958 i
D., Nuclear Engineering, University of Florida, 1963 M.
i
S., Nuclear Engineering, University of Florida, 1960 B.
!              EXPERIENCE AND BACKGROUND:
S., Chemical Engineering, University of Florida, 1.958 i
:                1984 - Present Director, Neelv Nuclear Research Center, Georgia
i EXPERIENCE AND BACKGROUND:
:                                                Institute of     Technology, Atlanta, GA 30332.
1984 - Present Director, Neelv Nuclear Research Center, Georgia Institute of Technology,
Accomplished the following
: Atlanta, GA 30332.
:                                      o        Developed   and   obtained         USNRC     approval       for     an       l
Accomplished the following o
{                                                 Emergency Preparedness Plan for the 5 MW Georgia                               !
Developed and obtained USNRC approval for an
l                                                Tech Researen Reactor (GTRR).                                                 'l I
{
l
Emergency Preparedness Plan for the 5 MW Georgia l
;                                      o        Developed a plan and obtained USNRC approval for dismantlement and decommissioning of the Georgia Tech AGN-201       reactor.           Decommissioning             was         ;
Tech Researen Reactor (GTRR).
completed in 1986.
'l I
o         Coordinated in record time, i.e., 8 months, the planning,     procedure             writing,           procedure             ;
l o
implementation and personnel training / retraining                             i for.the GTRR restart program.
Developed a plan and obtained USNRC approval for dismantlement and decommissioning of the Georgia Tech AGN-201 reactor.
o         Increased GTRR program funding to the levels needed                             !
Decommissioning was completed in 1986.
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.
o Coordinated in record time, i.e.,
                                        =
8 months, the
NUCLEAR REGULATORY COMMISSION DocM No. 6"o.- / (, o - 6A3     EXHIBIT NO. N
: planning, procedure
                                                          .            In the rnattw of M       MA''
: writing, procedure implementation and personnel training / retraining i
9608070241 960624                                                O staff g(pplicant D intervenor D other PDR             ADOCK.05000160                                 a1dentified ETReceived O Rejected     Reporter b_) C W Q                                    PDR        '
for.the GTRR restart program.
De 6/0//9 4         witness   MAA                     J
o Increased GTRR program funding to the levels needed to more than cover expenses from 1983 - 1996.
o Restructured the Georgia Tech Radiation Safety Office and built it on a foundation of technical excellence governed by
: detailed, written procedures.
NUCLEAR REGULATORY COMMISSION
=
DocM No. 6"o.- / (, o - 6A3 EXHIBIT NO.
N 9608070241 960624 In the rnattw of M MA''
O staff g(pplicant D intervenor D other PDR ADOCK.05000160 Q
PDR a1dentified ETReceived O Rejected Reporter b_) C W De 6/0//9 4 witness MAA J


ll                                                                             }
ll
* i
}
      . R. A. Karam
i R. A. Karam Page 2 o
* Page 2 o     Restructured     reactor   operating     personnel   and redirected the " operational culture" from one of
Restructured reactor operating personnel and redirected the " operational culture" from one of casual informality to one governed by written,
* casual informality to one governed by written,
. approved procedures.
                      . approved procedures. Sensitivity training to USNRC regulations and requirements was strongly featured.
Sensitivity training to USNRC regulations and requirements was strongly featured.
i o   wrote proposals and directed research activities             ;
i o
with a volume of $11 million dollars.
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         !
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.
the Department of Energy.                                   -
a 1972 - Present Professor of Nuclear Encineerina and Health
a
{
!      1972 - Present Professor of Nuclear Encineerina and Health                 {
j Physics, Georgia Institute of Technology, Atlanta, l
j                       Physics, Georgia Institute of Technology, Atlanta,         !
GA 30332.
l                      GA 30332. Accomplishments include the followings           i 2
Accomplishments include the followings i
o    Originated and taught the following courses:               l
2 Originated and taught the following courses:
;                          NE 6201 Advanced Reactor Physics I                     :
l o
,                            NE 6202 Advanced Reactor Physics II .-                '
NE 6201 Advanced Reactor Physics I NE 6202 Advanced Reactor Physics II NE 6235 Reactor Safety NE 6237 Fast Reactors j
!'                          NE 6235   Reactor Safety NE 6237   Fast Reactors                               ;
NE 6205 Reactor Laboratory 1
j                            NE 6205   Reactor Laboratory 1
o Taught the following courses:
o   Taught the following courses:
NE 4201 Reactor Physics I NE 4202 Reactor Physics II NE 4205 Reactor Laboratory NE 6260 Radiation Shielding i
NE 4201 Reactor Physics I
4 NE 6229 Reactor Applied Theory
;                          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
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
L l
;                o    Supervised 12 Ph. D.     students and numerous M. S.
o Coordinated graduate curriculum for the School of j
I                     candidates.
i Nuclear Engineering for 10 years.
!                o   Edited the following books:
G o
: 1.   " Energy and the Environment       -
Supervised 12 Ph.
Cost Benefit Analysis." Pergamon Press, 1975, with K. Z.
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.
Morgan.
: 2.   " Environmental     Impact   of     Nuclear   Power Plants."   Pergamon Press, 1975.
2.
: 3.   " Advanced   Reactors:     Physics, Design and 1                         Economics."     Pergamon Press, 1974, with J.
" Environmental Impact of Nuclear Power Plants."
j                 ,        Kallfelz.
Pergamon Press, 1975.
3.
" Advanced Reactors:
: Physics, Design and 1
Economics."
Pergamon Press, 1974, with J.
j Kallfelz.
1 i
1 i
i i
i i
b
b


