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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
D. Steiner
Nuclear Technology | Volume 9 | Number 1 | July 1970 | Pages 83-92
Reactor | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28730
Articles are hosted by Taylor and Francis Online.
The neutronic behavior of fusion reactor blankets is discussed, and transport-theory calculations are presented for two blanket designs. The areas investigated are (1) tritium breeding, (2) nuclear heating, and (3) neutron irradiation effects within the vacuum wall of the blanket, i.e., neutron-induced (a) atom displacements and (b) helium and hydrogen production. The two blanket designs considered consist of niobium as the vacuum wall and structural material, lithium or lithium in combination with lithium-beryllium fluoride (called “flibe”) as the coolant, and graphite as the neutron moderator and reflector. The results indicate that the tritium breeding potential of both designs is promising. The results also show that the tritium-breeding and nuclear heating characteristics of the lithium-flibe blanket are inferior to those of the lithium blanket. The calculated atom displacement rates and production rates of helium and hydrogen within the vacuum wall are essentially the same for both blanket designs.