Dr. Dan Meneley

Adjunct Professor
Faculty of Energy Systems and Nuclear Science
UOIT
2000 Simcoe Street North
Oshawa, ON L1H 7K4
Office: UA 3073
e-mail: Daniel.Meneley@uoit.ca
Tel: 905.721.8668 ext. 3437
Fax: 905.721.3046

Education

Ph.D. Imperial College, University of London, England Reactor Physics specialty in the Department of Mechanical Engineering, 1963
Diploma of Imperial College, University of London, England,1960 (Nuclear Engineering)
B.E.University of Saskatchewan, Saskatoon, Canada Civil Engineering (with Great Distinction) 1958

Courses Taught

Risk Analysis
Nuclear Plant Safety Design
Reactor Physics
Reactor Safety

Research Areas

Systems Analysis for Nuclear Energy Supply
Principles and Practice of Nuclear Safety
Educational Technology

Selected Publications:

Stephen Yu,Jerry Hopwood, and Dan Meneley, "Reacteurs a eau lourde", Techniques de l'Ingenieur, Journaldu Genie Nucleaire, BN3210, Oct. 2000

D.A. Meneley& Associates Ltd., "CANDU Electric Energy System - an Outline of Design & Safety Characteristics", May 1993

D.A. Meneley, "CANDU Energy System Design and Safety - a Status Review", Journal of Korea Society for Energy Engineering, Vol. 2, No. 2, pp 171-178, Jan 1993

A.F. Shalabi, D.A. Meneley, "Modelling of Delayed Hydride Crack Initiation", Journal of Engineering Materials & Technology June, 1991)

A.F. Shalabi, D.A. Meneley, "Initiation of Delayed Hydride Cracking in Zirconium -2.5 wt.%Niobium", Journal of Nuclear Materials, 173, 313-320, 1990

J.E. Lafortune, D.A. Meneley, "Natural Convection in a Vertical Cylinder: Comparison ofCOMMIX-1A Predictions with Experiment", Int'l Journal of Heat and Mass Transfer, 33, No. 3 Mar 1990

P.S.L. Yuen, S. Banerjee, D.A. Meneley, "Measurements of Two-Phase Void Fraction by a Neutron Scattering Technique with Portable Neutron Sources: The Effect of Incident Neutron Energy Spectrum", Int'l Journal of Multiphase Flow, 14,No. 4 July, 1988

E. Hussein, D.A.Meneley, S. Banerjee, "On the Solution of the Inverse Problem of Radiation Scattering Imaging", Nuclear Science & Engineering, Vol. 92,pp. 341-349, 1986

E. Hussein, D.A.Meneley, S. Banerjee, "Single-Exposure Neutron Tomography of Two-Phase Flow", Int. J. Multiphase Flow, 12, No. 1, 1-34, 1986

S. Banerjee, E.Hussein, D.A. Meneley, "Simulation of Neutron Scattering Method for Measuring Void Fraction in Two-Phase Flow", Nuclear Eng. & Design 53:393-405, 1979

J. Hoover, G.K.Leaf, D.A. Meneley, "Fuel Cycle Analysis System, REBUS", NSE 45:52-65, 1971

E.L. Fuller, D.A.Meneley, D.L. Hetrick, "Weighted-Residual Methods in Space-Dependent Reactor Dynamics", NSE 40:206-23 1970

K.O. Ott, D.A.Meneley, "Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics", NSE 36: 402-11, 1969

D.R. MacFarlane,N. McNeal, D.A. Meneley, C.K. Sanathanan, "Sodium Boiling Transients in Oxide-Fuelled Fast Reactors", Nuclear Engineering and Design 1: 411-26, 1968

G.J. Fischer, D.A.Meneley, R.N. Hwang, E.F. Groh, C.E. Till, "Doppler Effect Measurements in Plutonium-Fuelled Fast Power Breeder Reactor Spectra", NSE 25:37-46, 1966

G.J. Fischer, J.R.Folkrod, H.H. Hummel, D.A. Meneley, "Doppler Coefficient Measurements forU-238 in Fast-Reactor Spectra", Nuclear Science & Engineering 18:290-2, 1964