1 R. A. Karam Page 3                                                                                   i l
1 R. A. Karam Page 3 i
: 4.     " Societal Cost of Nuclear and Other Energy                         j Alternatives." Pergamon Press, 1981, with L.                         I Weaver.                                                             ;
4.
: 5.     " Anticipated   and Abnormal           Transients           in   l Nuclear Power Plants."           Two volumes, ANS,                   l 1987.                                                               l i
" Societal Cost of Nuclear and Other Energy j
o Research activities included: Doppler Broadening; perturbation theory; neutron transport; anharmonic effects on crystalline binding and effects on                             :
Alternatives."
reactor parameters; advanced reactor concepts based on metallic fuels; cross section generation; fuel cycles; and reactor safety.
Pergamon Press, 1981, with L.
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.
I Weaver.
o   Developed measuring techniques for small reactivity changes and flux profiles. '
5.
o   Developed     analytical   methods to handle exact perturbation theory for situations where severe
" Anticipated and Abnormal Transients in Nuclear Power Plants."
                  - flux depressions existed as a function of space and energy.
Two volumes, ANS, 1987.
o   Managed the zero power reactor VI program for LMFBR development.
i o
o   Participated in the development of the fast neutron                         ;
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.
dosimeter.                                                                 '
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.
o   Developed methods for measuring delayed neutron
Argonne National Laboratory.
,                  emission-from Th-232 to Cf-252.
Achievements included the followings o
i o   Written safety analysis reports for the EPR-VI assemblies.
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 1
  . R. A. Karam Page 4 i
l R. A. Karam Page 4 i
o   Dr. Karam is a consultant to several national and international organizations   . He is also a fellow   !
o Dr. Karam is a consultant to several national and international organizations He is also a fellow in the American Nuclear Society.
in the American Nuclear Society. He published more than 80 technical papers.
He published more than 80 technical papers.
1972 - Present Consultant to various organizations, some of which     ,
1972 - Present Consultant to various organizations, some of which are listed below:
are listed below:                                       )
)
l
l 1.
: 1. Georgia Power Company, Reactor Safety Keview     ]
Georgia Power Company, Reactor Safety Keview
]
Subcommittee, 1985 to present.
Subcommittee, 1985 to present.
: 2. Southern Company, technical support, 1985     -
2.
present.
Southern Company, technical support, 1985 present.
: 3. Veterans Administration, evaluate programs of nuclear reactor at Omaha, Nebraska, 1986 -
3.
present.
Veterans Administration, evaluate programs of nuclear reactor at Omaha, Nebraska, 1986 present.
: 4. Nuclear Assurance Corporation,       design of transport and storage casks, 1983 - present.
4.
: 5. Department of Energy,     evaluation   of   LMR designs, 1985 - 1987.
Nuclear Assurance Corporation, design of transport and storage casks, 1983 - present.
: 6. Batelle Pacific Northwest, dose release in H 2 O from spent fuel.
5.
: 7. Japan   Atomic   Energy Research   Institute, program evaluation, 1974
Department of
: 8. Brazil Institute of de Energia Atomica, set up Reactor Physics Program, 1973 - 1974.
: Energy, evaluation of LMR designs, 1985 - 1987.
: 9. Wells Fargo, develop procedures for handling radioactive substances, 1975 - 1976.
6.
: 10. Board of Directors, Nuclear Services, 1972 -
Batelle Pacific Northwest, dose release in H O 2
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.
1974.
: 11. Board of Directors, Energy Technology, Inc.,
11.
Board of Directors, Energy Technology, Inc.,
1974 - 1976.
1974 - 1976.
: 12. Oak Ridge Associated Universities,         Cross Section Evaluation, 1972 - 1982.
12.
Oak Ridge Associated Universities, Cross Section Evaluation, 1972 - 1982.
O e
O e


