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2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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My story: Stanley Levinson—ANS member since 1983
Levinson early in his career and today.
As a member of the American Nuclear Society, I have been to many conferences. The International Conference on Probabilistic Safety Assessment and Analysis (PSA ’25), embedded in ANS Annual Meeting in Chicago in June, held special significance for me with the PSA ’25 opening plenary session recognizing the 50th anniversary of the publication of WASH-1400, which helped define my career. Reflecting on that milestone sent me back to 1975, when I was just an undergraduate student studying nuclear engineering at Rensselaer Polytechnic Institute (RPI) in Troy, N.Y., focusing on my mechanics, fluids, and thermodynamic classes as well as my first set of nuclear engineering classes. At that time—and many times since—the question “Why nuclear engineering?” was raised.
Mohammad Abdul Motalab, Woosong Kim, Yonghee Kim
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 122-137
Technical Paper | doi.org/10.1080/00295450.2017.1414541
Articles are hosted by Taylor and Francis Online.
This paper reports on the improvement of the power coefficient of reactivity (PCR) and minimization of the coolant void reactivity (CVR) of a CANDU6 reactor. A burnable absorber of Er2O3 (erbia) was mixed homogeneously with UO2 fuel in the central fuel element to maximize the Doppler broadening and minimize the CVR of the CANDU6 reactor. In this study, recovered uranium (RU) with 0.9 wt% 235U enrichment was utilized in the advanced CANFLEX fuel bundle instead of natural uranium (NU). First, the optimal loading of erbia was investigated through lattice-based analysis, and its impact on the lattice characteristics was examined. In particular, both the fuel Doppler effect and CVR were evaluated for the RU-loaded lattice. For a more reliable analysis, a three-dimensional (3-D) equilibrium core was determined based on the standard time-average methods for erbia-loaded CANDU6 cores using the Serpent-COREDAX/CANDU code system. The core analysis was based on a hybrid two-step method in which the lattice analysis was performed by the Serpent Monte Carlo code, and the 3-D whole-core analysis was done using a diffusion theory–based nodal code named COREDAX. For the derived equilibrium cores, the core performances were evaluated in terms of the fuel burnup and power profile. Additionally, the safety parameters, including the PCR and CVR, were evaluated for the equilibrium core conditions. The safety parameters of the 3-D whole core were compared with those obtained with simple lattice-based analysis. It was observed in the analysis that Er-loaded CANFLEX-RU fuel provides a 60% more negative fuel temperature coefficient than standard CANDU-NU fuel.