Listed below are publications in the field. Please visit the Knowledge Resource Center for a complete listing of proceedings and publications.

The following related titles are available:

• Fundamentals of Radiation Materials Science – purchase as a set with the Radiation Materials Science webcast and save 30%!
• Nuclear Principles in Engineering
• Environmental Degradation of Mat'ls in Nuclear Systems XII
• Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 1999, Ninth Edition

TMS Webcasts
TMS offers webcasts on a variety of topics to provide timely technical updates. The following webcast focuses on metals and alloys commonly used as structural materials in nuclear power systems.

• Radiation Materials Science: An Introduction to Materials Processes under Irradiation.

JOM
The TMS member journal, JOM, periodically focuses an issue on matters associated with nuclear materials technology. Recent editions of note include:

• The Nuclear Renaissance: A Challenge for the Materials Community, by Todd Osman.  January 2008.
• Cladding and duct materials for advanced nuclear recycle reactors, by T.R. Allen, J.T. Busby, R.L. Klueh, S.A. Maloy, and M.B. Toloczko. January 2008.
• Radiation effects on the microstructure of a 9Cr-ODS alloy by J. Gan, T.R. Allen, R.C. Birtcher, S. Shutthanandan, and S. Thevuthasan. January 2008.
• The development of metallic nuclear fuels for transmutation applications: Materials challenges, by D.D. Keiser, Jr., J.R. Kennedy, B.A. Hilton, and S.L. Haye. January 2008.
• The early characterization of irradiation effects in stainless steels at the Experimental Breeder Reactor-II, by D.L. Porter. January 2008.
• Material corrosion issues for nuclear waste disposition in Yucca Mountain, by Raul B. Rebak. January 2008.
• Localized corrosion of alloy 22 in the potential Yucca Mountain repository environment, by Xihua He and Todd Mintz. January 2008.
• Modeling Alloy 22 general corrosion in the Yucca Mountain nuclear waste repository, by Kevin G. Mon, Bryan E. Bullard, Fred Hua, and Gopal C. De. January 2008.
• The crevice corrosion of Alloy 22 in the Yucca Mountain nuclear waste repository, by R.M. Carranza. January 2008.
• The potential for the SCC of titanium alloys under repository-relevant environments for U.S. nuclear waste, by Fred Hua, Kevin Mon, Gopal De, Gerald Gordon, and Peter L. Andresen. January 2008.
• Toys that radiate fun: A look at atomic-themed games and collectibles. April 2007.
• Materials for advanced nuclear systems, by Robert J. Hanrahan. April 2007
• Basic research needs for advanced nuclear energy systems, by James B. Roberto and Tomas Diaz de la Rubia. April 2007.
• Space fission reactor structural materials: Choices past, present, and future, by J. T. Busby and K. J. Leonard. April 2007.
• The atomic structure of disordered ion tracks in magnesium aluminate spinel, by Kazuhiro Yasuda, Tomokazu Yamamoto and Syo Matsumura.  April 2007.
• Radiation effects in a model ceramic for nuclear waste disposal, by Ram Devanathan and William J. Weber, April 2007.
• Irradiation-induced order-to-disorder phase transformation at different temperatures in Dy2O3, by M. Tang, J. A. Valdez, K. E. Sickafus and P. Lu. April 2007.
• The atomic-scale modeling of dislocation-obstacle interactions in irradiated metals, D. J. Bacon and Yu. N. Osetsky. April 2007.
• Precipitate stability and morphology in irradiation environments, P. Krasnochtchekov, R. S. Averback and P. Bellon. April 2007.

Metallurgical & Materials Transactions
An archival peer-reviewed monthly publication focuses on the latest research in all aspects of physical metallurgy and materials science.  Recent articles relating to materials for nuclear power include:

• Materials Issues for Advanced Nuclear Systems (Foreword), by Raul Rebak.  February 2008.
• Synchrotron X-Rays for Microstructural Investigations of Advanced Reactor Materials Wolfgang Hoffelner, Annick Froideval, Manuel Pouchon, Jiachao Chen and Maria Samaras.  February 2008.
• The Mechanism of Zr and Hf in Reducing Radiation-Induced Segregation in 316 Stainless Steel M.J. Hackett, J.T. Busby and G.S. Was.  February 2008.
• Environmental Testing of Iron-Based Amorphous Alloys, by Raul B. Rebak, S. Daniel Day, Tiangan Lian, Phillip D. Hailey and Joseph C. Farmer.  February 2008.
• Oxidation Products of INCONEL Alloys 600 and 690 in Pressurized Water Reactor Environments and Their Role in Intergranular Stress Corrosion Cracking. J.B. Ferguson and Hugo F. Lopez. August 2006.
• Computation of Ni-Cr Phase Diagram via a Combined First-Principles Quantum Mechanical and CALPHAD Approach. Kwai S. Chan, Yi-Ming Pan, and Yi-Der Lee. July 2006.
• First-Principles Computations of Mechanical Properties of Ni2Cr and Ni2Mo .K.S. Chan, Y.-D. Lee, and Y.-M. Pan. March 2006.
• Microstructural Evolution in Zr3Al-Based Alloys during Various Long-Time Annealing Treatments. R. Tewari, G.K. Dey, S. Banerjee, and N. Prabhu. January 2006.
• Role of Temperature and Strain Rate on the Hydrogen-Induced Intergranular Rupture in Alloy 600. J. Chêne and A.M. Brass. February 2004.
• Residual Stresses in an Electron Beam Weld of Ti-834: Characterization and Numerical Modeling. J.R. Cho, K.T. Conlon, and R.C. Reed. December 2003.
• Hydride Embrittlement and Irradiation Effects on the Hoop Mechanical Properties of Pressurized Water Reactor (PWR) and Boiling-Water Reactor (BWR) ZIRCALOY Cladding Tubes: Part I. Hydride Embrittlement in Stress-Relieved, Annealed, and Recrystallized ZIRCALOYs at 20°C and 300°C. S. Arsene, J.B. Bai, and P. Bompard. March 2003.
• Hydride Embrittlement and Irradiation Effects on the Hoop Mechanical Properties of Pressurized Water Reactor (PWR) and Boiling-Water Reactor (BWR) ZIRCALOY Cladding Tubes: Part II. Morphology of Hydrides Investigated at Different Magnifications and their Interaction with the Processes of Plastic Deformation. Miléna Veleva, Sylvie Arsene, Marie-Christine Record, JeanLuc Bechade, and Jinbo Bai. March 2003.
• Hydride Embrittlement and Irradiation Effects on the Hoop Mechanical Properties of Pressurized Water Reactor (PWR) and Boiling-Water Reactor (BWR) ZIRCALOY Cladding Tubes: Part III. Mechanical Behavior of Hydride in Stress-Relieved Annealed and Recrystallized ZIRCALOYsat 20°C and 300°C. March 2003.