R.A. Karam Page 5 HONORS:
R.A. Karam Page 5 HONORS:
o     Fellow, American Nuclear Society, cited for outstanding contributions in reactor physics and nuclear engineering education.
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 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 -
o
1979 o   Member, Nuclear Safeguard Committee, 1972 - 1978 o   Member, Dean's Planning Committee, 1982 - 1983     ,
: Chairman, Nuclear Engineering Schools's Graduate Curriculum Committee, 1972 - 1982 o
o    Chairman, Ph. D. Preliminary Examination Committee,1983
Chairman, School's Program and Tenure Committee, 1977 -
                - 1984 o   Member, Dean's Tenure and Promotion Committee, 1983     -
1979 o
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
Member, Nuclear Safeguard Committee, 1972 - 1978 o
                - present AT AMERICAN NUCLEAR SOCIETY:
Member, Dean's Planning Committee, 1982 - 1983 o
o     Chairman, Atlanta Section of ANS, 1977 - 1979 o     Secretary, Reactor Physics Division of ANS, 1978 - 1980
Chairman, Ph. D. Preliminary Examination Committee,1983
        ,  o    Executive Committee, Reactor Physics Division, ANS,1980         ,
- 1984 o
                - 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
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


p       -
p v..
                                                . v..
i R.A. Karam Page 6 o-Member, Technical Program Committee, Anticipated ' and Abnormal Transients in LWR's, 1983
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
Assistant Chairman, National ANS Annual Meeting, June, o
o    Candidate for Board of Directors,       American Nuclear         '
i 1980 l
Society, 1985                                                   !
i o
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:
Candidate for Board of Directors, American Nuclear Society, 1985 Chairman, Glenn Murphy Award Committee, American Society o
o   " Basic Requirements for Standards in Reactor Physics,"
for Engineering and Education o
ANS, 1974 o   " Generation of Effective Cross Sections," International Conference held at Brookhaven National Laboratory, 1975 i
Member, ANS Award Committee, 1985 - present Chairman, Atlanta Section Honors and Awards Committee, o
o    "The Thorium Cycle Potential in a Breeder Economy," ANS,           '
1985 o
1977                                 -
Chairman, Technical Program Committee, Anticipated and Abnormal Transients in Nuclear Power Plants, Topical held in April, 1987 INVITED LECTURES:
o    "The Pressure Vesuel Question," ANS, 1977                       !
o
o    " Denatured Breeders," ANS, 1981 o   "The Effective Delays Neutron Fractions         and     the     i Reactivity Coefficient," ANS, 1982
" Basic Requirements for Standards in Reactor Physics,"
      ,  o    " Comparison of Measured and Calculated Delayed Neutron Yields," American Chemical Society, March 1982 o   " Heterogeneity and Anisotropy Effects on Group Cross
ANS, 1974 o
,              Sections," Brc khaven National Laboratory, 1982 o    "The U-233/U-238 LMFBR Operating on an Extended Burn-up Cycle,"   National Science Foundation, 1982
" Generation of Effective Cross Sections," International Conference held at Brookhaven National Laboratory, 1975 i
                                - - -      ,-                w      -me     - 1
"The Thorium Cycle Potential in a Breeder Economy," ANS, o
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
" Comparison of Measured and Calculated Delayed Neutron o
Yields," American Chemical Society, March 1982 o
" Heterogeneity and Anisotropy Effects on Group Cross Sections," Brc khaven National Laboratory, 1982 "The U-233/U-238 LMFBR Operating on an Extended Burn-up o
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
R.A. Karam Page 7 o
: 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.
" Safety Considerration of Thorium-Based Liquid Metal Reactors" o
: 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.                                                           '
International Conference on Waste Disposal and Radiation Problems, American Nuclear Society, 1979 PAPERS PUBLISHED IN REFEREED SCIENTIFIC JOURNALS 1.
: 3.   "A Simple and Accurate Numerical Method for Evaluation of Resonance Line Shape. " Annals Nuclear Energy, Vol.18, No. 5, pp. 49-257, 1991.
" Conceptual Design for an Epithermal Neutron Beam Facility at the Georgia Tech Research Reactor."
