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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
IAEA to help monitor plastic pollution in the Galapagos Islands
The International Atomic Energy Agency announced that its Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative has partnered with Ecuador’s Oceanographic Institute of the Navy (INOCAR) and Polytechnic School of the Coast (ESPOL) to build microplastic monitoring and analytical capacity to address the growing threat of marine microplastic pollution in the Galapagos Islands.
Stéphane Paquette, Hugues W. Bonin
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 315-336
Technical Paper | Fission Reactors | doi.org/10.13182/NT11-A13311
Articles are hosted by Taylor and Francis Online.
The present work describes the preliminary design of a 25-MW(thermal) nuclear reactor capable of providing safe and reliable heating and electricity to any Canadian Forces Bases, especially in the Arctic, as well as in comparable civilian applications. The aim of the project is to provide a nuclear reactor system with sufficient inherent safety characteristics as it is intended to run in automatic mode and be monitored by operators with limited experience and training. For the neutronics calculations, the design work of the reactor's core is carried out using the probabilistic simulation code MCNP 5 along with the Winfrith Improved Multigroup Scheme-Atomic Energy of Canada Limited (WIMS-AECL) deterministic code, Version 3.1, thus permitting a code-to-code comparison of the numerical results. Several design constraints related to coolant temperature and pressure, reactivity control, fuel enrichment, and time between refueling have been considered. The final reactor concept, named the Super Near Boiling 25 reactor (SNB25), provides heat energy dedicated to building and domestic water heating and supplies electricity through an organic Rankine cycle energy conversion plant. SNB25 employs TRISO fuel particles, contained in zirconium-sheathed fuel rods, and is light water cooled and moderated. Complete reactivity control is achieved through simple and reliable mechanical means consisting of 133 control rods and six adjustable radial reflector plates. The optimized reactor core configuration, along with its intrinsic control system, allows for the power plant to operate safely for more than a decade between refuelings from a typical central heating plant or the basement of a multilevel office building. The work also included a preliminary investigation of the nonnuclear part of the energy supply system including heat exchangers and the turbine-driven, electricity-generating system.