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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
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Shoichiro Okita, Yuji Fukaya, Atsushi Sakon, Tadafumi Sano, Yoshiyuki Takahashi, Hironobu Unesaki
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2251-2257
Technical Note from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2087836
Articles are hosted by Taylor and Francis Online.
In this paper, integral experiments on a graphite-moderated core were conducted at the B-rack of the Kyoto University Criticality Assembly in order to develop an integral experiment database for the applicability of data assimilation techniques to the neutronic design of a high-temperature gas-cooled reactor. The calculation/experiment-1 (C/E-1)values for the keff values at critical cores with the major nuclear data libraries, such as JENDL-4.0, JENDL-5, JEFF-3.2, ENDF/B-VII.1, and ENDF/B-VIII.0, were calculated for the core. Of these, the keff values with JENDL-5 with thermal neutron scattering law data for 30% porous graphite showed the best agreement with experimental values within 0.02% accuracy.