: 4.   "On the Evaluation of the Cubic, Quartic and Thermal Phonon Shifts and Cubic Phonon Widths." Annals Nuclear Energy, Vol.
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.
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.
5.
: 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.
"Anharmonic Effects on the Resonance Line Shape of U23e in UO. "
: 7.   " Metallic Fuel for the Na-Cooled Reactors with an Extended 4
Annals Nuclear Energy, Vol. 18, No.
Burn-up Cycle."     Annals of Nuclear Energy, H , 137, 1985.
8, pp. 427-442, 2
8.. " Space, Energy and Anisotropy Effects on U-238 Effective
1991.
!        Capture Cross Section in the Resonance Region."             Annals of Nuclear Energy, H , 41, 1984, with B. Meftah.
6.
: 9.   " Space,     Energy   and Anisotropy Effects           on   Diffusion Coefficients in the Resonance Region. "         Annals of Nuclear Energy, H , 41, 1984, with B. Meftah.
" Analysis of Partial-Refueling, Ultra-Long Life Core Using Metallic Fuel for 1000 MW(e) LMFBRS. " Nuclear Technology, 86, pp. 49-59, July 1989.
: 10. " Interface Effects in Multi-Region Reactors."             Annals of Nuclear Energy, H , 33, 1984, with B. Meftah.
7.
" Metallic Fuel for the Na-Cooled Reactors with an Extended Burn-up Cycle."
Annals of Nuclear Energy, H, 137, 1985.
4 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.


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y O
R.A. Karam Page 8
R.A. Karam Page 8 11.
,    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
" Metallic Combinations of Pu-Th and U232-Th or Pu-Th and U:23 22' U
Technology, 51, 535, 1982.
as Possible Alternatives to (Pu-U)O in LMFBR's." Nuclear 2
!      12. " Denatured Breeders . " Annals of Nuclear Energy, 1, 115, 1981, 1 i
i Technology, 51, 535, 1982.
with C. C. Lee.
12.
j     13. " Spectral Shift Effects Induced by Doppler Bordering on i
" Denatured Breeders. " Annals of Nuclear Energy, 1, 115, 1981, 1
Reactivity Coefficient. "     Nuclear Science and Engineering,   !
i with C. C. Lee.
;          21, 278, 1981, with A. Alapour.                                 l
j 13.
!      14. " Delay Neutron Yields:     Time Dependent Measurements and a Predictive Model." Physical Rev. C., H , 1113, 1981, with R.
" Spectral Shift Effects Induced by Doppler Bordering on i
;          Waldo.
Reactivity Coefficient. "
1
Nuclear Science and Engineering, 21, 278, 1981, with A. Alapour.
: 15. " Spatial Dependence of Effective Resonance Cross Sections."
14.
.;          Annals of Nuclear Energy, 1, 215, 1981, with B. Meftaty. -
" Delay Neutron Yields:
1 1     16. " Chemical Binding Effects on Resonance Line Shape and Neutron
Time Dependent Measurements and a Predictive Model."
]           Capture Rates." Annals of Nuclear Energy, 1, 255, 1981, with i           H. St. John.
Physical Rev.
: 17. " Measured Delay Neutron Yields."     Trans. American Nuclear Society, H, 879, 1981.
C., H, 1113, 1981, with R.
!      18. " Denatured Breeders."   Invited paper, Trans. American Nuclear
Waldo.
;          Society, H , 535, 1981.
1 15.
I     19. " Effects of Source Anisotropy and Nonuniformity on Resonance i
" Spatial Dependence of Effective Resonance Cross Sections."
Cross Sections in Multiregion Problems."       Trans. American Nuclear Society, M , 664, 1981, with B. Meftah.
Annals of Nuclear Energy, 1, 215, 1981, with B. Meftaty.
: 20. " Denatured Fuels in LMFBR's. " Trans. American Nuclear Society, M , November, 1980, with A. Alapour.
1 1
: 21. " Effects of Resonance Profile Representation on Reactor
16.
.          Integral Parameters."     Trans. American Nuclear Society, M ,
" Chemical Binding Effects on Resonance Line Shape and Neutron
i
]
          . November, 1980.
Capture Rates." Annals of Nuclear Energy, 1, 255, 1981, with i
: 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
H. St. John.
Trans. American Nuclear Society, November 12-16, 1979, with C. I C. Lee.
17.
: 23. " Safety Considerations of Thorium-Based Liquid Metal Fast Breeder Reactors. " International Conference on Waste Disposal and Radiation Problems, 1979, with C. C. Lee.
" 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,
November, 1980.
i 22.
" Optimization and Comparison of the Growth Potential of Metallic Pu-Th and U232-Th with Mixed Pu-U Oxide in LMFBR's."
i Trans. American Nuclear Society, November 12-16, 1979, with C.
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
1 l
4 A
4 A
2
2