TOPICAL CONFERENCES

H. D. Lightfoot, W. Mannheimer, D.A. Meneley, D. Pendergast, G. S.Stanford, "Nuclear Fission Energy is Inexhaustible", Proceedings of the Climate Change Technology Conference, Engineering Institute of Canada, Ottawa May 2006

D.A. Meneley, "Canada - Nuclear Desalination Technology Status and Future Development Plan", IAEA Inter-regionalNuclear Power Desalination Project, Taejon, May 1999

D.A. Meneley, R.B. Duffey, D.R. Pendergast, "CANDU Co-Generation Opportunities", IAEA Technical Committee Meeting, Beijing, Peoples' Republic of China, April 1999

D.A. Meneley, Chair, Working Group for Key Issue Paper #3, "Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities", IAEA International Symposium, Vienna,June 1997

D.A. Meneley, "Designer'sView of Hydrogen Mitigation" OECD Workshop - Implementation of Hydrogen Mitigation Techniques, Winnipeg, Manitoba, May 1996

P.G. Boczar, P.J.Fehrenbach, D.A. Meneley, "CANDU Fuel Cycle Option in Korea", KAIF/KNS 11thAnnual Conference, Korea, April 1996

D.A. Meneley, "AECL Reactor Development Program" - Advances in HWR, IAEA Conference, Bombay, India, Jan 1996

A.R. Dastur, D.A.Meneley, D.B. Buss, "Thorium Cycle Options in CANDU Reactors" - Global 95Conference, Versailles, France, May 1995

D.A. Meneley, A.R.Dastur, P.J. Fehrenbach, K.H. Talbot, "Synergistic Nuclear Fuel Cycles of the Future" - Global 95 Conference, Versailles, France, May 1995

J.T. Rogers,D.A. Meneley, C. Blahnik, V.G. Snell, S. Nijhawan, "Coolability of Severely Degraded CANDU Cores" - Proc. Seminar of the International Centre for Heat and Mass Transfer, p. 317, Cesme, Turkey,May1995

D.A. Meneley, R.S.Hart, R.A. Olmstead, V.G. Snell, "Heavy Water Reactors - Advances and Challenges" PBNC #9 Conference, Sydney, Australia, Nov. 1993

D.R. Pendergast,D.A. Meneley, "Evolution of CANDU Containment Design" - KAIF 10th Annual Conference, Seoul, Korea, April 1995

A.R. Dastur, D.A.Meneley, R.A. Verrall, P.G. Lucuta, "Annihilation of Plutonium in CANDU Reactors" IAEA Symposium on Plutonium Utilization, Obninsk, Russia Jan 1995

D.A. Meneley, S.K.W.Yu, "CANDU Development Directions", KAIF/KNS International Conference, Seoul, Korea, April 1993

G.L. Brooks, D.A.Meneley "Development Directions for CANDU Reactors", Int'l Conf. on Designand Safety of Advanced Nuclear Power Plants, October 1992

D.A. Meneley, "Reactor Safety in the Next Century", Conf. on Energy Technology Options for the 21^stCentury, McMaster University, Ontario, October 1992

P. Piumsomboon, D.A.Meneley, R. Girard, "Process Fault Verification System" CNS16th Annual Simulation Symposium, Saint John, New Brunswick (August 1991).

D.A. Meneley, "Advanced Canadian Reactors", Lecture notes presented at the Seminar on Nuclear Safety and Advanced Reactors, Universidad Internacional Menendez Pelayo, Valencia, Spain, July 1991

H.O. Tezel, D.A.Meneley, The Dynamic Simulation of a Two-Node Non-Equilibrium 600 MW CANDU Pressurizer System", CNS 14th Annual Simulation Symposium, Whiteshell Nuclear Research Establishment, April 1988

D.A. Meneley, "The Human Chemistry of a Nuclear Program", Proc. Conf. on Water Chemistry and Materials Performance, Canadian Nuclear Society, Toronto, October 1986 (Invited).

D.A. Meneley, "The Use of Operating Experience for Estimating the Future Public Risk from Nuclear Power Plants", Proc. International Symposium on the Total Risk and Benefit Impact of Energy Alternatives, Waterloo, Ontario, May 1986 (Invited).

