ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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Nuclear Science and Engineering
June 2024
Nuclear Technology
May 2024
Fusion Science and Technology
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.
Paul W. Humrickhouse, Paul P. H. Wilson
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 166-175
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3754
Articles are hosted by Taylor and Francis Online.
A model of the University of Wisconsin Nuclear Reactor has been developed using MCNP5. Benchmarking of the model has centered on available reactor operations data from the original loading of the current TRIGA Fuel Life Improvement Program core, including control element differential worth curves and axial flux maps. By simulating the experimental measurement procedure for control element worth, integral worth values obtained for three control blades are within 6% of measured values. The comparison of simulated and measured axial thermal flux profiles suggests the need to improve the definition of the core temperatures and detailed isotopics. Future plans include modeling full-power (1 MW), high-temperature operation and burnup calculations to obtain current fuel definitions.