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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Penn State and Westinghouse make eVinci microreactor plan official
Penn State and Westinghouse Electric Company are working together to site a new research reactor on Penn State’s University Park, Pa., campus: Westinghouse’s eVinci, a HALEU TRISO-fueled sodium heat-pipe reactor. Penn State has announced that it submitted a letter of intent to host and operate an eVinci reactor to the Nuclear Regulatory Commission on February 28 and plans to engage with the NRC on specific siting decisions. Penn State already boasts the Breazeale reactor, which began operating in 1955 as the first licensed research reactor at a university in the United States. At 70, the Breazeale reactor is still in operation.
G. Montet, G. Hennig, A. Kurs
Nuclear Science and Engineering | Volume 1 | Number 1 | March 1956 | Pages 33-52
Technical Paper | doi.org/10.13182/NSE56-A17656
Articles are hosted by Taylor and Francis Online.
The distribution of displaced carbon atoms in irradiated graphite has been studied with a radioactive tracer technique. Radiation-damaged graphite containing radioactive displaced carbon (C11) atoms was prepared by cyclotron or betatron irradiation. After partial annealing, the distribution of the C11 was determined by controlled oxidation and counting of CO2 gas samples. Experiments on various types of weakly irradiated graphite indicate that a very small fraction of the displaced atoms are driven to particle surfaces during the annealing process, the fraction being higher for natural graphite than for artificial graphite and varying inversely with graphite particle size. Experimental conditions were varied to determine their effects on the distribution of the disaplaced atoms. Data obtained indicate that very little reintegration of displaced atoms occurs during short neutron bombardments at room temperature, that about 80% of the atoms reintegrate into vacancies during annealing below 400°C and that the remainder coalesce into complexes, and that large scale motion of the complexes begins at 400°C and ceases at approximately 1000°C. At this latter temperature the complexes appear to reach their final positions; however, they are relatively loosely bound and integrate progressively at these sites until they become indistinguishable from lattice atoms near 1700°C. Vacancies resulting from prior irradiation were found by tracer experiments to be effective traps for displaced atoms so that, during annealing of subsequent damage, the fraction that reaches the particle surfaces decreases rapidly with bombardment.