C. Blahnik, D.W.McKean, D.A. Meneley, J. Skears, N. Yousef, "Principles of Operation of CANDU Multi-Unit Containment Systems", CNS International Conference on Containment Design, Toronto, Ontario, June 1984

D.A. Meneley, "Resolved and Outstanding Issues in Treatment of Source Terms, and What Constitutes Closure?" Proc. Topical Meeting on Fission Product Behaviour and Source Term Research, ANS/ENS/CNS Sponsored, Snowbird, Utah, July 1984 (Invited).

E. Hussein, S.Banerjee, D.A. Meneley, "A New Fast Neutron Scattering Technique for Local Void Fraction Measurement in Two-Phase Flow", Proc. 2nd Topical Meeting on Reactor Thermal Hydraulics, Santa Barbara, California, January 1983

R.A. Brown, D.A. Meneley, "Management of Nuclear Power Plant Safety from Concept to Operation", IAEA Seminar on Safety in Nuclear Power Plant Operation, Vienna, Austria November 1983

W.B. Behnke, P.A. Erkes D.A. Meneley, T. Kawahito, "Current Utility Views on the Water Reactor Nuclear Fuel Cycles", International ENS/ANS Conference on New Directions in Nuclear Energy with Emphasis on Fuel Cycles, Brussels, Belgium, April 1982

D.A. Meneley, W.T. Hancox, "LOCA Consequence Predictions in a CANDU-PHWR", IAEA International Conference on Nuclear Power Experience, Vienna, Austria, September 1982

D.A. Meneley, W.T.Hancox, "CANDU and Public Safety", 94th Annual Congress, Engineering Institute of Canada & Canadian Society for Mechanical Engineering, Calgary, April 1980

D.A. Meneley, "Neutron Kinetics-Status and Future Needs", CNA Symposium on Research Related to the Nuclear Fuel Cycle, Toronto, May 1979

D.A. Meneley, "CANDU-PHW Power Stations", Conference of Societe Francaise d'Energie Nucleaire, Paris, February 1978

D.A. Meneley, "Electrical Energy from CANDU - Here and Now", Proc. 29th Annual Technical Meeting of the Petroleum Society of CIM, Calgary, Alberta, June 1978

D.A. Meneley, "CANDU Systems", Proc. 1976 ASME-ANS Int'l Conf. on Advanced Nuclear Energy Systems, Pittsburgh, PA, March 1976

W.T. Sha, T.A.Daly, A.J. Lindeman, E.L. Fuller, D.A. Meneley, "Two-Dimensional Fast-Reactor Disassembly Analysis with Space-Time Kinetics", CONF-710302(Vol. 1) Proc. Conf. on New Developments in Reactor Mathematics and Applications, Idaho, March 1971

D.A. Meneley, G.K.Leaf, A.J. Lindeman, T.A. Daly, W.T. Sha, "A Kinetics Model for Fast Reactor Analysis in Two Dimensions", Symposium on Dynamics of Nuclear Systems, Tucson, Arizona, March 1970

D.A. Meneley, G.K.Leaf, P.M. Walker, S.H. Kyong, "Generalized Formulation for Fast Reactor Fuel Cycle Studies", CNM-R-2 (Vol.3), Proc. Int. Conf. on Research Reactor Utilization and Reactor Mathematics, Mexico City, May 1967

D.R. MacFarlane,N. McNeal, D.A. Meneley, C.K. Sanathanan, "Theoretical Studies of the Response of Fast Reactors During Sodium Boiling Accidents, Proc. Int. Conf. on Safety of Fast Reactors, Aix-en-Provence, September 1967

CANADIAN NUCLEARSOCIETY & CANADIAN NUCLEAR ASSOCIATION ANNUAL MEETINGS

D.A. Meneley, "Transition to Large Scale Nuclear Energy Supply", 27^th Annual Conference of CNS, Toronto, June 2006

D.A. Meneley, "Maintaining Vital Capability in the Canadian Nuclear Industry - Challenges and Opportunities", 22^ndAnnual Conference of CNS, Toronto, June 2001 (Invited)

