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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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Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Gabriel Ghita, Glenn Sjoden, James Baciak
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 319-331
Technical Paper | Radiation Protection | doi.org/10.13182/NT07-A3879
Articles are hosted by Taylor and Francis Online.
Plutonium-beryllium (Pu-Be) sources can be used as didactic source materials for special nuclear materials (SNM) detection evaluation protocols. Since limited specific information exists for many of the Pu-Be sources currently in service, before using a Pu-Be source for field studies, the leakage radiation of neutrons and gamma rays from the source must be fully assessed. Most Pu-Be sources have an outer stainless steel jacket and an inner tantalum jacket, with the Pu-Be homogeneously distributed throughout the inner jacket. To fully characterize the net leakage terms from our Pu-Be source, we applied three-dimensional radiation transport computations, including Monte Carlo (MCNP5) and deterministic (PENTRAN) methodologies. The transport model for our Pu-Be capsule is based on limited schematic and technical data. To define the decay history and resulting source spectrum, exothermic [alpha-neutron (,n)] reactions are modeled using OrigenArp in the SCALE5 package. For transport modeling purposes, the intermetallic Pu-Be compound was treated as an intimate mixture of plutonium and beryllium, based on the manufacturer's mass specifications. The net capsule leakage was derived using transport computations, and an iterative estimation of plutonium age was performed. Computational results for net leakage are in agreement with the manufacturer's specification of neutron yield and dose rate. We also combined computational results with experimental measurement data to fully validate our computational methods. We have successfully achieved agreement between computational and experimental data for our Pu-Be source leakage, and we are using the results at the Florida Institute of Nuclear Detection and Security to evaluate a prototype SNM neutron detector array for parcel screening and national security applications.