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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
2021 Student Conference
April 8–10, 2021
Virtual Meeting
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
NC State celebrates 70 years of nuclear engineering education
An early picture of the research reactor building on the North Carolina State University campus. The Department of Nuclear Engineering is celebrating the 70th anniversary of its nuclear engineering curriculum in 2020–2021. Photo: North Carolina State University
The Department of Nuclear Engineering at North Carolina State University has spent the 2020–2021 academic year celebrating the 70th anniversary of its becoming the first U.S. university to establish a nuclear engineering curriculum. It started in 1950, when Clifford Beck, then of Oak Ridge, Tenn., obtained support from NC State’s dean of engineering, Harold Lampe, to build the nation’s first university nuclear reactor and, in conjunction, establish an educational curriculum dedicated to nuclear engineering.
The department, host to the 2021 ANS Virtual Student Conference, scheduled for April 8–10, now features 23 tenure/tenure-track faculty and three research faculty members. “What a journey for the first nuclear engineering curriculum in the nation,” said Kostadin Ivanov, professor and department head.
Dong Won Lee et al.
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 48-51
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | dx.doi.org/10.13182/FST09-A8874
Articles are hosted by Taylor and Francis Online.
In order to verify the integrity of the first wall (FW) of the International Thermonuclear Experimental Reactor (ITER) the fabricated Be/Cu mock-ups were tested at the TSEFEY, e-beam facility, in Efremov, Russia. The Be/Cu mock-ups were joined with CuCrZr for a heat sink material among the Cu alloys and 316L austenitic stainless steel (SS316L) tubes for a coolant and then, joined with Be tiles for an armor material. Hot Isostatic Pressing (HIP) was used as a manufacturing method at 1050 °C, 100 MPa for 2 hours for a Cu/SS joining and at 620 °C, 100 MPa for 2 hours for a Be/Cu joining. The high heat flux (HHF) tests were performed for two Be/Cu mock-ups with a 2.5 MW/m2 heat flux and 80 sec durations, which were determined from a preliminary analysis with ANSYS-11. The temperature results from the test showed a good agreement with the analysis results and the fatigue lifetime was evaluated from the strain analysis results.
