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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Satoshi Hanawa, Takehiko Nakamura, Shunsuke Uchida, Pavel Kus, Rudolf Vsolak, Jan Kysela, Masanori Sakai
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 136-148
Technical Paper | Reprocessing | doi.org/10.13182/NT13-A16998
Articles are hosted by Taylor and Francis Online.
A water chemistry research program using the in-pile loop in the Japan Materials Testing Reactor (JMTR) has been launched to develop data that are applicable for model verification as well as model benchmarking. In advance of the in-pile loop experiment performed in the JMTR, reliability of in-pile electrochemical corrosion potential (ECP) measurement and applicability of the theoretical models were investigated, based on experimental data previously obtained in the in-pile loop of the LVR-15 experimental reactor at the Research Center Rez in the Czech Republic. The responses of different types of reference electrodes used for the ECP measurements were compared with each other to confirm their reliability under several different irradiation conditions corresponding to the core peripherals of boiling water reactors (BWRs). The corrosive conditions along the in-pile loop were first calculated using combined models of water radiolysis and ECP, and the calculated results were then compared with the ECP measurement data to validate the model.As a result, it was confirmed that the reference electrodes performed reliably under mixed neutron and gamma-ray irradiation conditions with minor calibration of each electrode prior to application in the loop, and that the combined models of water radiolysis and ECP can be applied for the evaluation of the corrosive conditions of the in-pile loop and BWR cores and their peripherals.