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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
Industry Update—August 2025
Here is a recap of industry happenings from the recent past:
SMR service center targeted for Ontario
GE Vernova Hitachi Nuclear Energy has announced plans to invest as much as $50 million to establish a Canadian BWRX-300 Engineering and Service Center near Ontario Power Generation’s Darlington New Nuclear Project site. The Ontario government had previously approved the construction of the first of four BWRX-300 small modular reactors at the site. The center will provide engineering and technical services for the long-term operation and maintenance of the future fleet of SMRs in Ontario. It will also serve as a hub for innovation and training, knowledge sharing, supply chain engagement, and workforce development.
S. Di Maria et al.
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 298-301
Modeling and Simulations | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13436
Articles are hosted by Taylor and Francis Online.
The main objective of the CDT project is to establish an engineering design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) that is the pilot plant of an industrial-scale of both an Accelerator Driven System (ADS) and a Lead Fast Reactor (LFR), based on the MYRRHA reactor concept, planned to be built during the next decade. An important issue regarding the reactor design of the MYRRHA/FASTEF experiment is the in-vessel fuel storage facility for fresh fuel, as it might have an impact on the criticality of the overall system that must be analyzed and quantified. In this work, the neutronic analysis of the in-vessel fuel storage facility and its coupling with the critical core was performed, using the state of the art Monte Carlo program MCNPX 2.6.0. Using this program several parameters were analyzed, like the criticality behavior (namely the Keff), the fission power production and the radiation damage (the displacements per atom).