g-R.A. Karam Page 9
g-R.A. Karam Page 9 24.
: 24.   " Liquid       Metal Fast Breeder Reactors with Thori un-Based 3           Metallic Fuels." International Conference on Waste Disposal
" Liquid Metal Fast Breeder Reactors with Thori un-Based 3
;        .and Radiation Problems, 1979, with C. C. Lee.
Metallic Fuels."
i
International Conference on Waste Disposal
: 25.   " Breeding Performance of Metallic Pu-Th,               U233-Th , U233-U23e
.and Radiation Problems, 1979, with C. C. Lee.
]           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.
i 25.
l l     26. "The Pressure Vessel Question."                 Trans. American Nuclear Society, H , November, 1977.
" Breeding Performance of Metallic Pu-Th, U233-Th,
4
U233-U e 23
: 27. "The Thorium-U " Cycle as an Alternative to LMFBR's. "
]
2 Trans.
Versus (Pu-U)O Fuels in LMFBR's. " International Symposium on 2
!,          American Nuclear Society, H , November 1977.
l Fast Reactor Physics, IAEA Report No. IAEA-SM-244-60, 1979, i
i     28. "A General Method for Generating Effective Resonance Cross l           Sections         for Heterogeneous Media."         Nuclear Science and l
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. "
Trans.
2 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.
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.
29.
!          Kallfelz and R. A. Karam, eds., Pergamon Press, 1975, with C.
" Spacial Dependence of Broad Group Cross Sections,"
j           Mildrum.
in i
: 30. "On the Discrepancy Between Measured and Calculated Central j           Reactivity Coefficients."           Nuclea.7 Science and Engineering,
Advanced Reactors:
;          H , 201, 1973.
Physics. Desian and Economics,*
j     31. "On the Discrepancy Between Measured and Calculated Central 4
J.
Reactivity' Coefficients."         Trans. Junerican Nuclear Society, j           H, 504, 1972.
M.
l     32. "On the Discrepancy Between Measured and Calculated Reactivity l           Coefficients."           Proc. International Meeting on Fast Reactor
Kallfelz and R. A. Karam, eds., Pergamon Press, 1975, with C.
:          Physics, Tokyo, Japan, 1973.
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."
1 Trans. American Nuclear Society, l b 458, 1972.
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
]
]
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.
Assemblies." Nuclear Science and Engineering, iq, 414, 1970.
I
I
(                       -
!(
                                                ,.    -m,w         -
-m,w


