Dr. Arthur has 23 years experience in field, experimental and theoretical
modeling studies of the long-term stability and performance of engineered
and natural barriers to radionuclide migration from geologic repositories
for nuclear wastes. He is a geochemist with specialized expertise in the
areas of: 1) actinide and fission-product geochemistry, 2) geochemistry
of natural waters, 3) thermodynamic, kinetic and mass-transfer
constraints on fluid-rock interactions in natural and waste-disposal
systems, 4) development of internally consistent thermodynamic and
hydrochemical databases, and 5) interpretation of chemical, isotopic,
mineralogical and geophysical data characterizing deep groundwater
systems at international sites selected for the development of
underground research laboratories (URLs). Dr. Arthur has extensive
experience in the use of geochemical modeling techniques and software,
including SUPCRT, Geochemist’s Workbench, EQ3/6, PHREEQC,
MINTEQA2, HYDROCHEM and TOUGHREACT. He has consulted for
nuclear waste R&D organizations and regulatory authorities in the U.S.,
Canada, Japan, Taiwan, U.K., Sweden, Finland and Switzerland.
Dr. Arthur has authored numerous articles in peer-reviewed journals
and in technical reports published by national R&D organizations in the
U.S., Europe and Asia. He has a Bachelor of Science degree in Geology
from California State University, San Diego, and a Ph.D. degree in
Geochemistry and Mineralogy from the Pennsylvania State University.

Dr. Matthew Kozak is a Principal Consultant for Monitor Scientific LLC.
He is known both nationally and internationally for his work on safety
assessments of waste disposal facilities and contaminated sites.
Dr. Kozak is a frequent consultant to the International Atomic Energy
Agency, and has supported the governments of Belarus, Bulgaria, Egypt,
Estonia, Malaysia, Moldova, Poland, and Romania on missions to site,
develop, construct, and analyze disposal facilities to provide national
capacity to disposal of radioactive waste. He was the official U.S. delegate
to the International Atomic Energy Agency’s Coordinated Research
Program on Improvement of Safety Assessment Methodologies (ISAM),
and is currently participating in its successor program on Application of
Safety Assessment Methodologies (ASAM). He has also conducted recent project work in Canada, the UK, Korea, Japan, and South Africa. In the
USA, Dr. Kozak has supported EPA, EPRI, DOE, and NRC on a wide
variety of radioactive waste disposal and radioactive contamination issues.
This has included work on Yucca Mountain, and a number of other sites
for low-level waste. He has provided technical input to regulatory
rulemakings for high-level and low-level wastes, and for residual
contamination from decommissioning.
During 2000-2001, Dr. Kozak was a member of the National Research
Council Committee on Cesium Processing Alternatives for High-Level
Waste at the Savannah River Site. Dr. Kozak is the former chair of
Scientific Committee 87-3 for the National Council on Radiation Protection (NCRP) on safety assessment of radioactive waste disposal facilities. 
Dr. Kozak is also a past member of NCRP Umbrella Scientific Committee
87 on Radioactive and Mixed Waste. In 2004, Dr. Kozak was on the
IAEA’s International Peer Review Team for the Australian National Repository.

Dr. Stenhouse has over 15 years’ experience in addressing issues
associated with contaminant transport and the resultant impacts on the
environment, primarily humans. He has provided technical expertise to national implementing and supporting waste agencies with responsibilities
for radioactive waste disposal in Europe, North America and Asia. He has
also provided technical support to international organizations such as
IAEA and NATO, including several missions to Bulgaria and Russia, to
enhance collaboration with local scientist on radioactive waste issues.
Much of this work has focused on an in-depth understanding of the key
transport properties of radionuclides in solution, primarily sorption and diffusion parameters. Dr. Stenhouse also has over 15 years’ experience
in performance assessment and scenario analysis, initially associated
with safety assessments for radioactive waste disposal, but more recently
applied to geological CO2 storage projects, in particular the Phase 1
assessment for the Weyburn Project (see Projects). Other technical
interests include Principal Component Analysis, impacts from naturally-
occurring radioactive materials (NORM), and clearance levels. He has over
80 publications and reports on the above topics. Dr. Stenhouse obtained
his B. Sc. in Pure Chemistry and Ph.D. in Nuclear Geochemistry at the
University of Glasgow, Scotland.

Dr. Wei Zhou is the senior consultant who has worked in the fields
of safety, performance, and risk assessment related to nuclear waste
management, CO2 geological sequestration, and hazardous waste
management. Her consulting activities primarily involve methodology development, modeling and simulation, independent expert review,
model and software development, training and workshop, quality
assurance for clients ranging from industries (Electric Power Research
Institute, Nuclear Energy Institute, Korean Hydro and Nuclear Power, Canadian Petroleum Technology Research Institute, etc), governments
(US EPA, DOE, Swedish Nuclear Inspectorate, Japan Atomic Energy
Agency, etc), research institutes (Taiwan’s Institute of Nuclear Energy
Research, Beijing Research Institute of Uranium Geology, etc), and
international organizations (International Energy Agency, Nuclear Energy Agency, Commission for the European Communities, etc). In particular,
her areas of expertise include probabilistic, deterministic, or hybrid
modeling and assessment, scenario analysis, systems analysis, natural
analogue, modeling and simulation of multi-phase, multi-component,
and multi-medium systems as well as coupled transport processes.
Dr. Zhou’s interest also covers environmental system and impact
assessment, advanced nuclear fuel cycle, uranium mining, risk
communication, global warming, and sustainable development.
Dr. Zhou obtained Ph.D. in Nuclear Engineering from University of
California at Berkeley in 1992. She obtained Bachelor degree in
Mechanical Engineering from Beijing Polytechnic University and Master
degree in Mechanical Engineering from San Jose State University.

Dr. Apted has a Bachelor of Science Degree in Chemistry from the Massachusetts Institute of Technology, and a Ph.D. Degree in
Geochemistry from the University of California, at Los Angeles. 
He is a scientific consultant with more than 25 years of experience in
nuclear-waste disposal R&D, primarily in the design and testing of engineered barrier systems (EBS), hydrogeochemical modeling, and
safety assessment. For the Electric Power Research Institute he is the
R&D manager for post-closure risk assessment studies regarding disposal
of spent nuclear fuel and high-level waste at the Yucca Mountain site,
Nevada, USA. He is a member of the International Technical Advisory Committee (ITAC) to the Nuclear Waste Management Organization of
Japan (NUMO), and serves as a coordinator for NUMO’s International
Tectonics Committee.  Dr. Apted is Chairman of the EBS and Technology
Support Group for STUK, the safety authority in Finland. He also has
consulted for nuclear waste repository implementation and regulatory agencies in Sweden, Switzerland, South Africa, Canada, Taiwan, and
South Korea. Dr. Apted is past Chairman for the Materials Research
Society's Symposium on the Scientific Basis for Nuclear Waste Management. He has organized, conducted, and authored reports for
the International Atomic Energy Agency (IAEA) and the Nuclear Energy
Agency (NEA). He has served on various US National Academy of
Sciences committees related to nuclear waste disposal. Dr. Apted has
presented and/or published over 150 papers in the above technical areas.