J.S. Pitre, D.A. Meneley, "An Improved Dynamic Simulation of a CANDU Pressurizer", 10thAnnual Conference of CNS, Ottawa, June 1989

A.F. Shalabi, D.A.Meneley,"Crack Initiation of Hydrides in Zr-2.5 % Nb", 9th Annual Conference of CNS, Winnipeg, June 1988

D.A. Meneley, E.M.Hussein, R.A. Chaplin, R. Girard, "The University of New Brunswick Nuclear Engineering Program", 9th Annual Conference of CNS, Winnipeg, June 1988

J.L. Olsen, D.A. Meneley, "The Regulatory Process and Future Directions", 26th Annual Conference of CNA, Toronto, June 1986 (Invited)

D.A. Meneley, "A Proposal for Evolution of Safety & Licensing Criteria", 6th Annual Conference of CNS, Ottawa, June 1985

D. Abraham, D.Bot, D.A. Meneley, "A Multi-Microprocessor Thermal-Hydraulic Simulator", 4th Annual Conference of CNS, Montreal, June 1983

D.A. Meneley, "Reactor Safety - Some Current Realities", 2^nd Annual Conference of CNS, Ottawa, June 1981

D.A. Meneley, "Some Lessons from a Typical Accident", 1^st Annual Conference of CNS, Montreal, June 1980

TRANSACTIONS OFTHE AMERICAN NUCLEAR SOCIETY

D.A. Meneley, V.G. Snell, "Safety Considerations in International Growth of Nuclear Energy", ANS/ENS Int'l Conference, Chicago, November 1992, (Invited)

L.M. Mesman, D.A. Meneley, "Input and Control Management Scheme for the DSNP Simulation Language", Trans. ANS 53:50-51, November 1986

F.R. Bennett, D.A. Meneley, R.T. Popple, "Levelling with the People", Trans. ANS 39: 49-50, November 1981

E.L. Fuller, D.A. Meneley, J.A. Naser, "Increasing Time Step Sizes in QX1 by Using a Temperature Correction to Reactivity", Trans. ANS 15: No. 1, June1972

W.Y. Kato, D.A. Meneley, "An Analysis of Subcritical Reactivity Measurements Using Pulsed-Neutron Techniques for Fast Reactors", Trans. ANS 14: 863-4, October 1971

D.A. Meneley, K.O.Ott, "Spectral Effects on Liquid-Metal Fast Breeder Reactor Transients", Trans. ANS 12:706, November 1969

E.L. Fuller, D.A. Meneley, D.L. Hetrick, "Integration of the Multimode Kinetics Equations by the Method of Undetermined Parameters", Trans. ANS 12: 710-11, November 1969

L.J. Hoover, D.A.Meneley, "Influence of Neutron Energy Group Structure on Fuel CycleAnalysis of Fast Breeder Reactors", Trans. ANS 12: 441-2, November 1969

D.A. Meneley, K.O.Ott, E.S. Wiener, "Influence of the Shape-Function Time Derivative on Spatial Kinetics Calculations in Fast Reactors", Trans. ANS 11: 225-6, June 1968

D.A. Meneley, "Calculational Checks of Plutonium Cross Sections by Comparison with Critical Assembly Results", Trans. ANS 8: 444, November 1965

G.J. Fischer, D.A. Meneley, "Doppler-Effect Measurements in Plutonium-Fuelled Fast Assemblies", Trans. ANS 1: 252, November 1964

REPORTS

D.A. Meneley, "CANDU Design - Emphasizing Transient Experience" and "CANDU Nuclear

Regulatory Practice- A Designer's Perspective", Nuclear Power Reactor Safety Courses presented at M.I.T., Boston, Mass., USA, July 1996

D.A. Meneley, "Presentation to National Nuclear Safety Administration CHINA" Mississauga, Ontario June 1996

D.A. Meneley, "Reactor Development Future" Institute of Advanced Engineering - Ajou University, Korea, April 1996

D.A. Meneley, "CANDU Safety Case" - Training Program for Indonesian Regulatory Staff, Indonesia, Nov. 1995

D.A. Meneley, "Comment on the Qualitative Comparison of PWR and CANDU, by PAEC", Nov. 1995

