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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.
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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
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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Yasushi Seki, Hiromasa Iida, Robert T. Santoro, Hiromitsu Kawasaki, Michinori Yamauchi
Fusion Science and Technology | Volume 2 | Number 2 | April 1982 | Pages 272-285
Technical Paper | Shielding | doi.org/10.13182/FST82-A20760
Articles are hosted by Taylor and Francis Online.
The effects of radiation streaming through the neutral beam injector (NBI) port and divertor throat of a tokamak fusion reactor, the INTOR-J, was evaluated using Monte Carlo and discrete ordinates methods. Radiation streaming through the NBI port is found to be tolerable when a thick drift tube support acts as an effective shield. Neutron streaming through the divertor throat, however, makes the shutdown dose too high for personnel access into the reactor room. The radiation levels in the reactor room resulting from leakage through the NBI room walls are far smaller than that from leakage through the bulk shield, except behind the NBI room. The Monte Carlo-Monte Carlo and discrete ordinates—Monte Carlo coupling techniques used in the present study are shown to be very effective for the radiation streaming calculations.