R.A. Karam Page 10
R.A. Karam Page 10 37.
: 37.       " Analysis of Sodium-Void Coefficients."       Trans. American Nuclear Society, M , 284,.1970.
" Analysis of Sodium-Void Coefficients."
: 38.     " Measurements of the Normalization Integral and the Spatial Distribution of the Importance of Fission Neutrons."     Nuclear Science and Engineering, H , 192, 1969.
Trans. American Nuclear Society, M, 284,.1970.
: 39.       " Analysis of the Die-Away of Prompt Neutrons with Two-Group Time Dependent Diffusion Equations in Reflected Reactors. "
38.
Nuclear Science and Engineering, H , 285, 1969.
" Measurements of the Normalization Integral and the Spatial Distribution of the Importance of Fission Neutrons."
: 40.       " Central Reactivity Worth Measurements and Calculations."
Nuclear Science and Engineering, H, 192, 1969.
Trans. American Nuclear Society, H , 647, 1969.
39.
: 41.       " Critical Mass Sensitivity to the Treatment of Heterogeneity Effects in a Large UC Fast Core, Assembly 5 of ZPR-6. " Trans.
" Analysis of the Die-Away of Prompt Neutrons with Two-Group Time Dependent Diffusion Equations in Reflected Reactors. "
American Nuclear Society, H , 718, 1969.                ..
Nuclear Science and Engineering, H, 285, 1969.
: 42.       " Computer-Aided Calibration of a Fine Autorod,   Nuclear Appl.
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.
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.
43.
: 44.       "Large UC Fast Core, Assembly 5 of ZPR-6."       Trans. American Nuclear Society, H , 243, 1968.
" Sodium-Void Effects in a 4000-Liter UO Core, Assembly 6 of 2
: 45.       " Sodium-Void Effects in a Large UC Fast Core."             Trans.
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.
American Nuclear Society, H 244, 1968.
: 46.       " Heterogeneity Effects in Large UC Fast Core."             Trans.
46.
American Nuclear Society, H , 245, 1968.
" Heterogeneity Effects in Large UC Fast Core."
: 47.       "A 4000-Liter UO' Fast Core Assembly 6 of ZPR-6."         Trans.
Trans.
American Nuclear Society, H , 597, 1968.
American Nuclear Society, H, 245, 1968.
: 48.       " Computer Calibration of e Fine Autorod. "     Trans. American Nuclear Society, H ,566, 1968.
47.
: 49.       " Flux Intrastructure in a Large, Plate-Type Heterogeneous UO2 Fast Core." Trans. American Nuclear Society, H , 598, 1968.
"A 4000-Liter UO' Fast Core Assembly 6 of ZPR-6."
: 50.       " Zoned-Core Concepts."     Trans. American Nuclear Society, M ,
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.
270, 1967.


l R.A. Karam Page 11
R.A. Karam Page 11 51.
: 51.   " Measurement of the Spatial Distribution of the Importance of Fission Neutrons in Fast Reactors." Trans. American Nuclear Society, 1, 490, 1966.
" Measurement of the Spatial Distribution of the Importance of Fission Neutrons in Fast Reactors."
: 52.   " Measured Sodium-Void Coefficient and Fission Ratios in a Large Zoned Fast Reactor."                     Trans. American Nuclear Society, 1, 487, 1966.
Trans. American Nuclear Society, 1, 490, 1966.
: 53.   " Comparison of Measured and Calculated Worths of various Materials in a Zoned Fast Assembly." Trans. American Nuclear Society, 1, 232, 1966.
52.
: 54.   " Measured and Calculated Flux Distributions in a Zoned Fast Reactor."               Trans. American Nuclear Society, 1, 229, 1966.
" Measured Sodium-Void Coefficient and Fission Ratios in a Large Zoned Fast Reactor."
: 55.   " Analysis of the Die-Away. of Prompt Neutrons."                                 Trans.
Trans. American Nuclear Society, 1, 487, 1966.
American Nuclear Society, H , 593, 1967.
53.
: 56.   " Spatial Dependence of Prompt Neutron Chains in Re lected Reactors."               Trans. American Nuclear Society,               1, 225, 1965.
" Comparison of Measured and Calculated Worths of various Materials in a Zoned Fast Assembly." Trans. American Nuclear Society, 1, 232, 1966.
: 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.
54.
: 58.   " Measurement of Rossi- in -Reflected Reactors."                                 Trans.
" 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.
American Nuclear Society, 2, 283, 1964.
: 59.   " Measurement of and Power Calibration of Fast Reactor."                                         !
59.
Trans. American Nuclear Society, 2, 248, 1964.                                                   I
" Measurement of and Power Calibration of Fast Reactor."
: 60.   " Neutron               Decay       Spectrometer."           Review of Scientific Instruments, H , 600, 1964, with T. F. Parkinson.
Trans. American Nuclear Society, 2, 248, 1964.
l l
I 60.
: 61.   " Spectrum               Measurement with Neutron Decay Spectrometer."                           !
" 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.
Review of Scientific Instruments, H, 600, 1964, with T. F. Parkinson.
: 63.   "
l 61.
" Spectrum Measurement with Neutron Decay Spectrometer."
Trans. American Nuclear Society, 1, 259, 1963.
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.
An Experimental Study of Polyethylene-Lead Shields. " Trans.
4               American Nuclear Society, 2, 221. 1060.                                                           j TECHNICAL REPORTS
4 American Nuclear Society, 2, 221. 1060.
: 1. A 4000-Liter UO 2 Fast Core, Assembly 6 of EPR-6, Argonne National Laboratory Rept. No. ANL-7410, 75, 1969.                                                 !
j TECHNICAL REPORTS 2
1 3 , , .                  ,,e-,.3       ,,,,  _.
1.
A 4000-Liter UO Fast Core, Assembly 6 of EPR-6, Argonne National Laboratory Rept. No. ANL-7410, 75, 1969.
1 3
,,e-,.3


