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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
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.
Ivo Kodeli, Daniel L. Aldama, Piet F. A. de Leege, David Legrady, J. Eduard Hoogenboom, Pat Cowan
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 210-224
Technical Note | doi.org/10.13182/NSE07-A2723
Articles are hosted by Taylor and Francis Online.
A special-purpose multigroup cross-section library optimized for nuclides and reactions arising in nuclear oil well logging was prepared for use in deterministic and Monte Carlo transport codes. The library is based on the recent ENDF/B-VI.8 evaluation, which includes among others improved oxygen and chlorine cross sections. A 175-neutron and 45-gamma-ray energy group structure was selected as a way to take into account the requirements of oil well-logging applications. This library is expected to improve the prediction of the neutron and gamma spectra at the detector positions of the logging tool. For the Monte Carlo codes the library can be useful in particular in calculations requiring multigroup cross sections, like adjoint or MIDWAY methods. Furthermore, comparison of deterministic and Monte Carlo calculations using the same or similar cross sections can reveal the uncertainty linked to the computational method and model. The use of the library for the interpretation of the carbon/oxygen neutron logging measurements in boreholes was studied. Preparation and testing of this library, which is available from the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Data Bank, is described.