SCDAP/RELAP5 Peer Review Committee

SCDAP/RELAP5 Independent Peer Review Committee
M. L. Corradini
Michael L. Corradini is Chair of nuclear engineering and engineering physics department, College of Engineering, University of Wisconsin-Madison. During the last 12 years, he has been engaged in research related to nuclear and industrial safety, with specific emphasis on subjects involving multiphase flow and heat/mass transfer. His current research focuses on vapor-explosion phenomena, jet-spray breakup, and mixing dynamics, as well as heat/mass transfer and chemical reactions involved in molten-core-concrete interactions. He is a Fellow of the American Nuclear Society and was a recipient of the 1990 Young Members Engineering Achievement Award. He serves as a consultant for the NRC Advisory Committee on Reactor Safeguards, as well as for the Department of Energy (DOE) National Laboratories (Los Alamos National Laboratory, Oak Ridge National Laboratory, Idaho National Engineering Laboratory, and Brookhaven National Laboratory), and participates in research with the national and international sponsors. Professor Corradini obtained his B.S. degree in mechanical engineering from Marquette University in 1975 and his M.S. and Ph.D. from the Massachusetts Institute of Technology in 1978. He was a member of the technical staff at Sandia National Laboratories for three years before joining the faculty of the University of Wisconsin-Madison in nuclear engineering.

V. K. Dhir
Vijay K. Dhir is a professor of engineering and applied science, Mechanical Aerospace and Nuclear Engineering Department, School of Engineering and Applied Science, University of California at Los Angeles (UCLA). During the past 17 years, he has done both basic and applied research in the thermal sciences and in energy conversion systems. His basic research is on the phenomenological studies of phase-change heat and mass transfer. This research includes experimental and analytical investigations of pool and forced flow boiling under saturated and subcooled conditions, two-phase flow in porous media, film condensation, simultaneous melting and condensation under steady-state and transient conditions, and evaporation. In the applied areas, he has worked on safety and thermal hydraulics of fission and fusion nuclear power reactors. The studies have included reflood heat transfer, degraded core heat transfer and fluid flow phenomenology, core-concrete interactions, natural convection and stratification in liquid-metal-cooled reactors, and melting, freezing, and plugging of coolant channels in transient overpower accidents. He has served on various DOE review panels; has been a consultant to Atomics International, Canoga Park, in support of the design efforts for a pool-type, fast-breeder reactor with inherent safety characteristics; and has served as a member of the MELCOR Peer Review Committee. He has also been a consultant to the National Bureau of Standards; Science Applications International Corporation; Battelle Northwest Laboratories; EG&G, Idaho, Inc.; General Electric; Electric Power Research Institute; and Pickard, Lowe and Garrick. Dr. Dhir obtained his Ph.D. in mechanical engineering from the University of Kentucky, Lexington, and has published more than 100 papers in various national and international journals and conference proceedings. At UCLA, he teaches courses in heat transfer, thermodynamics, and nuclear reactor thermal-hydraulic design.

T. J. Haste
Tim Haste is a senior scientist in the Reactor Safety Studies Department, Safety and Performance Division, AEA Reactor Services, AEA Technology, Winfrith, United Kingdom. He is currently engaged in analysis of early-phase melt progression in PWR systems, is project manager for UK activities involving MELCOR and SCDAP/RELAP5, is collaborating actively with national laboratories in the US, France, and Germany, and has served as a member of the MELCOR Peer Review Committee. He is presently chairman of the UK SCDAP/RELAP5 User's Group. Before his appointment at Winfrith, he worked for 10 years at the Springfields Laboratories of AEA Technology, specializing in theoretical analysis of fuel performance in advanced gas-cooled-reactor and PWR systems under normal and design basis LOCA conditions and in thermophysical properties of reactor materials. One year of this period was spent as a visiting scientist at the OECD Halden Reactor Project, Norway. He was a coauthor of the UK Zircalloy Data Manual. Before working at Springfields, he researched into Doppler broadening in fast reactors at Harwell, UK. Dr. Haste maintains a general interest in the water reactor fuels area, acting as a referee for papers and reviews in international journals and conferences and contributing regularly in these areas. After graduating in theoretical physics from Cambridge University, UK, he obtained a Ph.D. in Nuclear Science from Oxford University, UK. He is a Fellow of the UK Institute of Mathematics, a member of the UK Institute of Physics (Chartered Physicist), and a member of the British Nuclear Energy Society.

