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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
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.
J. G. Goodwin, F. R. Lorenz
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 49-56
Technical Paper | doi.org/10.13182/NSE59-A25626
Articles are hosted by Taylor and Francis Online.
Five 30-lb, 4-in. diam iodide hafnium ingots representing material typical of that utilized for the Shippingport PWR were fabricated into strip. Typical tensile, impact, hardness, corrosion test weight gain, electrical resistivity, and chemical analysis values were obtained by testing samples from each strip. The effect of irradiation on the impact strength and hardness of hafnium strip was investigated by subjecting a total of 36 subsized Izod impact specimens to irradiation for two cycles in the MTR. A duplicate group of nonirradiated specimens was used as a control group. The mechanical, physical, and corrosion property measurements for the nonirradiated and irradiated samples showed no physically significant differences attributable to chemical analysis. The impact strength and hardness values for the irradiated specimens showed differences which were attributable to the integrated neutron flux received.
