Recommended Resources: Materials in Nuclear Power Systems

Provided Courtesy of Materials Technology@TMS

For additional resources, visit
http://www.materialstechnology.org

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The following are recommended resources for materials in nuclear power systems from an advisory group of | | | | |
TMS subject matter experts | | | | | |
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PAPER TITLE | AUTHOR(S) | SOURCE | LINK | | |
Stability of Ferritic MA/ODS alloys at high temperatures | M.K. Miller, D.T. Hoelzer, E.A. Kenik, K.F. Russell | Intermetallics, 13 (2005) 387-392 | [View Abstract] | | |
Improvement of Creep Strength of 9CrODS Martensitic Steel by Controlling Excess Oxygen and Titanium Concentrations | S. Ohtuska, S. Ukai, M. Fujiwara, T. Kaito and T. Narita | Materials Transactions, 46(3) (2005) 1 | [View Abstract] | | |
Plastic instability in polycrystalline metals after low temperature irradiation | T.S. Byun and K. Farrell | Acta Materialia, 1597-1608 (2004) | [View Abstract] | | |
The Mechanisms and Modeling of Intergranular Cracking in Ni-Cr-Fe Alloys Exposed to High Purity Water | G.A. Young, W.W. Wilkening, D.S. Morton, E. Richey, and N. Lewis | 12th Environmental Degradation Conference of Materials in Nuclear Power Systems-Water Reactors, p. 913. | [View Article] | | |
Higher Temperature Reactor Materials Workshop | T. Allen, S. Bruemmer, M. Kassner, R. Odette, R. Stoller, G. Was, W. Wolfer, S. Zinkle, J. Elmer, and A Motta | Higher Temperature Reactor Materials Workshop, U. S. DOE - ANL-02/12 | [View Report] | | |
High-Resolution Characterizations of Stress-Corrosion Cracks in Austenitic Stainless Steel from Crack Growth Tests in BWR-Simulated Environments | S. M. Bruemmer and L. E. Thomas | 12th Environmental Degradation Conference of Materials in Nuclear Power Systems-Water Reactors, p. 189. | [View Article] | | |
An Overview of Internal Oxidation as a Possible Explanation of Intergranular Stress Corrosion Cracking of Alloy 600 in PWRS | P. M. Scott | 9th Environmental Degradation Conference of Materials in Nuclear Power Systems-Water Reactors, p. 3. | [View Article] | | |
Comparison of Swelling and Irradiation Creep Behavior of fcc-Austenitic and bcc-Ferritic/Martensitic Alloys at High Neutron Exposure | F. A. Garner, et al | J. of Nuclear Materials, v. 276, 1999, p. 123 | [View Abstract] | | |
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 H. F. Lopez | Met. and Mater. Trans. A, 37A, 2006, 2471 | [View Abstract] | | |
Long Term Radiation Effects in Fission and Fusion Reactors | W. Wolfer, A. Kubota, M. Surh, T. Okita, J. Sturgeon, F. Garner and K. Morishita | Workshop on  Advanced Computational Materials Science for Fusion and Fission Reactors, U. S. Department of Energy, 2004 | [View Slides] | | |
Simulation and Modeling for Advanced Nuclear Energy Systems Workshop | R.  Stevens, D. Keyes and P. Finck (Chairs) | Simulation and Modeling for Advanced Nuclear Energy Systems Workshop, Office of Nuclear Energy and Office of Advanced Scientific Computing Research, U. S. Department of Energy, August 2006. | [View Report] | | |
Nuclear Physics and Related Computational Science R&D for Advanced Fuel Cycles Workshop. | L. Schroeder and E. Lusk (Chairs) | Nuclear Physics and Related Computational Science R&D for Advanced Fuel Cycles Workshop, U. S. DOE Office of Science, August 2006. | [View Presentaions] | http://www-fp.mcs.anl.gov/nprcsafc/ | |
Basic Research Needs for Advanced Nuclear Energy Systems | J. Roberto and T. Diaz de la Rubia (Chairs) | Basic Research Needs for Advanced Nuclear Energy Systems, Office of Basic Energy Science, U. S. Department of Energy, October 2006 | [View Report] | | |
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