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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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Orlando, FL|Renaissance Orlando at SeaWorld
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Candidates announced for 2025 ANS leadership positions
As the U.S. election season finally comes to an end, the annual American Nuclear Society election season is right around the corner. Seventeen candidates have been nominated for the positions of ANS vice president/president-elect, treasurer, and six positions on the board of directors (four U.S. directors, one non-U.S. director, and one student director). Ballots will be sent via email on Tuesday, March 4, 2025, and must be submitted by 1:00 p.m. (EDT) on Tuesday, April 15, 2025.
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.