T. J. Heames
Terry Heames is a senior engineer at Science Applications International Corporation and has over 20 years of experience in the reactor safety area. He is part of a long-term contract with Sandia National Laboratories to provide expert assistance in the nuclear safety research area. Mr. Heames is currently coordinating the development of the VICTORIA fission-product behavior code. He was a developer of the MELPROG water reactor melt progression code and of the SAS liquid metal reactor melt progression code. Mr. Heames maintains a general interest in melt progression and accident sequence phenomena by reviewing and contributing papers in that field. He holds an M.S. degree in mechanical engineering from Northwestern University.

R. P. Johnson
Rick Johnson is Committee Chair for the SCDAP/RELAP5 Peer Review Committee. He is a staff member at Los Alamos National Laboratory, Los Alamos, New Mexico, in the Terrestrial Reactor Technology Section within the Reactor Design and Analysis Group. Mr. Johnson has performed LWR thermal-hydraulic code assessments, conducted nuclear plant systems analyses, provided code-user support, and developed computer systems models. Previous experience includes BWR fuel engineering work for Westinghouse Electric Corporation. He holds an M.S. degree in nuclear engineering from Oregon State University.

J. E. Kelly
John E. Kelly is manager of the Accelerator Production of Tritium Project, Department 6414, Sandia National Laboratories, Albuquerque, New Mexico. His current interests are directed toward assessing the safety of neutron spallation technology. During the past 12 years, his principal activities have been in four areas related to reactor safety: thermal hydraulics, severe accidents, probabilistic risk assessment (PRA), and new production reactor safety. He has performed basic research in developing, assessing, and applying numerical methods to complex nuclear reactor thermal-hydraulic problems. In addition, he developed computer models for in-vessel melt progression analysis and was the principal investigator for a program that developed an integrated, best-estimate computer code for analyzing in-vessel core melt progression (MELPROG). He managed and directed the development of the MELCOR severe-accident computer code and participated in the Committee for Safety of Nuclear Installations (CSNI) working group that studied the TMI-2 accident. Dr. Kelly received his Ph.D. in nuclear engineering from the Massachusetts Institute of Technology in 1980. He has authored or coauthored over 30 articles and reports in the nuclear reactor safety area.

M. Khatib-Rahbar
Mohsen Khatib-Rahbar is president of Energy Research, Inc., in Rockville, Maryland. His research focuses on nuclear reactor safety and PRA. He has published extensively on severe accidents, source terms, methods for uncertainty analysis, consequence assessment, thermal hydraulics, and numerical methods. He has also developed computer models for simulation of thermal-hydraulic and neutronic transients in LWRs and liquid-metal, fast-breeder reactors. Before starting Energy Research, Inc., he was a staff scientist at Brookhaven National Laboratory, where he managed programs dealing with level 2/3 PRA reviews, verification, and benchmarking of the source-term code package (STCP) and MELCOR, source-term uncertainties (QUASAR), Zion/Draft NUREG-1150, and regulatory implications of new source terms. Dr. Khatib-Rahbar was a visiting scientist at Gesellschaft fuer Reaktorsicherheit in Germany (1982) and at the NRC Office of Nuclear Regulatory Research (1988-1989). He is currently a consultant to the US DOE, the NRC, the Swiss Federal Nuclear Safety Inspectorate, the International Atomic Energy Agency, the European Space Agency, several national laboratories and private organizations, and has served as a member of the MELCOR Peer Review Committee. He holds a Ph.D. in nuclear science and engineering from Cornell University.

R. Viskanta
Raymond Viskanta is W.F.M. Goss Distinguished Professor of Engineering at Purdue University. His research focuses on heat transfer in buoyancy-driven flows, solid-liquid phase change, flow and heat transfer in porous media, radiative transfer in participating media, and combined conduction radiation, as well as convection-radiation heat transfer. Dr. Viskanta has been a Springer and Visiting Professor at the University of California, Berkeley, and a Guest Professor at the Technical University of Munich and at the Tokyo Institute of Technology. Before accepting employment with Purdue University, he was a mechanical engineer at Argonne National Laboratory in the Reactor Engineering Division. He has served as a consultant on heat transfer and thermal hydraulics to a number of national laboratories and industry, was a member of the Peer Review Panel on the Draft Reactor Risk Reference Document (NUREG-1150), and was a member of the MELCOR Peer Review Committee. He was a consultant to the PRA Subcommittee of the US Department of Energy Advisory Committee on Nuclear Facilities Safety. Dr. Viskanta is the technical editor of the ASME Journal of Heat Transfer, serves on advisory editorial boards of several journals, and is an author of over 300 journal publications on heat transfer, thermal sciences, and radiative transfer. He holds a Ph.D. in mechanical engineering from Purdue University and is a member of the National Academy of Engineering. Return to Rick Johnson Home Page