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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.
2024 ANS Annual Conference
June 9–12, 2024
Las Vegas, NV|The Mirage
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NRC seeks comments on new fee schedule for FY 2024
The Nuclear Regulatory Commission is asking for feedback on proposed changes to the annual, licensing, inspection, and special projects fees for fiscal year 2024.
The proposed fee rule, published February 20 in the Federal Register, is based on the FY 2024 Congressional Budget Justification as a full-year appropriation, but it has not yet been enacted. The final rule will be based on the NRC’s actual appropriation, and the agency will update the final fee schedule as appropriate.
Ernestas Narkūnas, Artūras Šmaižys, Povilas Poškas, Audrius Šimonis, Valerij Naumov, Dmitrij Ekaterinichev
Nuclear Technology | Volume 208 | Number 12 | December 2022 | Pages 1876-1889
Technical Paper | doi.org/10.1080/00295450.2022.2092367
Articles are hosted by Taylor and Francis Online.
This paper presents an evaluation of the gamma-radiation shielding capabilities of the CONSTOR® RBMK-1500/M2 cask dedicated for the storage of spent nuclear fuel at the Ignalina Nuclear Power Plant in Lithuania. This cask is of a new design with increased capacity compared to the older CONSTOR RBMK-1500 and CASTOR RBMK-1500 casks and new facility for their interim storage has been installed. “Hot tests” conducted at this new interim storage facility included dose rate measurements of the CONSTOR RBMK-1500/M2 casks that were loaded with particular sets of spent nuclear fuel half-assemblies and transferred to the facility for subsequent interim storage. Having actual data on the spent nuclear fuel half-assemblies that were loaded into a particular cask, gamma dose rate modeling of that CONSTOR RBMK-1500/M2 cask (namely, cask ID 153) was performed. Modeling was performed using the MCNP (based on the stochastic mathematical method) and the VISIPLAN and MicroShield (both based on the deterministic mathematical method) computer codes. The obtained modeling results were compared between the different codes and with the measurement results. The performed analysis revealed that modeled gamma dose rates are in good agreement for all analyzed codes, although agreement with the measurements is to some extent less.