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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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 issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
M. J. Loughlin, E. I. Polunovskiy, S. Zheng
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 271-275
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Radiation Transport and Protection | doi.org/10.13182/NT11-A12299
Articles are hosted by Taylor and Francis Online.
The nuclear fusion devices using the principle of magnetic plasma confinement such as the ITER tokamak are going to consist of a variety of highly heterogeneous, nuclear-radiation-sensitive components. The compactness of the ITER tokamak makes it difficult to rely on large safety margins. Under these circumstances the use of reasonably heterogeneous, highly precise models for the nuclear analysis is going to be unavoidable. Techniques have been developed to create these models based as directly as possible on computer-aided design (CAD) specifications, thereby retaining fidelity and speeding up the process. Inevitably, some adaption of the CAD model is necessary as part of the conversion process.This paper describes the approach to the production of the models for nuclear analysis for ITER developed by the neutronics group in the ITER Organization. Algorithmization of the CAD-based modeling for MCNP code has been undertaken.