l 1
l e
e R.A. Karam Page 12
R.A. Karam Page 12 2.
: 2. Sodium-Void Effects in a Large UO 2 Fast Core, EPR-6, Assembly 6,   ibid., p. 125.
Sodium-Void Effects in a Large UO Fast Core, EPR-6, Assembly 2
: 3. Heterogeneity Effects in a Large UO2        Fast Core,     EPR-6, Assembly 6, ibid., p. 133.
6, ibid., p. 125.
: 4. Measured Physics Parameters in a Large UC Fast Core, Assembly 5 of EPR-6, Argonne National Laboratory Rept. No. ANL-7310, 167, 1968.
3.
1
Heterogeneity Effects in a Large UO Fast Core, EPR-6, 2
: 5. Two-Group Space Dependent Kinetics in Reflected Reactors, ibid., p. 480.
Assembly 6, ibid., p. 133.
: 6. Physics Measurements in Tungsten-Based Fast Reactors, Argonne National Laboratory Report No. ANL-7007, 1967.
4.
: 7. EPR-9 Assemblies No. 6-9 Critical Experiments,       Argonne National Laboratory Report No. ANL-7208, 1967.           ~
Measured Physics Parameters in a Large UC Fast Core, Assembly 5 of EPR-6, Argonne National Laboratory Rept. No. ANL-7310, 167, 1968.
: 8. Measured Physics Parameters in a Zoned Fast UC Core, Assembly 4z,   Argonne National Laboratory Report No. ANL-7281, 1966.
5.
: 9. Experimental Verification of Reactor Physics Parameters of Zoned Cores, Intern. Conf. on Fast Critical Expts. and Their Analysis, ANL-7329, 403, 1966.                                   I
Two-Group Space Dependent Kinetics in Reflected Reactors, ibid., p. 480.
: 10. Zoned Core Simulating a 2600-Liter Carbide Fast Core, Argonne National Laboratory Report No. ANL-7110, 114, 1965.
6.
: 11. Note on Rossi-   in Reflected Fast Reactors, ibid., p.
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.
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.
172.
: 12. Mn-55 and Co-59 Resonance Detectors,   ibid., p. 293.           I
12.
: 13. Solid State Neutron Spectrometer,   ibid., p. 300.               I
Mn-55 and Co-59 Resonance Detectors, ibid., p. 293.
: 14. Spatial Dependence of Prompt Neutron Chains, ikid., p. 330.       I
13.
: 15. A Statistical Method for the Measurement of       .re. , Argonne National Laboratory Report No. ANL-7010, 188, 1965.
Solid State Neutron Spectrometer, ibid., p. 300.
: 16. Analysis of Fast Neutron Spectrum Measurement by Magnetic Analysis   of   Charged   Particles   Produced   by     Neutron Interactions,   ikid., p. 190.
14.
: 17. Analysis for Large Fast Critical Assemblies, Argonne National Laboratory Report No. ANL-6271, 1966.                             l l
Spatial Dependence of Prompt Neutron Chains, ikid., p. 330.
I
15.
A Statistical Method for the Measurement of Argonne
.re.,
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


O R.A. Karam Page 13
O R.A. Karam Page 13 18.
: 18. Physics Parameters in Large Dilute UC Cores, Intern. Conf. on Fast Critical Experiments and Their Analysis, ANL-7320, 231, 1966.
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.
19.
: 20. Time-Dependent Beta-Delayed Neutron Yields and Generalized Z Model   for Fission Yield Prediction,       Lawrence Livermore Laboratory Report No. UCRL-84249, 1980.
Suspended-Bed Reactor Prelianinary Design - U233-Th232 Cycle, A
0 l}}
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.
0
.}}

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Text

..

