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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Shunsuke Uchida, Satoshi Hanawa, Yutaka Nishiyama, Takehiko Nakamura, Tomonori Satoh, Takashi Tsukada, Jan Kysela
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 119-135
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT13-A16997
Articles are hosted by Taylor and Francis Online.
In-pile loop experiments are one of the key technologies that can provide an understanding of corrosion behaviors of structural materials in nuclear power plants (NPPs). The experiments should be supported not only by reliable measurement tools to confirm corrosive conditions under neutron and gamma-ray irradiations but also by theoretical models for extrapolating the measured data to predict corrosion behaviors in NPPs.The relationships among electrochemical corrosion potential (ECP), metal surface conditions, exposure time, and other environmental conditions have been determined from in situ measurements of corrosion behaviors of stainless steel specimens exposed to H2O2 and O2 in high-temperature water. Based on the relationships, a model to evaluate the ECP of stainless steel was developed by coupling an electrochemical model and a double-oxide layer model.Major conclusions obtained from the evaluation model are as follows: (a) The difference in ECP behaviors of the specimens exposed to H2O2 and O2 were mainly from the thickness and developing rate of the inner oxide layers. (b) Calculated ECP behaviors, e.g., the different responses to H2O2 and O2 and hysteresis and memory effects, agreed with the measured ones. (c) Neutron exposure might decrease ECP due to radiation-induced diffusion in the oxide layer.The ECP evaluation model will be applied to evaluation of corrosive conditions in the JMTR in-pile loop.