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Division Spotlight
Reactor Physics
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
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.