D.A. Meneley, "Why is Reactor Safety A Concern" - CNS Reactor Safety Course, Oshawa, Ontario, Nov. 1994

D.A. Meneley, "CANDU Nuclear-Electric Energy System" - Visit to IAE, Seoul, Korea, Feb. 1994

D.A. Meneley, "CANDU Energy System - Achievement and Progress", Ajou University Department of System Engineering, Seoul, Korea, Feb. 1994

D.A. Meneley, "Safety of Nuclear Energy Systems" - Seoul National University, Seoul, Korea June 1993

D.A. Meneley, "Fuel, Burners and Breeders - The Next Fifty years" - Ajou University, Korea, May 1993

D.A. Meneley, "Nuclear Liability Case - Evidence of D.A. Meneley" - Nuclear Liability Case Conf., Toronto, Ontario, May 1993

F.K. Hare, A.R. Robertson, W. Paskievici, D.A. Meneley, "AECB Resource Requirements", Report to the Ministry of Energy Mines and Resources, Ottawa, February 1990

Ontario Nuclear,"The Safety of Ontario's Nuclear Power Reactors; A Scientific and Technical Safety Review", Ministry of Energy, Toronto, February 1988

Int'l Nuclear, "Basic Safety Principles for Nuclear Plants", International Atomic Energy Agency, Safety Advisory Group, Vienna, Safety Series No. 75-INSAG-3, March 1988

Int'l Nuclear Safety Advisory Group, "Source Terms from Severe Accidents to Nuclear Plants withLight Water Reactors", International Atomic Energy Agency, Vienna, Safety Series No. 75 -INSAG-2, March 1987

Int'l Nuclear Safety Advisory Group, "Towards Improvement in Quality Assurance", International Atomic Energy Agency, Vienna, INSAG Technical Note No. 1, March1987

Int'l Nuclear Safety Advisory Group, "Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident", Int'l Atomic Energy Agency, Vienna, Safety Series No.75-INSAG-1, Oct.1986

Committee on Nuclear Safety Research, "Revitalizing Nuclear Safety Research", National Academy of Sciences, Washington, D.C., December 1986

D.A. Meneley, "Nuclear Weapons & Nuclear Reactors", Ontario Hydro Design & Development Division Report #77157, Aug.1977

P.A. Pizzica, D.A. Meneley, "SYNBURN - A Fast Reactor Fuel Cycle Program", ANL-76-14January 1976

B.M. Carmichael, D.A. Meneley, D. Vondy, "Report of the Subcommittee on Standard Interface Files", LA-5324-MX, July 1973

DRL Staff and Consultants, "Safety Evaluation of the Fast Flux Test Facility", 1972(Restricted Access)

D.A. Meneley, K.O.Ott, E.S. Wiener, "Fast Reactor Kinetics - the QX1 Code", ANL-7769,March 1971

D.A. Meneley, E.L.Fuller, A.E. McArthy, "Neutronics of Advanced Liquid-Metal Fast Breeder Reactors with Refractory-Clad Fuel",ANL-7710, June 1970

Staff of Reactor Eng. & Applied Phys. Division, "Evaluation of Five Conceptual Designs of a1000 MWe Fast Breeder Reactor Power Plant, 1970 (unpublished)

Reactor Engineering & Applied Physics Division, "EBR-II Run 25 and 26A Interim Report, 1968", (unpublished)

K.A. Hub, I. Charak, D.E. Lutz, D.H. Thompson, P.F. Gast, D.A. Meneley, "Feasibility Study of Nuclear Steam Supply System Using 10,000 MW Sodium-Cooled Breeder Reactor", ANL-7183, September 1966

D.A. Meneley, L.C.Kvitek, D.M. O'Shea, "MACHI: A One-Dimensional Diffusion TheoryPackage", ANL-7223, June 1966

Selected Honours, Awards &Affiliations

Canadian Academy of Engineering - Fellow
Canadian Nuclear Society -- Fellow
American Nuclear Society - Fellow
Canadian Nuclear Association W.B. Lewis Medal, 1990
Life Member and Past Chair, Defence Science Advisory Board
IAEA Nuclear Safety Advisory Group, 1985-1988
International Nuclear Energy Academy, Member and Past Chair