Gary S. Was

发表

Feasibility Study of Supercritical Light Water Cooled Reactors for Electrical Power Production, 5th Quarterly Report, October - December 2002

L. Oriani, Jacopo Buongiorno, Mario D. Carelli, 2003 .

Nuclear materials program at the University of Michigan

Gary S. Was, 1985 .

Materials degradation in fission reactors: Lessons learned of relevance to fusion reactor systems

Gary S. Was, G. Was, 2007 .

Economic feasibility study of total energy system options for the Massachusetts Institute of Technology

Gary S. Was, M Golay, 1978 .

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors: Bruemmer/Ninth

Peter Ford, Gary S. Was, Steve Bruemmer, 1999 .

Expanding the scope of nuclear engineering at the University of Michigan

Gary S. Was, 1995 .

Adjoint sensitivity analysis in nuclear reactor fuel behavior modeling

Ronald A Rohrer, Gary S. Was, R. Christensen, 1981 .

Creation of a remotely monitored and controlled ion beam laboratory using novel hardware and software tools

Gary S. Was, T. Kubley, Fabian Naab, 2019 .

Simulation of ion beam transport through the 400 Kv ion implanter at Michigan Ion Beam Laboratory

Gary S. Was, Fabian Naab, Ovidiu Toader, 2013 .

Clad failure modeling. Discussion

H. H. Klepfer, Gary S. Was, R. Christensen, 1982 .

Remote Monitoring and Control of Irradiation Experiments

Gary S. Was, Ovidiu Toader, V. H. Rotberg, 2003 .

Higher temperature reactor materials workshop sponsored by the Department of Energy Office of Nuclear Energy, Science, and Technology (NE) and the Office of Basic Energy Sciences (BES).

Stephen M. Bruemmer, M. Kassner, Todd R. Allen, 2002 .

Perspectives on multiscale modelling and experiments to accelerate materials development for fusion

Steven J. Zinkle, Mark R. Gilbert, Andrey Litnovsky, 2021 .

Materials Challenges for Generation IV Nuclear Energy Systems

James I. Cole, Douglas C. Crawford, Todd R. Allen, 2008 .

Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A

Gaurav Gupta, Suntharampillai Thevuthasan, Todd R. Allen, 2005 .

Ion irradiation-induced phase transformation of pyrochlore and zirconolite

Lumin Wang, Gary S. Was, Rodney C. Ewing, 1999 .

Engineered Coatings for Ni Alloys in High Temperature Reactors

Carlos G. Levi, Gary S. Was, Elizabeth A. Clark, 2010, Metallurgical and Materials Transactions A.

The relationship between hardness and yield stress in irradiated austenitic and ferritic steels

Gary S. Was, J. Busby, G. Was, 2005 .

Time, temperature, and dissolved oxygen dependence of oxidation of austenitic and ferritic-martensitic alloys in supercritical water

Todd R. Allen, Gary S. Was, T. Allen, 2005 .

Fundamentals of Radiation Materials Science: Metals and Alloys

Gary S. Was, G. Was, 2007 .

A high intensity radiation effects facility

Gary S. Was, Ovidiu Toader, V. H. Rotberg, 2001 .

Modeling of microstructure evolution in austenitic stainless steels irradiated under light water reactor condition

Roger E. Stoller, Gary S. Was, J. Gan, 2001 .

Relationship between localized strain and irradiation assisted stress corrosion cracking in an austenitic alloy

Gary S. Was, Diana Farkas, M. D. McMurtrey, 2011 .

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production

L. Oriani, Jacopo Buongiorno, James W. Sterbentz, 2005 .

Irradiation induced microstructure and irradiation assisted stress corrosion cracking in supercritical water

Gary S. Was, Zhijie Jiao, S. Teysseyre, 2006 .

Swelling and radiation-induced segregation in austentic alloys

Edward A. Kenik, Todd R. Allen, Gary S. Was, 2005 .

Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction

Andrew M. Minor, Peter Hosemann, Gary S. Was, 2015 .

Behavior of grain boundary chemistry and precipitates upon thermal treatment of controlled purity alloy 690

Gary S. Was, G. Was, Thomas M. Angeliu, 1990 .

FCODE-BETA|SS: a fuel performance code for stainless steel clad pressurized water reactor fuel

Gary S. Was, Richard W. Smith, 1985 .

Application of adjoint sensitivity analysis to nuclear reactor fuel rod performance

Scott J. Wilderman, Gary S. Was, 1984 .

Materials Challenges for Advanced Nuclear Energy Systems

Steven J. Zinkle, Gary S. Was, S. Zinkle, 2009 .

Fundamentals of radiation materials science

Gary S. Was, G. Was, 2007 .

Dependence of radiation-induced segregation on dose, temperature and alloy composition in austenitic alloys

Todd R. Allen, Gary S. Was, T. Allen, 1995 .

Irradiation assisted stress corrosion cracking of controlled purity 304L stainless steels

Gary S. Was, J. M. Cookson, G. Was, 1993 .

A model for the normal stress dependence of intergranular cracking of irradiated 316L stainless steel in supercritical water

Gary S. Was, G. Was, E. A. West, 2011 .

Role of Localized Deformation in Irradiation-Assisted Stress Corrosion Cracking Initiation

Gary S. Was, Zhijie Jiao, M. D. McMurtrey, 2011, Metallurgical and Materials Transactions A.

The effect of oversized solute additions on the microstructure of 316SS irradiated with 5 MeV Ni++ ions or 3.2 MeV protons

Stephen M. Bruemmer, L. Fournier, Gary S. Was, 2004 .

Materials Challenges in Nuclear Energy

Steven J. Zinkle, Gary S. Was, S. Zinkle, 2013 .

Radiation-Induced Material Changes and Susceptibility to Intergranular Failure of Light-Water-Reactor Core Internals

Stephen M. Bruemmer, Gary S. Was, Peter L. Andresen, 1999 .

Radiation damage to structural alloys in nuclear power plants: mechanisms and remediation

Gary S. Was, Peter L. Andresen, G. Was, 2014 .

Corrosion and stress corrosion cracking in supercritical water

Gaurav Gupta, Todd R. Allen, Gary S. Was, 2007 .

Irradiation-assisted stress corrosion cracking

Gary S. Was, Peter L. Andresen, Yugo Ashida, 2011, Comprehensive Nuclear Materials.

Deformation and fracture in microlaminates

T. Foecke, Gary S. Was, G. Was, 1996 .

The effect of grain boundary character distribution on the high temperature deformation behavior of Ni–16Cr–9Fe alloys

Bogdan Alexandreanu, Gary S. Was, Visit Thaveeprungsriporn, 2003 .

Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments

Gary S. Was, Peter L. Andresen, G. Was, 2007 .

Emulation of neutron irradiation effects with protons: validation of principle

Stephen M. Bruemmer, Edward A. Kenik, Todd R. Allen, 2002 .

The role of coincidence-site-lattice boundaries in creep of Ni-16Cr-9Fe at 360 °C

Gary S. Was, Visit Thaveeprungsriporn, G. Was, 1997 .