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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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
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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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Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
L. G. Mooney
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 157-172
Technical Paper | doi.org/10.13182/NSE71-A19664
Articles are hosted by Taylor and Francis Online.
Calculations were performed to determine energy and angle distributions of the fission-product gamma ray, air-ground secondary gamma ray, and neutron fluence incident on structures resulting from the detonation of a representative intermediate-yield thermonuclear weapon 100 m above the ground. These energy and angle distributions were used as input data to the ANISN discrete ordinates code to calculate the penetration of the radiation through various thicknesses of type O-HW1 concrete. The production and transport of concrete capture gamma rays were calculated in tandem with the neutron transport. The penetration results were used to calculate the various radiation components at the center of a simple concrete blockhouse. The inside lengths and widths of the structure varied from 10 to 50 ft and the inside height was fixed at 10 ft. Wall and roof thicknesses varied from 6 to 60 in. The results of the calculations were expressed as structure protection coefficients (dose at the receiver per unit free-field dose). The neutron dose was found to contribute the highest fraction of the total dose for wall and roof thicknesses up to 12 in. For thicknesses of 18 in. and more, the airground secondary gamma rays and concrete capture gamma rays were found to dominate, becoming increasingly more important with increasing thickness. The relative magnitude of each component did not vary significantly with structure size; however, all components were found to decrease with an increase in structure size for a given wall and roof thickness.