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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
José Ramón Ramírez Sánchez, John Garcia, R. T. Perry
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 524-527
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9237
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For environmental reasons, it was proposed to remove the lead shielding in the front panel of a glove box and replace it with another material. This technical note shows that steel could be used. Also, the thickness of steel required to maintain acceptable doses to an operator is determined. Computer modeling and analysis show that 3.175 cm (1¼ in.) of steel is required to maintain the same dose to the operator from gamma radiation as 0.635 cm (¼ in.) of lead. However, it was demonstrated that source placement and geometry play a large role in the operator's dose independent of the structural material because of streaming through ports and windows. Because of streaming, the dose received through the metal in the front panel was not the dominant source of radiation to the operator. It was found that 1.5875 cm (5/8 in.) of steel could be used in the panel.