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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
NRC okays construction permits for Hermes 2 test facility
The Nuclear Regulatory Commission announced yesterday that it has directed staff to issue construction permits to Kairos Power for the company's proposed Hermes 2 nonpower test reactor facility to be built at the Heritage Center Industrial Park in Oak Ridge, Tenn. The permits authorize Kairos to build a facility with two 35-MWt test reactors that would use molten salt to cool the reactor cores.
Alberto Previti, Alberto Brighenti, Damien Raynaud, Barbara Vezzoni
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2459-2483
Research Article | doi.org/10.1080/00295639.2023.2189535
Articles are hosted by Taylor and Francis Online.
The design and safety assessment of nuclear reactors rely on a combination of calculations performed by several simulation packages, each dedicated to modeling a specific ensemble of phenomena. To treat the complexity of the physical problem, appropriate software architectures and methodologies to trace and implement user needs are of paramount importance to fulfill the needs of all the possible stakeholders. This work proposes a systematic approach to break the complexity of constructing a lattice neutronics platform that is one of the simulation packages needed in nuclear reactor analysis. After reviewing the state of the art of current methods applied in reactor physics engineering, the work concentrates on identifying the applicable software architecture strategies and on discussing advantages and drawbacks. While the specific target is the neutronics code APOLLO3®, the subsequent categorization and analysis of user needs written in the form of formal requirements allow for defining a unified approach to design an effective, industrial-grade, and future-proof calculation platform. Subsequent presentation of typical use cases involved in developing deterministic lattice calculation schemes allows linking the formal definition of use cases and software architecture with the actual application to a specific calculation setting. This work aims, therefore, at proposing an innovative viewpoint to tackle large software developments applicable in the nuclear industry. The research presented in this paper has been developed at Framatome in the context of the lattice neutronics work package of the H2020 CAMIVVER project.