L

. /W10 00CKElED USNRC RESUME i

95 33[ 18. Pi2 :26 MAME:

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

{

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.

o Restructured the Georgia Tech Radiation Safety Office and built it on a foundation of technical excellence governed by

detailed, written procedures.

NUCLEAR REGULATORY COMMISSION

=

DocM No. 6"o.- / (, o - 6A3 EXHIBIT NO.

N 9608070241 960624 In the rnattw of M MA

O staff g(pplicant D intervenor D other PDR ADOCK.05000160 Q

PDR a1dentified ETReceived O Rejected Reporter b_) C W De 6/0//9 4 witness MAA J

ll

}

i 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 Originated and taught the following courses:

l o

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 NE 6260 Radiation Shielding i

4 NE 6229 Reactor Applied Theory

~

j NE 3211 Introduction to Nuclear Engineering i

L l

o Coordinated graduate curriculum for the School of j

i Nuclear Engineering for 10 years.

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

4.

" Societal Cost of Nuclear and Other Energy j

Alternatives."

Pergamon Press, 1981, with L.

I Weaver.

5.

" Anticipated and Abnormal Transients in Nuclear Power Plants."

Two volumes, ANS, 1987.

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 O 2

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

p v..

i R.A. Karam Page 6 o-Member, Technical Program Committee, Anticipated ' and Abnormal Transients in LWR's, 1983

)

Assistant Chairman, National ANS Annual Meeting, June, o

i 1980 l

i o

Candidate for Board of Directors, American Nuclear Society, 1985 Chairman, Glenn Murphy Award Committee, American Society o

for Engineering and Education o

Member, ANS Award Committee, 1985 - present Chairman, Atlanta Section Honors and Awards Committee, o

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

"The Thorium Cycle Potential in a Breeder Economy," ANS, o

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

" Comparison of Measured and Calculated Delayed Neutron o

Yields," American Chemical Society, March 1982 o

" Heterogeneity and Anisotropy Effects on Group Cross Sections," Brc khaven National Laboratory, 1982 "The U-233/U-238 LMFBR Operating on an Extended Burn-up o

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 UO. "

Annals Nuclear Energy, Vol. 18, No.

8, pp. 427-442, 2

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 Burn-up Cycle."

Annals of Nuclear Energy, H, 137, 1985.

4 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 22' U

as Possible Alternatives to (Pu-U)O in LMFBR's." Nuclear 2

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.

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,

November, 1980.

i 22.

" Optimization and Comparison of the Growth Potential of Metallic Pu-Th and U232-Th with Mixed Pu-U Oxide in LMFBR's."

i Trans. American Nuclear Society, November 12-16, 1979, with C.

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-U e 23

]

Versus (Pu-U)O Fuels in LMFBR's. " International Symposium on 2

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. "

Trans.

2 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."

1 Trans. American Nuclear Society, l b 458, 1972.

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 UO Core, Assembly 6 of 2

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.

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 61.

" Spectrum Measurement with Neutron Decay Spectrometer."

Trans. American Nuclear Society, 1, 259, 1963.

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 2

1.

A 4000-Liter UO Fast Core, Assembly 6 of EPR-6, Argonne National Laboratory Rept. No. ANL-7410, 75, 1969.

1 3

,,e-,.3

l e

R.A. Karam Page 12 2.

Sodium-Void Effects in a Large UO Fast Core, EPR-6, Assembly 2

6, ibid., p. 125.

3.

Heterogeneity Effects in a Large UO Fast Core, EPR-6, 2

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.

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.

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.

13.

Solid State Neutron Spectrometer, ibid., p. 300.

14.

Spatial Dependence of Prompt Neutron Chains, ikid., p. 330.

15.

A Statistical Method for the Measurement of Argonne

.re.,

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

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.

0

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