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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Meng-Jen (Vince) Wang, Glenn E. Sjoden
Nuclear Science and Engineering | Volume 195 | Number 11 | November 2021 | Pages 1154-1175
Technical Paper | doi.org/10.1080/00295639.2021.1906587
Articles are hosted by Taylor and Francis Online.
We present a systematic computational dose rate evaluation for a packaged 1.8-Ci 241AmBe source using both Monte Carlo and deterministic approaches, with some experimental measurements for correlation. The 241AmBe source is stored in an extended 55-gal-drum container. Computational dose rate analysis is performed using MCNP6 (Monte Carlo) and PENTRAN (SN) on the Center for High Performance Computing system at the University of Utah. Limited information is available regarding internal drum shielding construction, and a reverse engineering approach is presented here to estimate the dose rate and compare with measured experimental values. Our analysis shows that a deterministic three-dimensional quadrature (SN) and anisotropic scattering (PN) order of S20P2 is sufficient for dose rate calculations of the 241AmBe source with polyethylene surrounding the source as shielding material. Higher quadrature orders, i.e., at least S70 for neutrons and S40 for photons, are needed in the presence of air due to severe streaming effects, and this is dependent upon the distance between the source and measurement locations. With air surrounding the 241AmBe source, the Monte Carlo method is considered to be better for neutron dose calculations while the SN method is considered better for photon dose calculations. Good agreement from both computational verification and experimental validation are observed for the dose “hot spot” in the extended 55-gal drum. The differences noted between the MCNP6/PENTRAN calculations are within 6% for the neutron dose rate and 30% for the photon dose rate. It is observed that more than 95% of the dose is attributed to neutrons. Detailed studies including a literature data validation, PENTRAN SN convergence study, buildup factor analysis, and dose rates with different shielding materials are presented in the narrative.
