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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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Fusion Science and Technology
NRC’s Inspector General issues report
Overall findings of a survey of Nuclear Regulatory Commission personnel indicate that while the NRC maintains a few strengths compared to external benchmarks, results have declined since 2015 in a number of areas, according to a recent report from the NRC’s Office of the Inspector General (OIG).
The survey was conducted in February 2020 by Willis Towers Watson, a global risk-management, insurance brokerage, and advisory firm that has partnered with the OIG for more than 20 years to assess the NRC’s safety culture and climate, as well as other aspects of employee experience.
Richard F. Mattas
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1257-1262
Blanket and First Wall Engineering | dx.doi.org/10.13182/FST83-A23030
Articles are hosted by Taylor and Francis Online.
A one dimensional computer code has been developed to examine the lifetime of first wall and impurity control components. The code incorporates the operating and design parameters, the material characteristics, and the appropriate failure criteria for the individual components. The major emphasis of the modelling effort has been to calculate the temperature-stress-strain-radiation effects history of a component so that the synergystic effects between sputtering erosion, swelling, creep, fatigue, and crack growth can be examined. The general forms of the property equations are the same for all materials in order to provide the greatest flexibility for materials selection in the code. The code is capable of determining the behavior of a plate, composed of either a single or dual material structure, that is either totally constrained or constrained from bending but not from expansion. The code has been utilized to analyze the first walls for FED/INTOR and DEMO.