Technical and Management Challenges Associated with Structural Materials Degradation in Nuclear Reactors in the Future
F. Peter Ford’s Plenary Talk from the 13th Enviornmental Degradation of Materials in Nuclear Power Systems,
Expert Panel Report on Proactive Materials Degradation Assessment
A U.S. Nuclear Regulatory Commission report on the status of understanding materials degradation in nuclear power systems.
Materials Degradation and Aging - An EPRI Nuclear Power Action Plan
A review of degradation modes in nuclear power systems and keys to improving performance, reliability, and profitability.
Reawakening of United States Nuclear Energy: Materials Challenges for a New Generation of Power Plants
View presentations made to members of Congress and staffers at a materials information luncheon held in Washington, D.C on May 3, 2007.
Radiation Materials Science: An Introduction to Materials Processes under Irradiation
Radiation Materials Science (RMS) is the materials science of radiation effects. This webcast focuses on metals and alloys commonly used as structural materials in nuclear power systems.
Basic Research Needs for Advanced Nuclear Energy Systems
Report from the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems.
Technology and Applied R&D Needs for Advanced Nuclear Energy Systems
A resource document that includes an overview of nuclear energy, details on the nuclear fuel cycle and materials technological needs.
Nuclear Physics and Related Computational Science R&D for Advanced Fuel Cycles Workshop
Presentations from the Nuclear Physics and Related Computational Science R&D for Advanced Fuel Cycles Workshop
Higher Temperature Reactor Materials Workshop
Technical report of an in-depth workshop focused on the reactor concepts proposed as part of the Generation IV Nuclear Energy System Roadmap.
Nuclear Materials Database
Mechanical properties data for more than 7500 specimens of materials used in nuclear power reactors are stored in the common database.
12th International Symposium on Environmental Degradation of Materials in Nuclear Systems - Water Reactors
Free to TMS Members, 131 papers are included covering degradation phenomena particular to the various reactor systems, BWRs, PWR primary and PWR secondary, as well as narrow topic areas, such as zircalloy and low alloy steels, and cross-cutting topics, such as nickel-base welds, irradiation effects, and irradiation assisted stress corrosion cracking.
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