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Remembering Joseph M. Hendrie
Joseph M. Hendrie
To those of us who knew Joe, even prior to his appointment as chair of the Nuclear Regulatory Commission, it is an understatement to say that he was a larger-than-life member of the nuclear science and technology enterprise. He was best known to the broader community for two major accomplishments: the design and construction of the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory and the creation of the standard review plan (SRP) for the U.S. Atomic Energy Commission.
In addition to the products of these endeavors becoming major fundaments to their respective communities, they were uniquely Joe. The safety analysis report for the HFBR was written essentially single-handedly by him. This was true of the SRP as well, which became the key safety review document for the NRC as it performed safety reviews for the growing number of power reactor applications in the United States. His deep technical knowledge of nuclear engineering and his extraordinary management skills made this possible.
Jin-Yang Li, Long Gu, Hu-Shan Xu, Yong Dai, You-Peng Zhang, Cun-Feng Yao, Rui Yu, Lu Zhang, Sheng Yang
Nuclear Technology | Volume 207 | Number 2 | February 2021 | Pages 270-284
Technical Paper | doi.org/10.1080/00295450.2020.1757963
Articles are hosted by Taylor and Francis Online.
To study the burnup features of accelerator-driven subcritical systems (ADSs), simplified transmutation trajectories are imperative to make the simulation process more effective with acceptable precision. This process has long been considered a challenging task since the construction of simplified burnup chains often need complex judgments and experiences. Additionally, the burnup analysis of ADSs requires more specific burnup chains for some important isotopes with minor actinides (MAs) and long-lived fission products (LLFPs) included. However, some general burnup codes lack these chains or pack some particularly important isotopes into a kind of pseudo nuclide. In this context, a PyNE-based burnup module (PyNE-Burn) has been developed to solve the burnup problem in ADSs, where three types of isotopes have been considered to construct the simplified burnup chains and weight-sorted judgment criteria have been proposed to determine which nuclides should be included. Moreover, the scan-mode-method-based high-order differential expression has been employed to substitute the legacy method in solving the linearized burnup chains. Finally, numerical tests have been carried out to demonstrate that the PyNE-Burn module has acceptable accuracy and can be used in dealing with the burnup problem in ADSs.