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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.
J. Manuel Perlado, Lorenzo Malerba, Tomás Díaz de la Rubia
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 840-847
Inertial Fusion Technology | doi.org/10.13182/FST98-A11963717
Articles are hosted by Taylor and Francis Online.
An extreme condition in Inertial Fusion Energy (IFE) reactors will be the very high neutron dose rate from each burst of high gain targets. The effect of pulsed damage on the structural materials of the reactor chamber needs to be examined and its actual importance carefully assessed.
A first calculation of neutron spectra and intensities in one burst of directly driven target (pR ≈ 4 g.cm−2, 3 Hz) yields, for a ≈ 500 MJ shot of neutrons, a rate of ≈ 7 × 1020 n.s−1, the total time of deposition on the chamber walls being of ≈ 1 μs. This corresponds to a collisional parameter of 0.1 dpa/burst (in Fe), which gives an average damage rate of ≈ 3.8 dpa/year. The evolution in time of collisional damage is also presented.
Our work focuses on cubic silicon carbide (β-SiC) as a base for the next generation of low-activation materials. The Molecular Dynamics (MD) code MDCASK allows the description of the interaction of high energy recoils with the SiC lattice, by using a modification of the many-body semi-empirical inter-atomic Tersoff potential, merged with a repulsive binary potential obtained from ab initio calculations. A new assessment of previous works is presented. Preliminary values of threshold displacement energies are given and the observation of recombination barriers is reported. As a first step for a future intra- and inter-pulse damage study, by means of Kinetic Monte-Carlo (KMC) diffusion calculations, 3 and 5 keV Si-recoil-induced cascade simulations are analysed, discussing excitation and defects' characteristics in both sub-lattices: differences with respect to earlier works are found. Finally, the simulations of accumulations of up to 25 recoils of 500 eV and 1 keV are examined, in order to get a deeper insight into the damage state produced inside the material by intensive and prolonged irradiation in the absence of self-annealing.